MICROMOX: The influence of microstructure of MOX fuel on its irradiation behaviour under transient conditions

• Unité de recherche: PCRD EU
• Numéro de projet: 00.0040
• Titre du projet anglais: MICROMOX: The influence of microstructure of MOX fuel on its irradiation behaviour under transient conditions

Mots-clé (Anglais)

Fission gas model; fuel performance code; TRANSURANUS;
Nuclear Fission; Radiation Protection; Safety;
JRC

Autre Numéro de projet (Anglais)

EU project number: FIKS-2000-00030

Programme de recherche (Anglais)

EU-programme: 5. Frame Research Programme - 5.5.2 Nuclear fission

Description succincte (Anglais)

See abstract

Partenaires et organisations internationales (Anglais)

Belgonucléare (B), British Nuclear Fuel Ltd. (GB), Joint Research Centre-Institute for Energy (EU; former Institute for Advanced Materials), Joint Research Centre-Institute for Transuranium (EU), Nuclear Research and Consultancy Group (NL)

Résumé des résultats (Abstract) (Anglais)

Excessive fission gas release in MOX fuel prevents the achievement of burnup above40 GWd/tHM. The objective of the MICROMOX project is to study to what extent theas-fabricated microstructure of the MOX fuel influences the gas release intransient conditions. For this/ MOX fuels with various microstructures (homogeneous/heterogeneous Pu distribution, large grain) will be fabricated by ITU, loaded in rodlets instrumented for temperature and pressure measurements and irradiated at moderate rating in HFR to achieve a burnup of 60 GWd/tHM. The end of irradiation will consist in a temperature transient allowing follow fission gas release as a function of fuel temperature. Post-irradiation examinations of fuel will be made at NRG and PSI, focusing on fuel microstructural investigations. These data will be used to model the fission gas release.

Références bases de données (Anglais)

Swiss Database: Euro-DB of the
State Secretariat for Education and Research
Hallwylstrasse 4
CH-3003 Berne, Switzerland
Tel. [phone]
Swiss Project-Number: 00.0040