Published May 1993
| Version v1
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Comparison of TRAC-BF1 calculations with the LaSalle 2 instability event
Description
In March of 1988 the LaSalle 2 BWR, while at about 85 percent power, was exposed to a loss of both recirculation pumps providing drive flow to the jet pumps. Within a few minutes the reactor power began to oscillate, resulting in an overpower scram. This report presents results of calculations performed with the TRAC-BF1 code to assess the capability of the code to calculate the observed behavior of the LaSalle plant during the event
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94002839; NTIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 45 p.
- Report number
- EGG-NRE--10803
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25028862
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- FEEDWATER HEATERS; HEAT TRANSFER; HYDRAULICS; LA SALLE COUNTY-2 REACTOR; LOSS OF FLOW; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SCRAM; STABILITY; T CODES
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEATERS; POWER REACTORS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).