BWR Anticipated Transients Without Scram Leading to Instability
Anticipated transients without scram (ATWS) in aboiling water reactor (BWR) were simulated in order to understand reactor response and determine the effectiveness of automatic and operator actions to mitigate this beyond-design-basis accident. The events of interest herein are initiated by a turbine trip when the reactor is operating in the expanded operating domainMELLLA+ [maximum extended load line limit plus]. In these events the reactor may initially be at up to 120% of the original licensed thermal power (OLTP) and at flow rates as low as 80% of rated.For these (and similar) ATWS events the concern isthat when the reactor power decreases in response to a dual recirculation pump trip, the core will become unstable and large amplitude oscillations will begin. The occurrence of these power oscillations, if left unmitigated, may result in fuel damage, and the amplitude of the poweroscillations may hamper the effectiveness of the injection of dissolved neutron absorber through the standby liquid control system (SLCS).
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- Sponsoring Organization:
- AMERICAN NUCLEAR SOCIETY
- DOE Contract Number:
- DE-AC02-98CH10886
- OSTI ID:
- 1091775
- Report Number(s):
- BNL-101129-2013-CP; R&D Project: 15451/15830; 401001060
- Resource Relation:
- Conference: 2013 ANS Winter Meeting and Nuclear Technology Expo; Washington, D.C; 20131110 through 20131114
- Country of Publication:
- United States
- Language:
- English
Similar Records
A long-term MAAP 3. 0B analysis of a severe anticipated transient without scram accident in a boiling water reactor
Effect of power oscillations on suppression pool heating during ATWS (Anticipated Transients Without Scram) conditions