Comparison of TRAC-BF1 calculations with the LaSalle 2 instability event
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.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 10194571
- Report Number(s):
- EGG-NRE--10803; ON: DE94002839
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
FEEDWATER HEATERS
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HYDRAULICS
LA SALLE COUNTY-2 REACTOR
LOSS OF FLOW
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
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BOILING WATER COOLED
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210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
FEEDWATER HEATERS
HEAT TRANSFER
HYDRAULICS
LA SALLE COUNTY-2 REACTOR
LOSS OF FLOW
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SCRAM
STABILITY
T CODES