Laguna Verde closure of all MSIV transient analyses with TRAC-BF1
Creators
Description
This paper shows the work performed to analyze the behavior of the Laguna Verde Nuclear Power Station (LVNPS) in the event of the total closure of the main steam isolation valves (MSIVs). This analysis was based on results derived by the TRAC-BF1 code, a well-known best-estimate code used for transient analyses of boiling water reactors (BWRs). The work undertook an evaluation of several safety parameters, such as dome pressure rise, maximum temperature in the fuel, maximum reactor power, and others. The LVNPS is a 1931-MW(thermal) BWR/5 General Electric plant. A TRAC-BF1 model of LVNPS was developed in this work and proved to work quite well when compared with other theoretical results. A comparison of the TRAC-BF1 calculations with those of the start-up tests is in process that will validate the LVNPS model
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 355.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038776
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; CORE SPRAY SYSTEMS; DRYERS; ENGINEERED SAFETY SYSTEMS; FEEDWATER; FUEL ELEMENTS; HIGH PRESSURE COOLANT INJECTIO; LAGUNA VERDE-1 REACTOR; LEVELS; LOW PRESSURE COOLANT INJECTION; POSITIONING; POWER DENSITY; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; REACTOR CORES; REACTOR SAFETY; RELIEF VALVES; SCRAM; SECONDARY COOLANT CIRCUITS; STEADY-STATE CONDITIONS; STEAM SEPARATORS; T CODES; TEMPERATURE CONTROL; TRANSIENTS; VALVES
- Descriptors DEC
- BWR TYPE REACTORS; CONTROL; CONTROL EQUIPMENT; COOLING SYSTEMS; ECCS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SEPARATION EQUIPMENT; SHUTDOWN; SIMULATION; THERMAL REACTORS; VAPOR SEPARATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.