Joshua Schlegel

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Joshua Schlegel

Joshua P. Schlegel

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Biography

Missouri University of Science and Technology - Nuclear Engineering

Assistant Professor at Missouri S&T
Research
Joshua
Schlegel
Greater St. Louis Area
I am a professor in Nuclear Engineering specializing in nuclear reactor thermal hydraulics, or the motion of fluid and energy in nuclear reactor systems. I work extensively on two-phase flows including interfacial area transport and bubble hydrodynamics and am branching out into exciting new areas such as phase change materials and passive safety systems. As an instructor, I am working to bring a more hands-on approach to the classroom through problem-based, team-based learning techniques and am working to develop a laboratory course on thermal-fluids with laboratory activities based on ongoing research.

Missouri S&T Nuclear Engineering: https://nuclear.mst.edu/facultystaffandfacilities/faculty/schlegel/
Google Scholar: https://scholar.google.com/citations?user=mhpWWK8AAAAJ&hl=en
ResearchGate: https://www.researchgate.net/profile/Joshua_Schlegel

Experience

  • Purdue University

    Postdoctoral Research Associate

    • Obtained over $700,000 in total funding for experimental research
    • Developed and implemented a rigorous review program for external reports
    • Managed and advised several teams of graduate students; guided graduate students through the submission of five papers to refereed journals
    • Developed dynamic solver for interfacial area transport and void transport equations, coupled with prediction of pressure drop and gas velocity based on the two-fluid model
    • Directed development of droplet-capable conductivity probes for local measurements in annular flow

  • Missouri S&T

    Assistant Professor

    • Educating the next generation of nuclear scientists and engineers
    o Revised and reformatted Reactor Fluid Mechanics (NUC ENG 3221) and Reactor Heat Transfer
    (NUC ENG 3223) to implement team-based and problem-based teaching methods
    o Pushed the inclusion of additional instruction and industry involvement in Nuclear Systems
    Design I/II (Nuc Eng 4496 and 4497)
    o Established professional development seminar series for Nuclear Engineering students
    • Researching solutions to thermal-hydraulics challenges in a variety of systems
    o Established of Thermal Hydraulics Experiment, Modeling, and Engineering Simulation (THEMES) laboratory at Missouri S&T
    o Developed a new, modular two-fluid model code development with interfacial area transport
    to investigate bubble coalescence and breakup and other key thermal-hydraulic phenomena
    o Developing of advanced, droplet-capable electrical resistivity probes
    o Measuring and modeling condensation heat transfer in Small Modular Reactor (SMR) safety
    systems
    o Developing and assessing phase change materials for nuclear and commercial applications
    • Ensuring excellence in the undergraduate program
    o Overhauled monitoring of ABET performance criteria and continuous-improvement process
    o Initiated review and overhaul of academic program

Education

  • Purdue University

    Doctor of Philosophy (Ph.D.)

    Nuclear Engineering
    Thesis Title: Multidimensional Two-Phase Flow Structure in Systems with Large Diameter

  • Purdue University

    Postdoctoral Research Associate


    • Obtained over $700,000 in total funding for experimental research • Developed and implemented a rigorous review program for external reports • Managed and advised several teams of graduate students; guided graduate students through the submission of five papers to refereed journals • Developed dynamic solver for interfacial area transport and void transport equations, coupled with prediction of pressure drop and gas velocity based on the two-fluid model • Directed development of droplet-capable conductivity probes for local measurements in annular flow

Publications

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Direct Synthesis of Radioactive Gold Nanoparticles Using a Research Nuclear Reactor

    Journal of Nuclear Medicine Technology

    We report the synthesis of radioactive gold nanoparticles in a single step process with appropriate activity and size to be used in cancer treatment and diagnosis. Methods: A 2 mM solution of gold chloride (HAuCl4), 1 mM of polyvinylpyrrolidone (PVP, M.W: 360,000), and 60 mM of 2-propanol was prepared in deionized water. Seven different samples of the solution were irradiated in a total neutron flux of 7.45 x 1012 n/cm2s in a research reactor for 0.5, 1, 3, 5, 10, 30, and 60 minutes. The resulting nanoparticles were characterized for morphology and chemical composition using a Transmission Electron Microscopy (TEM) and ImageJ. Results: The nanoparticles obtained presented particle-sizes between 3 nm and 450 nm. It is found that the average particle size depends on the time of irradiation, with longer irradiation time producing smaller nanoparticles. Irradiation for 10 minutes were found to produce nanoparticles with suitable characteristic for potential cancer treatment and diagnosis (average size: 50 nm, activity: 6.85 MBq / mL). Conclusion: Direct production of chemically stable, radioactive, gold nanoparticles was successfully accomplished using the Missouri S&T Research Nuclear Reactor (MSTR). The nanoparticles obtained present physical, and radioactive characteristics potentially useful in cancer treatment and diagnosis.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Direct Synthesis of Radioactive Gold Nanoparticles Using a Research Nuclear Reactor

