Fission gas release from irradiated mixed-oxide fuel pellet during simulated reactivity-initiated accident conditions; Results of BZ-3 and BZ-4 tests

Kakiuchi, Kazuo ; Udagawa, Yutaka ; Amaya, Masaki

In order to investigate fission gas release behavior of high-burnup mixed-oxide (MOX) fuel pellet for LWR under reactivity-initiated accident (RIA), the tests called BZ-3 and BZ-4 were conducted at the Nuclear Safety Research Reactor (NSRR) in Japan Atomic Energy Agency (JAEA). Electron probe microanalysis and rod-puncture tests were performed on the fuel pellets before and after pulse irradiation tests, and from the comparison between the puncture test results and the results evaluated from EPMA, it was suggested that fission gas release from not only the Pu-spot but also the Pu-spot-excluded region.

Language	:	English
Journal	:	Annals of Nuclear Energy
Volume	:	155
Number	:
Pages	:	p.108171_1 - 108171_11
Publication Year/Month	:	2021/06
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Paper URL	:	https://doi.org/10.1016/j.anucene.2021.108171
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	Reactivity-initiated accident; Mixed-oxide fuel; Fission gas release; Fuel pellet; SEM/EPMA; Puncture test; Radial Xe concentration profile
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Article of JAEA R&D Review	:
Cooperating Institute	:	原子力規制委員会原子力規制庁

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Registration No. : AA20200318
JAEA Abstracts No. : 49000373
Paper Submission No. : 23926

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