Dr. Jun Wang is a Research Scientist at the University of Wisconsin, Madison. He has over 10 years of experience in code development, validation, and application, and his research areas include nuclear thermal hydraulics and safety, severe accident, fuel performance, and advanced reactors. Wang has over 50 peer-review articles published on top nuclear journals and conferences. He also has over 200 peer-review experience in 20 journals and conferences, such as the International Journal of Heat and Mass Transfer, Applied Thermal Engineering, Annals of Nuclear Energy, Nuclear Technology, Nuclear Engineering and Design, and Progress in Nuclear Energy. Dr. Xin Li has years of experience in numerical modeling both at the macroscopic nuclear power plant system level and at the microscopic phenomenological level. Her research interests and expertise are analysis of severe accident phenomenology and thermal-hydraulics as well as Computer Fluid Dynamics. Dr. Chris Allison worked at Idaho National Laboratory as a technical specialist for over 20 years, involved in experimental and code development activities. Now Dr. Allison is the general manager and co-founder of Innovative Systems Software (ISS), LLC. Dr. Allison serves as a technical consultant for the International Atomic Energy Agency (IAEA) for severe accident management and analysis. He has served as a guest lecturer for IAEA-sponsored training workshops on RELAP5 and RELAPS/SCDAP. He has served in a similar capacity for the U.S. Nuclear Regulatory Commission (NRC) and U.S. Department of Energy (DOE). Dr. Judy Hohorst works at Innovative Systems Software LLC as a senior engineer. She is in charge of the work RELAP/SCDAP training, and RELAP/SCDPASIM validation.

• I MAP OF CODE DEVELOPMENT1. Roadmap2. Guidance of Nuclear Code development3. Nuclear Engineering Software Quality Assurance4. Multi-physics Coupling PlanII PHYSICS AND FUELS CODES5. Nuclear Physics Deterministic Code6. Nuclear Physics Probability Code: OpenMCIII FUELS AND SUB-CHANNEL CODES7. Fuels and Assemblies Codes: FRAPCON/FRAPTRAN8. Fuels and Assemblies Codes: TRANSURANUS 9. Fuels and Assemblies Codes: ALCYONE and GERMINAL10. Sub-Channel Codes: CTF and VIPRE-01IV THERMAL-HYDRAULIC CODES11. RCS Systems Thermal Hydraulic Codes: RELAP5-based codes12. RCS Systems Thermal Hydraulic Codes: TRACE13. ATHLET14. SAM15. Other Thermal Hydraulic CodesV SEVERE ACCIDENT CODES16. RCS SA Codes: RELAP/SCDAPSIM17. ATHLET-CD18. Integral SA Codes: IMPACT/SAMPSON19. MELCORVI Noval CFD methods20. MPS Code21. LBM CodeVII SPECIAL OR NEW DIRECTION22. Code for Nuclear materials23. Nuclear Power Plant Cybersecurity24. Artificial Neural Network25. Artificial Intelligence Code26.Temporal Data Mining (TDM)

Dr. Jun Wang is a Research Scientist at the University of Wisconsin, Madison. He has over 10 years of experience in code development, validation, and application, and his research areas include nuclear thermal hydraulics and safety, severe accident, fuel performance, and advanced reactors. Wang has over 50 peer-review articles published on top nuclear journals and conferences. He also has over 200 peer-review experience in 20 journals and conferences, such as the International Journal of Heat and Mass Transfer, Applied Thermal Engineering, Annals of Nuclear Energy, Nuclear Technology, Nuclear Engineering and Design, and Progress in Nuclear Energy. Dr. Xin Li has years of experience in numerical modeling both at the macroscopic nuclear power plant system level and at the microscopic phenomenological level. Her research interests and expertise are analysis of severe accident phenomenology and thermal-hydraulics as well as Computer Fluid Dynamics. Dr. Chris Allison worked at Idaho National Laboratory as a technical specialist for over 20 years, involved in experimental and code development activities. Now Dr. Allison is the general manager and co-founder of Innovative Systems Software (ISS), LLC. Dr. Allison serves as a technical consultant for the International Atomic Energy Agency (IAEA) for severe accident management and analysis. He has served as a guest lecturer for IAEA-sponsored training workshops on RELAP5 and RELAPS/SCDAP. He has served in a similar capacity for the U.S. Nuclear Regulatory Commission (NRC) and U.S. Department of Energy (DOE). Dr. Judy Hohorst works at Innovative Systems Software LLC as a senior engineer. She is in charge of the work RELAP/SCDAP training, and RELAP/SCDPASIM validation.

