Transuranics and fission products release from PWR fuels in severe accident conditions. Lessons learnt from VERCORS RT3 and RT4 tests
Creators
- 1. Centre d'Etudes de Cadarache, BP1, DEN/DEC/SA3C, Commissariat a l'Energie Atomique, Saint Paul Lez Durance (France)
- 2. Inst. for Transuranium Elements, JRC, European Commission, Karlsruhe (Germany)
- 3. Centre d'Etudes de Cadarache, BP3, DPAM/SEMIC, Inst. de Radioprotection et de Surete Nucleaire, St Paul lez Durance (France)
- 4. EDF R and D, Clamart (France)
- 5. EDF/SEPTEN, Villeurbanne (France)
Description
Over the last decades, several experimental programs devoted to the source term of fission products (FP) and actinides released from PWR fuel samples in severe accident (SA) conditions have been initiated throughout the world. In France, in this context, the Institute for Radiological Protection and Safety (IRSN) and Electricite de France (EDF) have supported the analytical VERCORS program which was performed by the Commissariat a l'Energie Atomique (CEA). The VERCORS facility at the LAMA-laboratory (CEA-Grenoble, France) was designed to heat up an irradiated fuel sample - taken from EDF's nuclear power reactors - to fuel relocation, and to capture the fission products released from the fuel and deposited downstream on a series of specific filters (impactors, bead-bed filter). On-line gamma detectors aimed at the fuel position, filters and gas capacity monitored the progress of FP release from the fuel, FP deposition on the filters and the fission gases emitted by the fuel (xenon and krypton). Before and after the test, a longitudinal gamma-scan of the fuel was conducted to measure the initial and final FP inventory in order to evaluate the quantitative fractions of FP emitted by the fuel during the test. All the components of the loop were then gamma-scanned to measure and locate the FPs released during the test and to draw up a mass balance of these FP. 25 annealing tests were performed between 1983 and 2002 on irradiated PWR fuels under various conditions of temperature and atmospheres (oxidising or reducing conditions). The influence of the nature of the fuel (UO2 versus MOX, burn up) and the fuel morphology (initially intact or fragmented fuel) have also been investigated. This led to an extended data base allowing on the one hand to study mechanisms which promote FP release in SA conditions, and on the other hand to enhance models implemented in SA codes. Because gamma spectrometry is well suited to FP measurement and not to actinides (except neptunium), chemical analysis of the filter deposits and other surface deposits downstream were performed in some specific cases, in order to extend the result to non gamma-active isotopes and confirm the gamma-spectroscopy results; this, in turn, will help to close the mass balance of the fission products and transuranic elements. In the present case, VERCORS RT3 and RT4 samples were sent to ITU in order to be analysed by Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) after dissolution. The present communication gives a general overview of the VERCORS program and presents in more detail the main findings regarding RT3 and RT4 with, on the one hand, the general FP behaviour including the comparison between gamma-spectrometry and ICP-MS results and, on the other hand, the significant release - up to ∼10 % of the initial inventory - of uranium in oxidizing conditions. (author)
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38115434.pdf
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-26-3
- Imprint Title
- Proceedings of the International Conference Nuclear Energy for New Europe 2006
- Imprint Pagination
- vp.
- Journal Page Range
- [16 p.]
- Report number
- INIS-SI--07-002
Conference
- Title
- International Conference Nuclear Energy for New Europe 2006
- Dates
- 18-21 Sep 2006
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 38115434
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DATA ACQUISITION; DATA ANALYSIS; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; SOURCE TERMS; TEST FACILITIES; TRANSURANIUM ELEMENTS
- Descriptors DEC
- DATA; ELEMENTS; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 15 refs., 4 tabs., 7 figs. Imprint:756 refs., 109 tabs., 481 figs.