    Journal of Nuclear Medicine Technology

    We report the synthesis of radioactive gold nanoparticles in a single step process with appropriate activity and size to be used in cancer treatment and diagnosis. Methods: A 2 mM solution of gold chloride (HAuCl4), 1 mM of polyvinylpyrrolidone (PVP, M.W: 360,000), and 60 mM of 2-propanol was prepared in deionized water. Seven different samples of the solution were irradiated in a total neutron flux of 7.45 x 1012 n/cm2s in a research reactor for 0.5, 1, 3, 5, 10, 30, and 60 minutes. The resulting nanoparticles were characterized for morphology and chemical composition using a Transmission Electron Microscopy (TEM) and ImageJ. Results: The nanoparticles obtained presented particle-sizes between 3 nm and 450 nm. It is found that the average particle size depends on the time of irradiation, with longer irradiation time producing smaller nanoparticles. Irradiation for 10 minutes were found to produce nanoparticles with suitable characteristic for potential cancer treatment and diagnosis (average size: 50 nm, activity: 6.85 MBq / mL). Conclusion: Direct production of chemically stable, radioactive, gold nanoparticles was successfully accomplished using the Missouri S&T Research Nuclear Reactor (MSTR). The nanoparticles obtained present physical, and radioactive characteristics potentially useful in cancer treatment and diagnosis.

  • Modified Distribution Parameter for Churn-Turbulent Flow in Large Diameter Channels

    Nuclear Engineering and Design

    Two phase flows in large diameter channels are important in a wide range of industrial applications, but especially in analysis of nuclear reactor safety for the prediction of BWR behavior and safety analysis in PWRs. To remedy an inability of current drift-flux models to accurately predict the void fraction in churn-turbulent flows in large diameter pipes, extensive experiments have been performed in pipes with diameters of 0.152 m, 0.203 m and 0.304 m to collect area-averaged void fraction data using electrical impedance void meters. The standard deviation and skewness of the impedance meter signal have been used to characterize the flow regime and confirm previous flow regime transition results. By treating churn-turbulent flow as a transition between cap-bubbly dispersed flow and annular separated flow and using a linear ramp, the distribution parameter has been modified for churn-turbulent flow. The modified distribution parameter has been evaluated through comparison of the void fraction predicted by the drift-flux model and the measured void fraction.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Direct Synthesis of Radioactive Gold Nanoparticles Using a Research Nuclear Reactor

    Journal of Nuclear Medicine Technology

    We report the synthesis of radioactive gold nanoparticles in a single step process with appropriate activity and size to be used in cancer treatment and diagnosis. Methods: A 2 mM solution of gold chloride (HAuCl4), 1 mM of polyvinylpyrrolidone (PVP, M.W: 360,000), and 60 mM of 2-propanol was prepared in deionized water. Seven different samples of the solution were irradiated in a total neutron flux of 7.45 x 1012 n/cm2s in a research reactor for 0.5, 1, 3, 5, 10, 30, and 60 minutes. The resulting nanoparticles were characterized for morphology and chemical composition using a Transmission Electron Microscopy (TEM) and ImageJ. Results: The nanoparticles obtained presented particle-sizes between 3 nm and 450 nm. It is found that the average particle size depends on the time of irradiation, with longer irradiation time producing smaller nanoparticles. Irradiation for 10 minutes were found to produce nanoparticles with suitable characteristic for potential cancer treatment and diagnosis (average size: 50 nm, activity: 6.85 MBq / mL). Conclusion: Direct production of chemically stable, radioactive, gold nanoparticles was successfully accomplished using the Missouri S&T Research Nuclear Reactor (MSTR). The nanoparticles obtained present physical, and radioactive characteristics potentially useful in cancer treatment and diagnosis.

