SENSITIVITY STUDIES FOR THE PWR ROD EJECTION ACCIDENT
Conference
·
OSTI ID:759029
- BROOKHAVEN NATIONAL LABORATORY
The objective of this study was to understand the uncertainty in fuel enthalpy calculated for the rod ejection accident (REA) in a pressurized water reactor (PWR). This is to help the US Nuclear Regulatory Commission in making judgments about acceptance criteria for the REA when high burnup fuel is used and for assessing the validity of licensee methods for calculating the REA. The approach is twofold. Sensitivity studies were first done to determine the effect on calculated fuel enthalpy of uncertainties in the important parameters which determine the outcome of the REA. The second step, which will be carried out at a later date, is to use the sensitivity to estimate the random error in the fuel enthalpy due to random errors in these key parameters once the variance of these parameters is determined.
- Research Organization:
- Brookhaven National Lab., Upton, NY (US)
- Sponsoring Organization:
- USDOE Office of Energy Research (ER) (US)
- DOE Contract Number:
- AC02-98CH10886
- OSTI ID:
- 759029
- Report Number(s):
- BNL--NUREG-67013; JCNW6382; JCNW6382
- Country of Publication:
- United States
- Language:
- English
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