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Jun 27, 2017, 5:30 PM
1h 30m
Poster Area (Yekaterinburg)

Poster Area


POSTER Track 5. Fast Reactor Materials (Fuels and Structures) and Technology Poster Session 1


Mr Evgenii Kinev (Institute of Nuclear Materials)


A large number of post irradiation examinations of the state of spent fuel element composition have been carried out for more than ten years of successful operation of BN-600 core of the third 01M2 modification. The paper aims to substantiate operating capacity of standard and certain experimental oxide fuel kinds with service life characteristics increase, in particular, burn-up depth increase. Examinations include analysis of gamma-emitting fission product distribution, swelling and fuel porosity measurements, metallography of kernel structural changes, kernel physicochemical and thermomechanical interaction with cladding material, X-ray diffraction analysis and oxygen enhancement ratio assessment. It is shown that with burn-up range 8.9−12.4 % FIMA uranium dioxide pellets are compatible with ChS-68 and EK-164 cladding steels. It leads to structural changes and fuel creep under restricted swelling inducing high-temperature corrosion not exceeding 65 μm. There is a tendency to residual gap broadening with burn-up increase due to high-porous unstable rim of the pellets. Fuel film generation on the cladding internal surface is typical for MOX fuel pellets with burn-up to 11.6 % FIMA. Kernel microstructure contains low-porous globular which interpreted as depleted uranium dioxide. Significant internal corrosion increase regarding standard fuel is not detected. Vibropac uranium gettered MOX fuel with burn-up to 10.1 % FIMA shows no high-temperature interaction with ChS-68 steel cladding. However an abnormal thermomechanic deformation of the cladding with a swelling kernel at the core-reflector boundary is observed due to getter nonuniform distribution and oxidation, and high local concentration of splitted cesium.

Country/Int. Organization

Russian Federation

Primary author

Mr Evgenii Kinev (Institute of Nuclear Materials)


Mr Andrey Barybin (Institute of Nuclear Materials) Mrs Natalia Glushkova (Institute of Nuclear Materials) Mr Vladimir Tsygvintsev (Institute of Nuclear Materials)

Presentation materials