  • Modified Distribution Parameter for Churn-Turbulent Flow in Large Diameter Channels

    Nuclear Engineering and Design

    Two phase flows in large diameter channels are important in a wide range of industrial applications, but especially in analysis of nuclear reactor safety for the prediction of BWR behavior and safety analysis in PWRs. To remedy an inability of current drift-flux models to accurately predict the void fraction in churn-turbulent flows in large diameter pipes, extensive experiments have been performed in pipes with diameters of 0.152 m, 0.203 m and 0.304 m to collect area-averaged void fraction data using electrical impedance void meters. The standard deviation and skewness of the impedance meter signal have been used to characterize the flow regime and confirm previous flow regime transition results. By treating churn-turbulent flow as a transition between cap-bubbly dispersed flow and annular separated flow and using a linear ramp, the distribution parameter has been modified for churn-turbulent flow. The modified distribution parameter has been evaluated through comparison of the void fraction predicted by the drift-flux model and the measured void fraction.

  • Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow

    Progress in Nuclear Energy

    While high-fidelity 3D simulation is important for model validation, scientific understanding, and some design calculations, it can be prohibitively expensive for system design applications or applications involving large geometries. Thus, there is also a need for practical, simplified approaches for those applications. The two-fluid model strikes a balance between detail and computational resources, but requires the accurate specification of several key constitutive models. These include (1) interfacial forces, (2) interfacial area concentration, (3) two-phase turbulence, and (4) wall and bulk boiling and condensation. In many modern CFD packages, uncertainties in the local interfacial area concentration can have strong effects on the ability to predict the other key parameters. This paper demonstrates that the drag force in 3D CFD can be formulated in much the same way as in 1D system analysis codes and that this approach can be used to formulate a model for interfacial area concentration. This approach may open a method to calculate the interfacial forces without the need for interfacial area transport equations. This reduces the number of differential equations and avoids the modeling challenges associated with bubble breakup and coalescence kernels and the need to specify the inlet interfacial area concentration a priori. The new method is expected to decouple the effects of interfacial area uncertainty and calibrated coefficients, and should provide reasonable local bubble diameters for both group-1 and group-2 bubbles. The approaches proposed in this study are applicable to two-phase flow simulations in rather simple geometries such as upward two-phase flow in vertical channels. In view of many applications for upward two-phase flow in vertical channels, including nuclear reactor systems, the proposed methods are considered useful.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Direct Synthesis of Radioactive Gold Nanoparticles Using a Research Nuclear Reactor

    Journal of Nuclear Medicine Technology

    We report the synthesis of radioactive gold nanoparticles in a single step process with appropriate activity and size to be used in cancer treatment and diagnosis. Methods: A 2 mM solution of gold chloride (HAuCl4), 1 mM of polyvinylpyrrolidone (PVP, M.W: 360,000), and 60 mM of 2-propanol was prepared in deionized water. Seven different samples of the solution were irradiated in a total neutron flux of 7.45 x 1012 n/cm2s in a research reactor for 0.5, 1, 3, 5, 10, 30, and 60 minutes. The resulting nanoparticles were characterized for morphology and chemical composition using a Transmission Electron Microscopy (TEM) and ImageJ. Results: The nanoparticles obtained presented particle-sizes between 3 nm and 450 nm. It is found that the average particle size depends on the time of irradiation, with longer irradiation time producing smaller nanoparticles. Irradiation for 10 minutes were found to produce nanoparticles with suitable characteristic for potential cancer treatment and diagnosis (average size: 50 nm, activity: 6.85 MBq / mL). Conclusion: Direct production of chemically stable, radioactive, gold nanoparticles was successfully accomplished using the Missouri S&T Research Nuclear Reactor (MSTR). The nanoparticles obtained present physical, and radioactive characteristics potentially useful in cancer treatment and diagnosis.

  • Modified Distribution Parameter for Churn-Turbulent Flow in Large Diameter Channels

    Nuclear Engineering and Design

    Two phase flows in large diameter channels are important in a wide range of industrial applications, but especially in analysis of nuclear reactor safety for the prediction of BWR behavior and safety analysis in PWRs. To remedy an inability of current drift-flux models to accurately predict the void fraction in churn-turbulent flows in large diameter pipes, extensive experiments have been performed in pipes with diameters of 0.152 m, 0.203 m and 0.304 m to collect area-averaged void fraction data using electrical impedance void meters. The standard deviation and skewness of the impedance meter signal have been used to characterize the flow regime and confirm previous flow regime transition results. By treating churn-turbulent flow as a transition between cap-bubbly dispersed flow and annular separated flow and using a linear ramp, the distribution parameter has been modified for churn-turbulent flow. The modified distribution parameter has been evaluated through comparison of the void fraction predicted by the drift-flux model and the measured void fraction.

  • Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow

    Progress in Nuclear Energy

    While high-fidelity 3D simulation is important for model validation, scientific understanding, and some design calculations, it can be prohibitively expensive for system design applications or applications involving large geometries. Thus, there is also a need for practical, simplified approaches for those applications. The two-fluid model strikes a balance between detail and computational resources, but requires the accurate specification of several key constitutive models. These include (1) interfacial forces, (2) interfacial area concentration, (3) two-phase turbulence, and (4) wall and bulk boiling and condensation. In many modern CFD packages, uncertainties in the local interfacial area concentration can have strong effects on the ability to predict the other key parameters. This paper demonstrates that the drag force in 3D CFD can be formulated in much the same way as in 1D system analysis codes and that this approach can be used to formulate a model for interfacial area concentration. This approach may open a method to calculate the interfacial forces without the need for interfacial area transport equations. This reduces the number of differential equations and avoids the modeling challenges associated with bubble breakup and coalescence kernels and the need to specify the inlet interfacial area concentration a priori. The new method is expected to decouple the effects of interfacial area uncertainty and calibrated coefficients, and should provide reasonable local bubble diameters for both group-1 and group-2 bubbles. The approaches proposed in this study are applicable to two-phase flow simulations in rather simple geometries such as upward two-phase flow in vertical channels. In view of many applications for upward two-phase flow in vertical channels, including nuclear reactor systems, the proposed methods are considered useful.

  • Experimental study of natural circulation instability with void reactivity feedback during startup transients for a BWR-type SMR

    Progress in Nuclear Energy

    The natural circulation boiling type SMR can experience flow instability during the startup transients due to the void reactivity feedback. A BWR-type natural circulation test loop has been built to perform the nuclear coupled startup transient tests for Purdue Novel Modular Reactor (NMR). This test loop is installed with different instruments to measure various thermal hydraulic parameters. The testing process can be monitored and controlled through PC with the assistance of LabVIEW procedure. The effects of power ramp rate on the flow instability during the nuclear coupled tests were investigated by controlling the power supply based on the point kinetics model with coolant void reactivity feedback. Two power ramp rates were investigated and the results were compared with those of the thermal hydraulic startup transients without void reactivity feedback. The time trace of power supply, system pressure, natural circulation rate, and void fraction profile are used to determine the flow stability during the transients. The results show that nuclear coupled startup transients also experience flashing instability and density wave oscillations. The power curves calculated from point kinetics model for startup transients show some fluctuations due to void reactivity feedback. However, the void reactivity feedback does not have significant effects on the flow instability during the startup procedure for the NMR.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Direct Synthesis of Radioactive Gold Nanoparticles Using a Research Nuclear Reactor

    Journal of Nuclear Medicine Technology

    We report the synthesis of radioactive gold nanoparticles in a single step process with appropriate activity and size to be used in cancer treatment and diagnosis. Methods: A 2 mM solution of gold chloride (HAuCl4), 1 mM of polyvinylpyrrolidone (PVP, M.W: 360,000), and 60 mM of 2-propanol was prepared in deionized water. Seven different samples of the solution were irradiated in a total neutron flux of 7.45 x 1012 n/cm2s in a research reactor for 0.5, 1, 3, 5, 10, 30, and 60 minutes. The resulting nanoparticles were characterized for morphology and chemical composition using a Transmission Electron Microscopy (TEM) and ImageJ. Results: The nanoparticles obtained presented particle-sizes between 3 nm and 450 nm. It is found that the average particle size depends on the time of irradiation, with longer irradiation time producing smaller nanoparticles. Irradiation for 10 minutes were found to produce nanoparticles with suitable characteristic for potential cancer treatment and diagnosis (average size: 50 nm, activity: 6.85 MBq / mL). Conclusion: Direct production of chemically stable, radioactive, gold nanoparticles was successfully accomplished using the Missouri S&T Research Nuclear Reactor (MSTR). The nanoparticles obtained present physical, and radioactive characteristics potentially useful in cancer treatment and diagnosis.

  • Modified Distribution Parameter for Churn-Turbulent Flow in Large Diameter Channels

    Nuclear Engineering and Design

    Two phase flows in large diameter channels are important in a wide range of industrial applications, but especially in analysis of nuclear reactor safety for the prediction of BWR behavior and safety analysis in PWRs. To remedy an inability of current drift-flux models to accurately predict the void fraction in churn-turbulent flows in large diameter pipes, extensive experiments have been performed in pipes with diameters of 0.152 m, 0.203 m and 0.304 m to collect area-averaged void fraction data using electrical impedance void meters. The standard deviation and skewness of the impedance meter signal have been used to characterize the flow regime and confirm previous flow regime transition results. By treating churn-turbulent flow as a transition between cap-bubbly dispersed flow and annular separated flow and using a linear ramp, the distribution parameter has been modified for churn-turbulent flow. The modified distribution parameter has been evaluated through comparison of the void fraction predicted by the drift-flux model and the measured void fraction.

  • Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow

    Progress in Nuclear Energy

    While high-fidelity 3D simulation is important for model validation, scientific understanding, and some design calculations, it can be prohibitively expensive for system design applications or applications involving large geometries. Thus, there is also a need for practical, simplified approaches for those applications. The two-fluid model strikes a balance between detail and computational resources, but requires the accurate specification of several key constitutive models. These include (1) interfacial forces, (2) interfacial area concentration, (3) two-phase turbulence, and (4) wall and bulk boiling and condensation. In many modern CFD packages, uncertainties in the local interfacial area concentration can have strong effects on the ability to predict the other key parameters. This paper demonstrates that the drag force in 3D CFD can be formulated in much the same way as in 1D system analysis codes and that this approach can be used to formulate a model for interfacial area concentration. This approach may open a method to calculate the interfacial forces without the need for interfacial area transport equations. This reduces the number of differential equations and avoids the modeling challenges associated with bubble breakup and coalescence kernels and the need to specify the inlet interfacial area concentration a priori. The new method is expected to decouple the effects of interfacial area uncertainty and calibrated coefficients, and should provide reasonable local bubble diameters for both group-1 and group-2 bubbles. The approaches proposed in this study are applicable to two-phase flow simulations in rather simple geometries such as upward two-phase flow in vertical channels. In view of many applications for upward two-phase flow in vertical channels, including nuclear reactor systems, the proposed methods are considered useful.

  • Experimental study of natural circulation instability with void reactivity feedback during startup transients for a BWR-type SMR

    Progress in Nuclear Energy

    The natural circulation boiling type SMR can experience flow instability during the startup transients due to the void reactivity feedback. A BWR-type natural circulation test loop has been built to perform the nuclear coupled startup transient tests for Purdue Novel Modular Reactor (NMR). This test loop is installed with different instruments to measure various thermal hydraulic parameters. The testing process can be monitored and controlled through PC with the assistance of LabVIEW procedure. The effects of power ramp rate on the flow instability during the nuclear coupled tests were investigated by controlling the power supply based on the point kinetics model with coolant void reactivity feedback. Two power ramp rates were investigated and the results were compared with those of the thermal hydraulic startup transients without void reactivity feedback. The time trace of power supply, system pressure, natural circulation rate, and void fraction profile are used to determine the flow stability during the transients. The results show that nuclear coupled startup transients also experience flashing instability and density wave oscillations. The power curves calculated from point kinetics model for startup transients show some fluctuations due to void reactivity feedback. However, the void reactivity feedback does not have significant effects on the flow instability during the startup procedure for the NMR.

  • A Correlation for Interfacial Area Concentration in High Void Fraction Flows in Large Diameter Pipes

    Chemical Engineering Science

    The interfacial area concentration is an important parameter for evaluating the interactions between the phases, including drag forces, heat transfer or chemical reaction rates. Many models for interfacial area concentration exist for dispersed bubbly flows. Very few correlations exist for the prediction of cap-turbulent, slug, or churn-turbulent flows. In this paper a new correlation for predicting the interfacial area concentration beyond bubbly flows in large diameter pipes is derived using a two-bubble-group method (spherical and distorted bubbles as Group-1 bubbles and cap and churn-turbulent bubbles as Group-2 bubbles) and the two-group interfacial area transport equation. The resulting equations can be used to predict the void fraction for each group of bubbles and the Sauter mean diameter for each group of bubbles in addition to the total interfacial area concentration. The model is then benchmarked based on the data collected by Schlegel et al., 2012; Schlegel et al., 2014. It is found that the correlation predicts the data for Sauter mean diameter of Group 1 bubbles with RMS error of 23.3% and bias of +1.83%. For Group 2 bubbles the RMS error is 24.0% and the bias is +5.35%. This indicates that the correlation somewhat over-predicts the bubble sizes. In spite of this the prediction error remains reasonable compared to the accuracy of previous correlations, and given that the experimental uncertainty can be as high as 15% for some flow conditions. The RMS error and bias in the total interfacial area concentration are 22.6% and −4.29%, respectively. This is consistent with the over-prediction of the Sauter mean diameters, but again is reasonable considering the experimental uncertainty and the prediction error of previous correlations. The model is also able to predict the trends found in the experimental data with varied liquid and gas velocities, representing a large improvement over previous modeling efforts.

