FIST/T23C, Simulated Failure to Maintain Water Level in BWR/6-218
Creators
- U.S. Nuclear Regulatory Commission (United States)
- Electric Power Research Institute (United States)
- General Electric Company (United States)
- Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)
Description
1 - Description of test facility: BWR/6-218 standard plant. A full size bundle with electrically heated rods is used to simulate the reactor core. A scaling ratio of 1/624 is applied in the design of the system components. Key features of the FIST facility include: (1) Full height test vessel and internals; (2) correctly scaled fluid volume distribution; (3) simulation of ECCS, S/RV, and ADS; (4) level trip capability; (5) heated feedwater supply system, which provides the capability for steady state operation. 2 - Description of test: Test T23C simulates a failure to maintain water level. Inventory loss eventually leads to bundle uncover and fuel rod heat-up. This test investigates system response up to the time when the bundle rod heat-up reaches the FIST heater temperature limit of 1200 deg. F
Availability note (English)
Available on-line: http://www.nea.fr/abs/html/csni0060.htmlAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43123743
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; ECCS; FAILURES; FEEDWATER; FUEL RODS; HEATERS; REACTOR ACCIDENT SIMULATION; REACTOR CORES; RODS; STEADY-STATE CONDITIONS; TEST FACILITIES; WEBSITES
- Descriptors DEC
- DOCUMENT TYPES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.; This record replaces 40013885