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Yamada, Fumiaki; Arikawa, Mitsuhiro*; Fukano, Yoshitaka
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05
In sodium-cooled fast reactor, since the coolant does not need to be pressurized, a pipe break due to the internal pressure does not occur physically. For safety margin in Japanese prototype fast breeder reactor (Monju), the guillotine pipe break accident, i.e., loss of integrity (LOPI) has been analyzed as an extreme assumption for beyond design basis accidents (B-DBAs) in the licensing application for the permit. The cooling capability of the core was re-evaluated in this paper during a large-scale, more specifically guillotine pipe break at the primary heat transport system (PHTS) in Monju, newly considering the following latest findings: (a) Experimental data on sodium boiling in fuel assemblies, (b) Actual PHTS pump coast-down characteristics, and (c) Transient burst test data on irradiated fuel claddings. The analysis models were the validated and simulations were re-performed also using the actual Monju data such as the response time to the trip signals, etc. As a result, it was clarified that the ratio of failed fuel claddings does not exceed around 3% of all of fuel assemblies, as in the past licensing analysis. The safety has been reconfirmed to be secured without significant core damage even under an extreme assumption of a double-ended guillotine pipe break at the PHTS in Monju.
Amaya, Masaki
no journal, ,
The objectives of the fuel safety research program at JAEA are to evaluate the adequacy of present safety criteria and safety margins, to provide a database for the regulation on improved fuels using new materials of cladding and pellet, and to provide reasonably mechanistic computer codes for regulatory application, in terms of light water reactor fuel. In this presentation, in addition to recent progress in the reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA) test programs, an overview of the current status of the fuel safety research at JAEA is described.
Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Tasaki, Yudai; Udagawa, Yutaka
no journal, ,
no abstracts in English
Taniguchi, Yoshinori; Udagawa, Yutaka
no journal, ,
no abstracts in English
Taniguchi, Yoshinori; Udagawa, Yutaka
no journal, ,
no abstracts in English