  • Uncertainty of Thermal Characterization of Phase Change Material by Differential Scanning Calorimetry Analysis

    International Journal of Engineering Research and Technology

    Phase change materials (PCMs) are used in many thermal heat storage applications because of their high heat capacity and desirable phase change temperatures. Recently many PCM products have been designed and commercialized to meet different thermal energy storage requirements. In order to correctly design commercial energy storage products, accurate knowledge of the thermal properties of the PCMs are essential. Heat flux Differential Scanning Calorimetry (DSC) is the most widely used method to characterize PCMs. However the existing standards and methods for calorimetry, which were designed for other materials, can lead to large errors if applied to PCMs. For example, the influence of non-equilibrium thermal gradients is very strong for PCMs. As a consequence, results are often systematically shifted to higher or lower values. Moreover, significant differences in the published data for the same material have been reported by many researchers. In this paper, DSC measurements were carried out parametrically with the goal of analyzing the sensitivity and resolution of the measurement technique under varying conditions. Several different types of PCMs were tested with varying sample sizes and heating rates. The phase transition temperature, onset temperature and the enthalpy of fusion were measured. The experimental results differ considerably for different measurements conditions. The results proved that using the correct heating rate and sample mass is necessary to obtain results with sufficient accuracy for PCM samples in a DSC. The optimum measurement condition was identified, and agreement between the obtained results and NIST data was demonstrated.

  • Prediction of interfacial area transport in a coupled two-fluid model computation

    Journal of Nuclear Science and Technology

    A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.

  • Preparation and enhanced thermal performance of novel (solid to gel) form-stable eutectic PCM modified by nano-graphene platelets

    Journal of Energy Storage

    This study presents the development of form-stable eutectic mixtures, modified with nanoscale structures for enhanced thermal performance. These additives may result in the next generation of phase change materials (PCMs) for thermal energy storage systems. An appropriate gelling or thickening agent (2-hydroxypropyl ether cellulose) is introduced so that the PCM will lose its fluidity, become form-stable, and the liquid leakage problem will be overcome. Nano-graphene platelets (NGPs) are added in order to enhance the thermal properties and overall heat transfer. Differential scanning calorimetry (DSC) was carried out for the thermal analysis of the PCMs. The paper experimentally studied in detail the enhanced thermo-physical properties required for stimulating and modelling the PCM in energy storage applications such as specific heat, thermal diffusivity, thermal conductivity, enthalpy, and density. The principle of the T-history method was applied using a parallel plate heating/cooling guarded plate apparatus to determine the true phase transition temperatures of bulk PCM. The supercooling of the enhanced shape stable mixture was found to be less than 0.1 °C. The thermal reliability test indicated that the enhanced form-stable eutectic mixture had reliable thermal performance over a postulated lifetime of 80 years. As a result, the developed form stable PCM eutectic mixture is a promising material for thermal energy storage.

  • Experimental study of two-phase flow structure in large diameter pipes

    Experimental Thermal and Fluid Science

    Current thermal-hydraulic analysis codes use static, flow-regime-dependent empirical models which introduce several sources of error and numerical instability. The interfacial area transport equation offers a more robust, reliable prediction of interfacial area and can allow for dynamic predictions of two-phase flows. In order to develop reliable mechanistic models for interfacial area concentration sources and sinks an extensive database is required, however the current database lacks significant data for pipes larger than 0.1 m diameter and for void fractions above 0.4. To improve and extend the database experiments have been performed in pipes with diameters of 0.152 m and 0.203 m with void fractions of up to 0.7, providing valuable data regarding the local profiles and axial development that can be used to evaluate current interfacial area transport models and assist in the development of new mechanistic models for interfacial area concentration sources and sinks.

