Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release

Author:

Giaccardi L.,Cherubini M.,Zullo G.,Pizzocri D.,Magni A.,Luzzi L.ORCID

Funder

H2020 Euratom

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference79 articles.

1. Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2+-x: Implications for nuclear fuel performance modeling;Andersson;J. Nucl. Mater.,2014

2. An efficient model for the analysis of fission gas release;Bernard;J. Nucl. Mater.,2002

3. A method of calculating fission gas diffusion from UO2 fuel and its application to the X-2-f loop test;Booth;Atomic Energy of Canada Limited,1957

4. Metal fission product behaviour in high temperature reactors - UO2 coated particle fuel;Brown;J. Nucl. Mater.,1976

5. CONTACT 1 and 2 experiments: Behaviour of PWR fuel rod up to 15000 MWd/tU;Bruet,1980

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