TRACB04 simulation of BWR/4 design-basis accident with LPCI to lower plenum
Description
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
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 52
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 480-481
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 15-20 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065814
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CORE SPRAY SYSTEMS; ECCS; EPRI; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; LOW PRESSURE COOLANT INJECTION; PERFORMANCE; PIPES; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR SAFETY; RESEARCH PROGRAMS; RUPTURES; T CODES; TRANSIENTS; US NRC
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-860610--.