  • Direct Synthesis of Radioactive Gold Nanoparticles Using a Research Nuclear Reactor

    Journal of Nuclear Medicine Technology

    We report the synthesis of radioactive gold nanoparticles in a single step process with appropriate activity and size to be used in cancer treatment and diagnosis. Methods: A 2 mM solution of gold chloride (HAuCl4), 1 mM of polyvinylpyrrolidone (PVP, M.W: 360,000), and 60 mM of 2-propanol was prepared in deionized water. Seven different samples of the solution were irradiated in a total neutron flux of 7.45 x 1012 n/cm2s in a research reactor for 0.5, 1, 3, 5, 10, 30, and 60 minutes. The resulting nanoparticles were characterized for morphology and chemical composition using a Transmission Electron Microscopy (TEM) and ImageJ. Results: The nanoparticles obtained presented particle-sizes between 3 nm and 450 nm. It is found that the average particle size depends on the time of irradiation, with longer irradiation time producing smaller nanoparticles. Irradiation for 10 minutes were found to produce nanoparticles with suitable characteristic for potential cancer treatment and diagnosis (average size: 50 nm, activity: 6.85 MBq / mL). Conclusion: Direct production of chemically stable, radioactive, gold nanoparticles was successfully accomplished using the Missouri S&T Research Nuclear Reactor (MSTR). The nanoparticles obtained present physical, and radioactive characteristics potentially useful in cancer treatment and diagnosis.

  • Modified Distribution Parameter for Churn-Turbulent Flow in Large Diameter Channels

    Nuclear Engineering and Design

    Two phase flows in large diameter channels are important in a wide range of industrial applications, but especially in analysis of nuclear reactor safety for the prediction of BWR behavior and safety analysis in PWRs. To remedy an inability of current drift-flux models to accurately predict the void fraction in churn-turbulent flows in large diameter pipes, extensive experiments have been performed in pipes with diameters of 0.152 m, 0.203 m and 0.304 m to collect area-averaged void fraction data using electrical impedance void meters. The standard deviation and skewness of the impedance meter signal have been used to characterize the flow regime and confirm previous flow regime transition results. By treating churn-turbulent flow as a transition between cap-bubbly dispersed flow and annular separated flow and using a linear ramp, the distribution parameter has been modified for churn-turbulent flow. The modified distribution parameter has been evaluated through comparison of the void fraction predicted by the drift-flux model and the measured void fraction.

  • Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow

    Progress in Nuclear Energy

    While high-fidelity 3D simulation is important for model validation, scientific understanding, and some design calculations, it can be prohibitively expensive for system design applications or applications involving large geometries. Thus, there is also a need for practical, simplified approaches for those applications. The two-fluid model strikes a balance between detail and computational resources, but requires the accurate specification of several key constitutive models. These include (1) interfacial forces, (2) interfacial area concentration, (3) two-phase turbulence, and (4) wall and bulk boiling and condensation. In many modern CFD packages, uncertainties in the local interfacial area concentration can have strong effects on the ability to predict the other key parameters. This paper demonstrates that the drag force in 3D CFD can be formulated in much the same way as in 1D system analysis codes and that this approach can be used to formulate a model for interfacial area concentration. This approach may open a method to calculate the interfacial forces without the need for interfacial area transport equations. This reduces the number of differential equations and avoids the modeling challenges associated with bubble breakup and coalescence kernels and the need to specify the inlet interfacial area concentration a priori. The new method is expected to decouple the effects of interfacial area uncertainty and calibrated coefficients, and should provide reasonable local bubble diameters for both group-1 and group-2 bubbles. The approaches proposed in this study are applicable to two-phase flow simulations in rather simple geometries such as upward two-phase flow in vertical channels. In view of many applications for upward two-phase flow in vertical channels, including nuclear reactor systems, the proposed methods are considered useful.

  • Experimental study of natural circulation instability with void reactivity feedback during startup transients for a BWR-type SMR

    Progress in Nuclear Energy

    The natural circulation boiling type SMR can experience flow instability during the startup transients due to the void reactivity feedback. A BWR-type natural circulation test loop has been built to perform the nuclear coupled startup transient tests for Purdue Novel Modular Reactor (NMR). This test loop is installed with different instruments to measure various thermal hydraulic parameters. The testing process can be monitored and controlled through PC with the assistance of LabVIEW procedure. The effects of power ramp rate on the flow instability during the nuclear coupled tests were investigated by controlling the power supply based on the point kinetics model with coolant void reactivity feedback. Two power ramp rates were investigated and the results were compared with those of the thermal hydraulic startup transients without void reactivity feedback. The time trace of power supply, system pressure, natural circulation rate, and void fraction profile are used to determine the flow stability during the transients. The results show that nuclear coupled startup transients also experience flashing instability and density wave oscillations. The power curves calculated from point kinetics model for startup transients show some fluctuations due to void reactivity feedback. However, the void reactivity feedback does not have significant effects on the flow instability during the startup procedure for the NMR.

