Uncertainty in BWR power during ATWS events
A study was undertaken to improve our understanding of BWR conditions following the closure of main steam isolation valves and the failure of reactor trip. Of particular interest was the power during the period when the core had reached a quasi-equilibrium condition with a natural circulation flow rate determined by the water level in the downcomer. Insights into the uncertainity in the calculation of this power with sophisticated computer codes were quantified using a simple model which relates power to the principal thermal-hydraulic variables and reactivity coefficients; the latter representing the link between the thermal-hydraulics and the neutronics. Assumptions regarding the uncertainty in these variables and coefficients were then used to determine the uncertainty in power.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5664422
- Report Number(s):
- BNL-NUREG-38210; CONF-860906-5; ON: TI86012698
- Resource Relation:
- Conference: Advances in reactor physics and safety meeting, Saratoga Springs, NY, USA, 17 Sep 1986
- Country of Publication:
- United States
- Language:
- English
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