Causes of instability at LaSalle and consequences from postulated scram failure
Description
The March 9, 1988 instability event at the LaSalle County-2 BWR power plant was simulated on the BNL Engineering Plant Analyzer (EPA) in order to assess its ability to simulate oscillatory transients, to identify the causes of the instability, to determine the maximum power amplitude of limit-cycle oscillations after postulated scram failure and to rank leading modeling parameters which affect instability. The EPA was found capable of simulating the LaSalle instability, which was found to have been caused by the combination of low core flow, moderately high power, low feedwater temperature and strong bottom power peaking. After postulated scram failure, the power was found to peak at 1300% of normal full power. Void reactivity, power peaking and core exit flow impedance were found to be the leading phenomena affecting thermohydraulic instability. 3 refs. 17 figs., 3 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE91004011; OSTI; INIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- BNL-NUREG--45273
Conference
- Title
- International workshop on boiling water reactor stability.
- Dates
- 17-19 Oct 1990.
- Place
- Upton, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22023292
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; EXCURSIONS; FLOW RATE; HEAT TRANSFER; HYDRAULICS; LA SALLE COUNTY-2 REACTOR; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SCRAM; TRANSIENTS; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016
- Secondary number(s)
- CONF-9010224--4.