TRACB04 simulation of BWR/4 design-basis accident with LPCI to lower plenum
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6623603
This paper presents a TRACB04 simulation of a BWR/4 design-basis accident (DBA). The DBA considered is a postulated guillotine break in one suction line, with low-pressure coolant injection (LPCI) into the recirculation drive lines and through the jet pumps into the lower plenum. The TRACB04 code is a best-estimate computer code for the analysis of boiling water reactor (BWR) transients, and is an enhanced version of TRAC. It was developed under the Full Integral Simulation Test (FIST) Program, sponsored by the US Nuclear Regulatory Commission, the Electric Power Research Institute, and the General Electric Company. This simulation was performed to provide best-estimate BWR/4 DBA calculational results, and to assess the TRACB04 overall performance in a system calculation.
- Research Organization:
- General Electric Co., San Jose, CA
- OSTI ID:
- 6623603
- Report Number(s):
- CONF-860610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
- 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
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPRI
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
MECHANICS
NATIONAL ORGANIZATIONS
PERFORMANCE
PIPES
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RUPTURES
SAFETY
SIMULATION
T CODES
TRANSIENTS
US NRC
US ORGANIZATIONS
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
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPRI
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
MECHANICS
NATIONAL ORGANIZATIONS
PERFORMANCE
PIPES
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
RUPTURES
SAFETY
SIMULATION
T CODES
TRANSIENTS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS