Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application: Woodhead Publishing Series in Energy
Editat de Jun Wang, Xin Li, Chris Allison, Judy Hohorsten Limba Engleză Paperback – 12 noi 2020
Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs.
- Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors
- Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes
- Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
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Specificații
ISBN-13: 9780128181904
ISBN-10: 0128181907
Pagini: 608
Ilustrații: Approx. 150 illustrations
Dimensiuni: 191 x 235 mm
Greutate: 1.03 kg
Editura: ELSEVIER SCIENCE
Seria Woodhead Publishing Series in Energy
ISBN-10: 0128181907
Pagini: 608
Ilustrații: Approx. 150 illustrations
Dimensiuni: 191 x 235 mm
Greutate: 1.03 kg
Editura: ELSEVIER SCIENCE
Seria Woodhead Publishing Series in Energy
Public țintă
Engineers in the nuclear industry; professors & post-grad students involved in code development; senior professionals involve in code development from a computer science perspective; early career researchers and professionals requiring a foundational understanding of nuclear code development carried out by their predecessors, and how it applies to their specific area of research.Cuprins
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)
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)