Recriticality in a BWR [boiling water reactor] following a core damage event
Creators
- 1. Pacific Northwest Lab., Richland, WA (USA)
- 2. Battelle Memorial Inst., Columbus, OH (USA)
Description
This report describes the results of a study conducted by Pacific Northwest Laboratory to assist the US Nuclear Regulatory Commission in evaluating the potential for recriticality in boiling water reactors (BWRs) during certain low probability severe accidents. Based on a conservative bounding analysis, this report concludes that there is a potential for recriticality in BWRs if core reflood occurs after control blade melting has begun but prior to significant fuel rod melting. However, a recriticality event will most likely not generate a pressure pulse significant enough to fail the vessel. Instead, a quasi-steady power level would result and the containment pressure and temperature would increase until the containment failure pressure is reached, unless actions are taken to terminate the event. Two strategies are identified that would aid in regaining control of the reactor and terminate the recriticality event before containment failure pressures are reached. The first strategy involves initiating boration injection at or before the time of core reflood if the potential for control blade melting exists. The second strategy involves initiating residual heat removal suppression pool cooling to remove the heat load generated by the recriticality event and thus extend the time available for boration. 31 figs., 17 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI91005316; NTIS; INIS; GPO.
Files
Additional details
Publishing Information
- Imprint Pagination
- 161 p.
- Report number
- NUREG/CR--5653
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22029326
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT; CONTROL ELEMENTS; CRITICALITY; EMERGENCY PLANS; EXCURSIONS; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; M CODES; MELTDOWN; OUTAGES; REACTOR CORES; REACTOR SAFETY; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC06-76RL01830
- Secondary number(s)
- PNL--7476.