Experimental study on void behavior in fast power transients simulating hot stand-by reactivity initiated accidents of BWR
- 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
Description
A series of experiments was performed in order to acquire insights on transient void behavior at high pressures, which simulated thermal-hydraulic conditions during a reactivity initiated accidents (RIA) at a hot stand-by condition of boiling water reactors (BWRs). A simulated fuel rod placed in the test section was rapidly heated by the direct electric current. The void fraction in the flow channel was evaluated from the measured impedance of a water-vapor mixture with use of the rod and the outer boundary wall as a pair of electrodes. The experimental results implied that key influential factors were the subcooling of the inlet water and the ambient pressure. Heat partitioning was estimated through energy balance calculations, which showed that heat consumed for the water heat-up was sharply decreased within a narrow range of water temperature adjacent to the saturation. The experimental results were applied to the analyses with TRAC-BF1 and RELAP5-Mod3 codes to assess the predictive capability of the best-estimate (BE) thermal-hydraulic codes. (author)
Additional details
Publishing Information
- Imprint Title
- NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [4617 p.]
- Journal Page Range
- [15 p.]
Conference
- Title
- 13. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-13
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Kanazawa, Ishikawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43036673
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; ENERGY BALANCE; EXCURSIONS; FUEL RODS; R CODES; REACTIVITY; T CODES; THERMAL HYDRAULICS; TRANSIENTS; VOID FRACTION; WATER
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1181.pdf