Fission product releases at severe LWR accident conditions: ORNL/CEA measurements versus calculations
- 1. CEA Centre d'Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique
- 2. Oak Ridge National Lab., TN (United States)
- 3. CEA Centre d'Etudes de Fontenay-aux-Roses, 92 (France). Dept. de Protection de l'Environnement et des Installations
Description
Experimental programs in the United States and France have followed similar paths in supplying much of the data needed to analyze severe accidents. Both the HI/VI program, conducted at the Oak Ridge National Laboratory (ORNL) under the sponsorship of the U. S. Nuclear Regulatory Commission (NRC), and the HEVA/VERCORS program, supported by IPSN-Commissariat a l'Energie Atomique (CEA) and carried out at the Centre d'Etudes Nucleaires de Grenoble, have studied fission product release from light water reactor (LWR) fuel samples during test sequences representative of severe accidents. Recognizing that more accurate data, i.e., a better defined source term, could reduce the safety margins included in the rather conservative source terms originating from WASH-1400, the primary objective of these programs has been to improve the data base concerning fission product release and behavior at high temperatures. To facilitate the comparison, a model based on fission product diffusion mechanisms that was developed at ORNL and adapted with CEA experimental data is proposed. This CEA model is compared with the ORNL experimental data in a blind test. The two experimental programs used similar techniques in out-of-pile studies. Highly irradiated fuel samples were heated in radiofrequency induction furnaces to very high temperatures (up to 2700 K at ORNL and 2750 K at CEA) in oxidizing (H2O), reducing (H2) or mixed (H2O+H2) environments. The experimental parameters, which were chosen from calculated accident scenarios, did not duplicate specific accidents, but rather emphasized careful control of test conditions to facilitate extrapolation of the results to a wide variety of accident situations. This paper presents a broad and consistent database from ORNL and CEA release results obtained independently since the early 1980'S. A comparison of CORSOR and CORSOR Booth calculations, currently used in safety analysis, and the experimental results is presented and discussed
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Additional details
Publishing Information
- Imprint Pagination
- 48 p.
- Report number
- CEA-DRN-DTP--95-016A
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 29011267
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; C CODES; CEA GRENOBLE; FISSION PRODUCT RELEASE; ORNL; PWR TYPE REACTORS; REACTOR ACCIDENTS; SPENT FUEL ELEMENTS; TEMPERATURE RANGE 1000-4000 K; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; CEA; COMPUTER CODES; ENRICHED URANIUM REACTORS; FRENCH ORGANIZATIONS; FUEL ELEMENTS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS