Thermal-hydraulic tests with out-of-pile test facility simulating natural convection capsule
Creators
- 1. Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)
Description
Power transient tests for the fuels of light water reactors are to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type irradiation test facilities, and the integrity of the fuels is to be investigated by the tests. Prior to the irradiation tests of the fuels, the out-of-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the realization of the irradiation tests and the planning of the test methods were carried out. In the present report, the outline of the out-of-pile test facility, the test plan and the tests simulating natural convection capsule were described. As a result of the tests, it was found that the power of the heater pin with a diameter of 9.5 mm can achieve to 600 W/cm without transition from nucleate boiling to film boiling under BWR and PWR coolant pressure conditions, and it became clear that the irradiation tests up to 600 W/cm of BWR and PWR fuels with their outer cladding diameter of 9.5 mm can be realized in JMTR. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-technology-2009-080
Files
System files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 30 p.
- Report number
- JAEA-Technology--2009-080
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 42011386
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CAPSULES; FILM BOILING; FUEL INTEGRITY; JAEA; JMTR REACTOR; NATURAL CONVECTION; NUCLEATE BOILING; POWER; PWR TYPE REACTORS; SIMULATION; TEST FACILITIES; TESTING; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- BOILING; CONTAINERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; IRRADIATION REACTORS; JAPANESE ORGANIZATIONS; MASS TRANSFER; MATERIALS TESTING REACTORS; MECHANICS; NATIONAL ORGANIZATIONS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs., 16 figs., 2 tabs.