  • A Correlation for Interfacial Area Concentration in High Void Fraction Flows in Large Diameter Pipes

    Chemical Engineering Science

    The interfacial area concentration is an important parameter for evaluating the interactions between the phases, including drag forces, heat transfer or chemical reaction rates. Many models for interfacial area concentration exist for dispersed bubbly flows. Very few correlations exist for the prediction of cap-turbulent, slug, or churn-turbulent flows. In this paper a new correlation for predicting the interfacial area concentration beyond bubbly flows in large diameter pipes is derived using a two-bubble-group method (spherical and distorted bubbles as Group-1 bubbles and cap and churn-turbulent bubbles as Group-2 bubbles) and the two-group interfacial area transport equation. The resulting equations can be used to predict the void fraction for each group of bubbles and the Sauter mean diameter for each group of bubbles in addition to the total interfacial area concentration. The model is then benchmarked based on the data collected by Schlegel et al., 2012; Schlegel et al., 2014. It is found that the correlation predicts the data for Sauter mean diameter of Group 1 bubbles with RMS error of 23.3% and bias of +1.83%. For Group 2 bubbles the RMS error is 24.0% and the bias is +5.35%. This indicates that the correlation somewhat over-predicts the bubble sizes. In spite of this the prediction error remains reasonable compared to the accuracy of previous correlations, and given that the experimental uncertainty can be as high as 15% for some flow conditions. The RMS error and bias in the total interfacial area concentration are 22.6% and −4.29%, respectively. This is consistent with the over-prediction of the Sauter mean diameters, but again is reasonable considering the experimental uncertainty and the prediction error of previous correlations. The model is also able to predict the trends found in the experimental data with varied liquid and gas velocities, representing a large improvement over previous modeling efforts.

  • Void Fraction and Flow Regime in Adiabatic Upward Two-Phase Flow in Large Diameter Pipes

    Nuclear Engineering and Design

    In pipes with very large diameters, slug bubbles cannot exist. For this reason, the characteristics of two-phase flow in large pipes are much different than those in small pipes. Knowledge of these characteristics is essential for the prediction of the flow in new nuclear reactor designs which include a large chimney to promote natural circulation. Two of the key parameters in the prediction of the flow are the void fraction and flow regime. Void fraction measurements were made in a vertical tube with diameter of 0.15 m and length of 4.4 m. Superficial gas and liquid velocities ranged from 0.1 to 5.1 m/s and from 0.01 to 2.0 m/s, respectively. The measured void fractions ranged from 0.02 to 0.83. Electrical impedance void meters at four axial locations were used to measure the void fraction. This data was verified through comparison with previous data sets and models. The temporal variation in the void fraction signal was used to characterize the flow regime through use of the Cumulative Probability Density Function (CPDF). The CPDF of the signal was used with a Kohonen Self-Organized Map (SOM) to classify the flow regimes at each measurement port. The three flow regimes used were termed bubbly, cap-bubbly, and churn flow. The resulting flow regime maps matched well with the maps developed previously through other methods. Further, the flow regime maps matched well with the criteria which were proposed based on Mishima and Ishii's (1984) criteria.

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • Atomic Energy Society of Japan

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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  • Atomic Energy Society of Japan

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

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  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

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    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

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    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

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    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

    Member

    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

    Member

    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

    Member

    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

    Member

    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

    Member

    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Atomic Energy Society of Japan

    Member

    The Atomic Energy Society of Japan is the only organization in Japan that aims to contribute towards progress in the development of atomic energy by seeking academic and technological advances pertaining to the peaceful use of atomic energy. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

  • Alpha Nu Sigma

    Secretary (2008-2009)

    The objective of the Alpha Nu Sigma Society is to recognize high scholarship, integrity, and potential achievement in applied nuclear science and nuclear engineering among outstanding students by means of membership in the Society.

  • American Nuclear Society

    Member

    The American Nuclear Society is a not-for-profit, international, scientific and educational organization with approximately 11,000 members including engineers, scientists, administrators, and educators. Members represent 1,600 plus corporations, educational institutions, and government agencies. ANS was established by individuals who recognized the need to unify the professional activities within the diverse fields of nuclear science and technology. The American Nuclear Society serves its members in their efforts to develop and safely apply nuclear science and technology for public benefit through knowledge exchange, professional development, and enhanced public understanding. urn:li:fs_position:(ACoAAALJuHcB78NY4UUr7QAQmBffs5TTF8pqe58,514049383)

NE 3223

2.5(3)

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online

NU 000

5(1)

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NUCENG 3223

5(1)

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