Assessment of RELAP5/MOD2 computer code against the Natural Circulation Test Data from Yong-Gwang Unit 2
- Korea Electric Power Corp., Taejon (Korea, Republic of). Research Center
- Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
The results of the RELAP5/MOD2 computer code simulation for the Natural Circulation Test in Yong-Gwang Unit 2 are analyzed here and compared with the plant operation data. The result of comparison reveals that the code calculation does present well the overall macroscopic behaviors of thermalhydraulic parameters in primary and secondary system compared with the plant operating data. The sensitivity study is performed to find out the effect of steam dump flow rate on the primary temperatures and it is found that the primary temperatures are very sensitive to the steam dump flow rate during the Natural Circulation. Because of the inherent uncertainties in the plant data, the assessment work is focussed on phenomena whereby the comparison between plant data and calculated data is based more on trends than on absolute values.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center; Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 10164152
- Report Number(s):
- NUREG/IA--0125; ON: TI93016058
- Country of Publication:
- United States
- Language:
- English
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COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
FLOW RATE
HEAT TRANSFER
HYDRAULICS
MATHEMATICS AND COMPUTERS
NATURAL CONVECTION
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SENSITIVITY ANALYSIS
STEAM