Assessment of engineering plant analyzer with Peach Bottom 2 stability tests
Conference
·
OSTI ID:5083683
Engineering Plant Analyzer (EPA) has been developed to simulate plant transients for Boiling Water Reactor (BWR). Recently, this code has been used to simulate LaSalle-2 instability event which was initiated by a failure in the feed water heater. The simulation was performed for the scram conditions and for the postulated failure in the scram. In order to assess the capability of the EPA to simulate oscillatory flows as observed in the LaSalle event, EPA has been benchmarked with the available data from the Peach Bottom 2 (PB2) Instability tests PT1, PT2, and PT4. This document provides a description of these tests.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5083683
- Report Number(s):
- BNL-NUREG-47694; CONF-920903--9; ON: DE92018148
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
ATWS
BENCHMARKS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
E CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
FREQUENCY ANALYSIS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
LA SALLE COUNTY-2 REACTOR
MECHANICS
OSCILLATIONS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER DISTRIBUTION
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
STABILITY
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
ATWS
BENCHMARKS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
E CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
FREQUENCY ANALYSIS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
LA SALLE COUNTY-2 REACTOR
MECHANICS
OSCILLATIONS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER DISTRIBUTION
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
STABILITY
THERMAL REACTORS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS