Assessment of PWR Steam Generator modelling in RELAP5/MOD2. International Agreement Report
- National Power, Leatherhead (GB). Technology and Environment Centre
An assessment of Steam Generator (SG) modelling in the PWR thermal-hydraulic code RELAP5/MOD2 is presented. The assessment is based on a review of code assessment calculations performed in the UK and elsewhere, detailed calculations against a series of commissioning tests carried out on the Wolf Creek PWR and analytical investigations of the phenomena involved in normal and abnormal SG operation. A number of modelling deficiencies are identified and their implications for PWR safety analysis are discussed -- including methods for compensating for the deficiencies through changes to the input deck. Consideration is also given as to whether the deficiencies will still be present in the successor code RELAP5/MOD3.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; National Power, Leatherhead (United Kingdom). Technology and Environment Centre
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10168879
- Report Number(s):
- NUREG/IA--0106; TEC/L--0471/R91; ON: TI93016824
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200
99 GENERAL AND MISCELLANEOUS
990200
COMPUTERIZED SIMULATION
HEAT TRANSFER
MATHEMATICAL MODELS
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR SAFETY
SAFETY ANALYSIS
STEAM GENERATORS
WOLF CREEK-1 REACTOR