Burn-up Determination and Accident Testing of HTR-PM Fuel Elements Irradiated in the HFR Petten
Creators
- 1. European Commission, Joint Research Centre, Directorate G – Nuclear Safety and Security Hermann-von-Helmholtz-Platz1, 76344 Eggenstein-Leopoldshafen (Germany)
- 2. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China)
Description
The current paper reports the results of gamma spectroscopic burn-up determination and KüFA safety testing at JRC Karlsruhe on spherical high-temperature reactor fuel elements, which were fabricated by the Institute of Nuclear and New Energy Technology of the Tsinghua University, Beijing. The fuel elements were irradiated in the High Flux Reactor, Petten, in the frame of the HFR-EU1 and HTR-PM campaigns and transported to JRC Karlsruhe for post-irradiation examination and accident testing in the KüFA device in the frame of a bilateral safety research study. Burn-up determination was performed on seven fuel elements based on the quantitative measurement of their Cs-137 inventories using an established gamma spectroscopy set-up in the JRC hot cell facilities. Accident testing was conducted on three HTR-PM fuel elements in several phases at simulated accident temperatures between 1620 °C and 1770 °C for 150 hours to simulate hypothetical depressurization and loss-of-forced circulation accidents. The release of Kr-85 was measured during the tests in a cold trap and solid fission product release was determined by gamma spectroscopic analyses of exchangeable cold plates in a low background environment. After successful completion of the KüFA tests the fuel elements are currently undergoing further post-irradiation examinations including profile disintegration as well as ceramography and scanning electron microscopy of individual coated particles. (author)
Files
54061971.pdf
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Additional details
Publishing Information
- Imprint Title
- 9th International Conference on High Temperature Reactor Technology (HTR2018)
- Imprint Pagination
- vp.
- Journal Page Range
- 8 p.
- Report number
- INIS-PL--23M0001
Conference
- Title
- 9. International Conference on High Temperature Reactor Technology
- Acronym
- HTR2018
- Dates
- 8-10 Oct 2018
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Poland
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54061971
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; BURNUP; CERAMOGRAPHY; CESIUM 137; DEPRESSURIZATION; FEDERAL REPUBLIC OF GERMANY; FISSION PRODUCT RELEASE; FORSCHUNGSZENTRUM JUELICH; FUEL ELEMENTS; HFR REACTOR; HOT CELLS; HTGR TYPE REACTORS; IRRADIATION; KRYPTON 85; NUCLEAR FUELS; SAFETY
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; DEVELOPED COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EQUIPMENT; EUROPE; EVEN-ODD NUCLEI; FUELS; GAS COOLED REACTORS; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KRYPTON ISOTOPES; LABORATORY EQUIPMENT; MATERIALS; MATERIALS TESTING REACTORS; MICROSECONDS LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Document from Juelich Preservation Project; 16 refs., 11 figs., 8 tabs.
- Secondary number(s)
- HTR2018--73