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The influence of microstructure of mox fuel on its irradiation behaviour under transient conditions

Objective

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.

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

BELGONUCLEAIRE SA
Address
Avenue Ariane 4
1200 Bruxelles
Belgium

Participants (5)

BRITISH NUCLEAR FUELS PLC
United Kingdom
Address
Sellafield B170
CA20 1PG Seascale
COMMISSION OF THE EUROPEAN COMMUNITIES
Germany
Address
Hermann-von-helmholtz Platz 1
76125 Karlsruhe
COMMISSION OF THE EUROPEAN COMMUNITIES
Netherlands
Address
Westerduinweg 3
1755 ZG Petten
NUCLEAR RESEARCH AND CONSULTANCY GROUP
Netherlands
Address
Westerduinweg 3
1755 ZG Petten
PAUL SCHERRER INSTITUT
Switzerland
Address

5232 Villigen