Applicability of NSRR room/high temperature test results to fuel safety evaluation under power reactor conditions

Sugiyama, Tomoyuki ; Umeda, Miki ; Udagawa, Yutaka ; Sasajima, Hideo ; Suzuki, Motoe; Fuketa, Toyoshi

Pulse irradiation tests of high burnup light water reactor fuels were performed at the Nuclear Safety Research Reactor (NSRR) in order to investigate transient fuel behavior and fuel failure limit under the reactivity-initiated accident (RIA) conditions. This paper presents new data from the NSRR high temperature tests at 250 to 290 $^{circ}$ C as well as data from the room temperature tests at around 20 $^{circ}$ C, and discusses the applicability of these data to the fuel safety evaluation under power reactor conditions.

Language	:	English
Journal	:	Proceedings of OECD/NEA Workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents (CD-ROM)
Volume	:
Number	:
Pages	:	12 Pages
Publication Year/Month	:	2009/09
Meeting title	:	OECD/NEA Workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents
Held date	:	2009/09
Location (city)	:	Paris
Location (country)	:	France
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:
Keywords	:	no keyword
Research Facility	:	NSRR(原子炉安全性研究炉)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	経済産業省原子力安全・保安院

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Registration No. : BB20083580
JAEA Abstracts No. : 37001569
Paper Submission No. : 6581

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