Irradiation test and post irradiation examination of the high burnup HTGR fuel - 18491
Creators
- 1. Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1393, Japan (Japan)
- 2. The Institute of Nuclear Physics, 1 Ibragimov str., Almaty 050032, The Republic of Kazakhstan (Kazakhstan)
Description
In order to examine irradiation performance of the new Tri-structural Isotropic (TRISO) fuel for the High Temperature Gas-cooled Reactor (HTGR) at the burnup around 100 GWd/t, a capsule irradiation test was conducted by WWR-K research reactor in the Institute of Nuclear Physics (INP) of Kazakhstan. The irradiated TRISO fuel was designed by Japan Atomic Energy Agency (JAEA) and fabricated in basis of the HTTR fuel technology in Japan. The fractional release of fission gas from the fuel during the irradiation shows good agreement with the predicted one released from as-fabricated failed TRISO fuel. It was suggested that unexpected additional fuel failure would not occur during the irradiation up to 100 GWd/t. In addition, the post-irradiation examination (PIE) with the irradiated fuel is planned to qualify TRISO fuel integrity and upgrade HTGR fuel design for further burnup extension. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 7 p.
Conference
- Title
- International Topical Meeting on High Temperature Reactor Technology
- Acronym
- HTR 2016
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52073025
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP EXTENSION; FISSION PRODUCTS; FUEL ELEMENT FAILURE; FUEL INTEGRITY; HTTR REACTOR; IRRADIATION CAPSULES; NUCLEAR ENERGY; NUCLEAR PHYSICS; PERFORMANCE; POST-IRRADIATION EXAMINATION; REACTOR DESIGN; SPENT FUELS; WWR-K-ALMATY REACTOR
- Descriptors DEC
- BURNUP; DESIGN; ENERGY; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FAILURES; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; ISOTOPES; MATERIALS; NUCLEAR FUELS; PHYSICS; RADIOACTIVE MATERIALS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWR TYPE REACTORS
Optional Information
- Notes
- 16 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)