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Contenido archivado el 2022-12-05

Supporting nuclear data for advanced MOX fuels

Objetivo



Objective :
The objective is to supplement the results of the previous European Strategy Study in the field of Partitioning and Transmutation (P & T). The use of advanced MOX fuels, either in thermal (PWR) or fast reactors will be investigated, see the companion proposal submitted by CEA. To this end the necessary nuclear data working libraries will be updated with new information from basic data evaluations and available integral experiments. The accuracy of the strategy studies to minimize wastes will be assessed. Short description :
For the scenario studies aiming at a reduced waste toxicity in MOX recycling schemes, more accurate data are required. Based on the European JEF 2.2 library these data will be introduced into working libraries for transport calculations and radioactive inventory calculations.
Available integral data will be used to improve the data files, and to estimate the uncertainty margins.
The contributions from BN and ECN (and also SCK) are closely coupled, and related to the use of advanced MOX fuels in PWR (overmoderation, full MOX loading and uranium-free fuels). Mass balances from high burnup irradiation are to be re-calculated at BN for MOX fuel pins irradiated in the BR3 reactor at very high burnup (e.g. 80,000 MWd/t).
The BR3 pin lattice was overmoderated with respect to standard PWR lattice. ECN will correlate the measured and calculated masses with the cross-sections, and estimate the uncertainties of mass inventories and of reactor parameters. At a later stage, ARIANE irradiation results should also be used to that aim. TUI proposes a verification of actinide and fission product nuclear data, based on irradiation experiments in the fast reactor KNK-II/2. This involves composition measurements using several techniques (IDMS, alpha- and gamma-spectrometry, ICP-MS).
The SCK contribution is coupled simultaneously to the BN-ECN and TUI proposals, as it consists of reviewing post irradiation examinations made in the past on a number of fuel samples from PWRs (like BR3), fast reactors (like KNK-II) and other reactors, so as to establish an extended data base.
At CEA, the French LWR programme has comprised analyses of spent fuel isotopics, for a wide range of UOX and MOX fuel types and burnups. Their analysis w ill be used to reduce uncertainties in nuclear data for actinides in MOX fuel from the JEF 2 database.
This relatively large work is complementary to the one described above, and is supplemented by fast reactor spent fuel and sample analysis (from PHENIX). ENEA proposes a contribution to the revision of nuclear data files for the isotopes Pu240, Pu242 and Am241, especially in the range of resonances. In order to get fruitful results from this large cooperation, the activities described above will be structured, by comparing first the computational techniques, and by integrating all results in a common data base, so as to agree on the final trend analysis.

Convocatoria de propuestas

Data not available

Régimen de financiación

CSC - Cost-sharing contracts

Coordinador

Belgonucléaire SA
Aportación de la UE
Sin datos
Dirección
4,Avenue Ariane
1200 Bruxelles
Bélgica

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Coste total
Sin datos

Participantes (5)