Assessment of engineering plant analyzer with Peach Bottom 2 stability tests

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:5083683

Rohatgi, U S; Mallen, A N; Cheng, H S; Wulff, W

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: USNRC; 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
• Resource Relation: Conference: International topical meeting on reactor thermal hydraulics: towards the next generation of nuclear power plants, Salt Lake City, UT (United States), 20-24 Sep 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
STABILITY
ATWS
BENCHMARKS
COMPUTERIZED SIMULATION
E CODES
FLUID FLOW
FREQUENCY ANALYSIS
HEAT TRANSFER
HYDRAULICS
LA SALLE COUNTY-2 REACTOR
OSCILLATIONS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER DISTRIBUTION
TRANSIENTS
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
990200 - Mathematics & Computers
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled