Fuel pin irradiation test at up to 5at% burnup in BOR-60 for oxide-dispersion-strengthened ferritic steel claddings

Kaito, Takeji ; Ukai, Shigeharu*; Povstyanko, A. V.*; Efimov, V. N.*

The fuel pin irradiation test of the ODS claddings, which were developed as promising materials for higher burnup fuels, was carried out at high cladding temperatures of 700 $^{circ}$ C and 650 $^{circ}$ C in BOR-60. Vibro-packed MOX fuels with low O/M ratio were used. The integrity of the ODS cladding fuel pins was maintained up to burnup of 5.1 at% and neutron dose of 21 dpa, and FCCI of the ODS claddings was very small. These results suggested that the ODS claddings and low O/M ratio fuels are the most appropriate fuel pin system for high burnup fuel.

Language	:	English
Journal	:	Journal of Nuclear Science and Technology
Volume	:	46
Number	:	6
Pages	:	p.529 - 533
Publication Year/Month	:	2009/06
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Paper URL	:	https://doi.org/10.3327/jnst.46.529
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	no keyword
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Cooperating Institute	:	Research Institute of Atomic Reactors

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Registration No. : AA20080974
JAEA Abstracts No. : 37001014
Paper Submission No. : 6007

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