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Journal Articles

Development of passive shutdown system for SFR

Nakanishi, Shigeyuki*; Hosoya, Takusaburo; Kubo, Shigenobu*; Kotake, Shoji; Takamatsu, Misao; Aoyama, Takafumi; Ikarimoto, Iwao*; Kato, Jungo*; Shimakawa, Yoshio*; Harada, Kiyoshi*

Nuclear Technology, 170(1), p.181 - 188, 2010/04

 Times Cited Count:14 Percentile:67.77(Nuclear Science & Technology)

A self-actuated shutdown system (SASS) for sodium cooled fast reactor (SFR) is a passive safety feature which inserts control rods by the gravity force, where the detachment of the rods would be achieved by the coolant temperature rise under anticipated transient without scram (ATWS) conditions. Various out-of-pile tests have already carried out to investigate the basic characteristics of SASS, and a demonstration test of holding stability under the reactor operation condition has been performed, where a function test of the driving system to re-connect and of pulling out the control rod have been done in the experimental reactor JOYO. The element irradiation tests have been also conducted to confirm that no impact will be foreseen by the irradiation. The effectiveness of SASS for a reference core design of JSFR has been evaluated through all types of ATWS. As a result, it is ensured that JSFR will have a reliable passive shutdown system.

Journal Articles

Conceptual design for Japan Sodium-cooled Fast Reactor, 4; Developmental study of steel plate reinforced concrete containment vessel for JSFR

Negishi, Kazuo; Hosoya, Takusaburo; Sato, Kenichiro*; Somaki, Takahiro*; Matsuo, Ippei*; Shimizu, Katsusuke*

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9418_1 - 9418_7, 2009/05

An innovative containment vessel, namely Steel plate reinforced Concrete Containment Vessel (SCCV) is developed for Japan Sodium-Cooled Fast Reactor (JSFR). Reducing plant construction cost is one of the most important issues for commercialization of fast reactors. This study investigated construction issues including the building structure and the construction method as well as design issues in terms of the applicability of SCCV to fast reactors. An experimental study including loading and/or heating tests has been carried out to investigate the fundamental structural features, which would be provided to develop methodology to evaluate the feasibility of SCCV under the severe conditions. In this paper, the test plan is described as well as the first test results.

Oral presentation

Conceptual design toward the commercial reactor of JSFR, 2; Technologies for safety enhancement

Kubo, Shigenobu*; Shimakawa, Yoshio*; Yamano, Hidemasa; Hosoya, Takusaburo*

no journal, , 

A self-actuated shutdown system (SASS) and recriticality-free technologies are under consideration to be introduced to commercial reactors of Japan Sodium-cooled Fast Reactor (JSFR) as candidates of innovative technology to enhance safety. The Fast Reactor Cycle Technology Development (FaCT) project has studied the applicability of these technologies based on relative research and development and on achievements in the conceptual design for JSFR safety. This paper reports the result of the applicability study.

Oral presentation

Studies on the safety design criteria of Generation-IV Sodium-cooled Fast Reactors, 2; Safety design criteria for SFR specific structures, systems and components

Fujita, Satoshi; Hosoya, Takusaburo*; Kubo, Shigenobu; Okano, Yasushi; Sakai, Takaaki; Nakai, Ryodai

no journal, , 

no abstracts in English

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