• I MAP OF CODE DEVELOPMENT1. Roadmap2. Guidance of Nuclear Code development3. Nuclear Engineering Software Quality Assurance4. Multi-physics Coupling PlanII PHYSICS AND FUELS CODES5. Nuclear Physics Deterministic Code6. Nuclear Physics Probability Code: OpenMCIII FUELS AND SUB-CHANNEL CODES7. Fuels and Assemblies Codes: FRAPCON/FRAPTRAN8. Fuels and Assemblies Codes: TRANSURANUS 9. Fuels and Assemblies Codes: ALCYONE and GERMINAL10. Sub-Channel Codes: CTF and VIPRE-01IV THERMAL-HYDRAULIC CODES11. RCS Systems Thermal Hydraulic Codes: RELAP5-based codes12. RCS Systems Thermal Hydraulic Codes: TRACE13. ATHLET14. SAM15. Other Thermal Hydraulic CodesV SEVERE ACCIDENT CODES16. RCS SA Codes: RELAP/SCDAPSIM17. ATHLET-CD18. Integral SA Codes: IMPACT/SAMPSON19. MELCORVI Noval CFD methods20. MPS Code21. LBM CodeVII SPECIAL OR NEW DIRECTION22. Code for Nuclear materials23. Nuclear Power Plant Cybersecurity24. Artificial Neural Network25. Artificial Intelligence Code26.Temporal Data Mining (TDM)

Dr. Jun Wang is a Research Scientist at the University of Wisconsin, Madison. He has over 10 years of experience in code development, validation, and application, and his research areas include nuclear thermal hydraulics and safety, severe accident, fuel performance, and advanced reactors. Wang has over 50 peer-review articles published on top nuclear journals and conferences. He also has over 200 peer-review experience in 20 journals and conferences, such as the International Journal of Heat and Mass Transfer, Applied Thermal Engineering, Annals of Nuclear Energy, Nuclear Technology, Nuclear Engineering and Design, and Progress in Nuclear Energy. Dr. Xin Li has years of experience in numerical modeling both at the macroscopic nuclear power plant system level and at the microscopic phenomenological level. Her research interests and expertise are analysis of severe accident phenomenology and thermal-hydraulics as well as Computer Fluid Dynamics. Dr. Chris Allison worked at Idaho National Laboratory as a technical specialist for over 20 years, involved in experimental and code development activities. Now Dr. Allison is the general manager and co-founder of Innovative Systems Software (ISS), LLC. Dr. Allison serves as a technical consultant for the International Atomic Energy Agency (IAEA) for severe accident management and analysis. He has served as a guest lecturer for IAEA-sponsored training workshops on RELAP5 and RELAPS/SCDAP. He has served in a similar capacity for the U.S. Nuclear Regulatory Commission (NRC) and U.S. Department of Energy (DOE). Dr. Judy Hohorst works at Innovative Systems Software LLC as a senior engineer. She is in charge of the work RELAP/SCDAP training, and RELAP/SCDPASIM validation.

• I MAP OF CODE DEVELOPMENT1. Roadmap2. Guidance of Nuclear Code development3. Nuclear Engineering Software Quality Assurance4. Multi-physics Coupling PlanII PHYSICS AND FUELS CODES5. Nuclear Physics Deterministic Code6. Nuclear Physics Probability Code: OpenMCIII FUELS AND SUB-CHANNEL CODES7. Fuels and Assemblies Codes: FRAPCON/FRAPTRAN8. Fuels and Assemblies Codes: TRANSURANUS 9. Fuels and Assemblies Codes: ALCYONE and GERMINAL10. Sub-Channel Codes: CTF and VIPRE-01IV THERMAL-HYDRAULIC CODES11. RCS Systems Thermal Hydraulic Codes: RELAP5-based codes12. RCS Systems Thermal Hydraulic Codes: TRACE13. ATHLET14. SAM15. Other Thermal Hydraulic CodesV SEVERE ACCIDENT CODES16. RCS SA Codes: RELAP/SCDAPSIM17. ATHLET-CD18. Integral SA Codes: IMPACT/SAMPSON19. MELCORVI Noval CFD methods20. MPS Code21. LBM CodeVII SPECIAL OR NEW DIRECTION22. Code for Nuclear materials23. Nuclear Power Plant Cybersecurity24. Artificial Neural Network25. Artificial Intelligence Code26.Temporal Data Mining (TDM)