Overview of the Vercors Programme Devoted to Safety Studies on Irradiated PWR Fuel
Creators
- 1. CEA Centre d'Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique
- 2. CEA Centre d'Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire
Description
The first objective of the Heva-Vercors Program is to improve the data of fission product release and behaviour after an extensive fuel temperature increase and loss of integrity of the fuel elements that occur in case of severe PWR accident. The program is co-funded by the French Nuclear Protection and Safety Institute (IPSN) and Electricite de France (EDF). The experiments are conducted in a shielded cell of the French Grenoble Nuclear Centre. For these tests, industrial fuel from French PWR reactor plants is used. In order to rebuild the short lived fission product inventory, a reirradiation is performed in the experimental Siloe reactor, prior to the test. Eight tests have been conducted in the frame of the Heva Program up to 2370 K in the 1983-1988 period. The main outcomes of these studies were linked to the volatile fission product release. This program has been extended by the Vercors one with higher fuel temperature (2600 K) and improved instrumentation: gamma spectrometry, emission tomography, metallography, scanning electron microscopy, energy dispersive X-ray analysis, X-ray diffraction are some of the experimental techniques used for on line and post test characterization. The knowledge of the behavior of low volatile fission product has been significantly improved with the six Vercors tests. The results of the Vercors 4 test (38 GWd/t(U), 2570 K, reducing atmosphere) are presented here as an example. The key parameters are exhibited. The next step of these studies will use the Vercors HT loop that is planned to be operational at the beginning of 1996 to reach fuel melting temperature. The first aim of these future tests is to study the behaviour of non volatile and transuranic elements. An even more sophisticated instrumentation is implemented to reach the goal. The use of MOX fuel, the interaction between fission product aerosols and structural materials (Ag-In-Cd) and the fuel granulometry effect will be the next steps of the experimental program. (authors)
Availability note (English)
Available from INIS in electronic form and/or on microfiche .Files
29011252.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- CEA-CONF--12490
Conference
- Title
- Congress Material Chemistry'96.
- Dates
- 14-15 Mar 1996.
- Place
- Tsukuba, Ibaraki (Japan).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 29011252
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BARIUM 140; CEA GRENOBLE; CESIUM 137; FISSION PRODUCT RELEASE; FUEL RODS; HOT CELLS; IODINE 133; LANTHANUM 140; MOLYBDENUM 99; PWR TYPE REACTORS; SILOE REACTOR; SPENT FUEL ELEMENTS; TEMPERATURE RANGE 1000-4000 K
- Descriptors DEC
- BARIUM ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CEA; CESIUM ISOTOPES; DAYS LIVING RADIOISOTOPES; ENRICHED URANIUM REACTORS; EQUIPMENT; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FRENCH ORGANIZATIONS; FUEL ELEMENTS; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IODINE ISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPE PRODUCTION REACTORS; ISOTOPES; LABORATORY EQUIPMENT; LANTHANUM ISOTOPES; MOLYBDENUM ISOTOPES; NATIONAL ORGANIZATIONS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; POOL TYPE REACTORS; POWER REACTORS; RADIOISOTOPES; RARE EARTH NUCLEI; REACTOR COMPONENTS; REACTORS; SECONDS LIVING RADIOISOTOPES; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 10 refs.