Nuclear Power Plant Design and Analysis Codes. Development, Validation, and Application. Woodhead Publishing Series in Energy

Table of Contents

I MAP OF CODE DEVELOPMENT 1. Roadmap 2. Guidance of Nuclear Code development 3. Nuclear Engineering Software Quality Assurance 4. Multi-physics Coupling Plan

II PHYSICS AND FUELS CODES 5. Nuclear Physics Deterministic Code 6. Nuclear Physics Probability Code: OpenMC

III FUELS AND SUB-CHANNEL CODES 7. Fuels and Assemblies Codes: FRAPCON/FRAPTRAN 8. Fuels and Assemblies Codes: TRANSURANUS 9. Fuels and Assemblies Codes: ALCYONE and GERMINAL 10. Sub-Channel Codes: CTF and VIPRE-01

IV THERMAL-HYDRAULIC CODES 11. RCS Systems Thermal Hydraulic Codes: RELAP5-based codes 12. RCS Systems Thermal Hydraulic Codes: TRACE 13. ATHLET 14. SAM 15. Other Thermal Hydraulic Codes

V SEVERE ACCIDENT CODES 16. RCS SA Codes: RELAP/SCDAPSIM 17. ATHLET-CD 18. Integral SA Codes: IMPACT/SAMPSON 19. MELCOR

VI Noval CFD methods 20. MPS Code 21. LBM Code

VII SPECIAL OR NEW DIRECTION 22. Code for Nuclear materials 23. Nuclear Power Plant Cybersecurity 24. Artificial Neural Network 25. Artificial Intelligence Code 26.Temporal Data Mining (TDM)

Authors

Jun Wang Research Associate, University of Wisconsin, Madison, USA. 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. Xin Li Research Fellow in Japan Atomic Energy Agency, Member of Atomic Energy Society of Japan. 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. Chris Allison Co-founder of Innovative Systems Software (ISS), LLC. 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). Judy Hohorst Senior Engineer, Innovative Systems Software LLC. 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.