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JAEA Reports

Evaluation of insertion property of control rod of JRR-3 at earthquake by time history response analysis method

Kawamura, Sho; Kikuchi, Masanobu; Hosoya, Toshiaki

JAEA-Technology 2021-041, 103 Pages, 2023/02

JAEA-Technology-2021-041.pdf:8.7MB

In response to new regulatory standard for research and test reactor which is enforced December 2013, JRR-3 got license in November 2018 by formulate new design basis ground motion. After that we evaluated for insertion property of control rod using that new design basis ground motion, and that evaluation results were accepted as approval of the design and construction method by Nuclear Regulation Authority. Now, we re-evaluated to insertion property of control rod about neutron absorber and follower fuel element by time history response analysis method. In this report, it shows that new results have sufficiency of margin compared with the past results that are accepted as approval of the design and construction method.

JAEA Reports

Seismic evaluation of the CRDM and the CRDM guide tube for JRR-3

Kikuchi, Masanobu; Kawamura, Sho; Hosoya, Toshiaki

JAEA-Technology 2021-040, 86 Pages, 2023/02

JAEA-Technology-2021-040.pdf:3.26MB

In JRR-3, in response to new regulatory standard for research and test reactor which is enforced December 2013, we established new design basis ground motion for confirming new regulatory standard and carried out seismic evaluations of the appointments, instruments and structures which are installed in JRR-3 by using that earthquake motion. This report shows that the result of evaluations by fatigue strength evaluation, which is more detailed evaluation approach, about Control Rod Drive Mechanism (CRDM) and the CRDM Guide Tube that have gotten the serious result of seismic safety margin by using time history response analysis method. As a result, it was confirmed that CRDM and the CRDM Guide Tube have sufficient seismic safety margin.

Journal Articles

Application of revised procedure on determining large excess reactivity of operating reactor; Fuel addition method

Nagao, Yoshiharu; Hosoya, Toshiaki; Kaneko, Yoshihiko*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.153 - 163, 2002/06

no abstracts in English

Oral presentation

Investigation of JRR-3 control rod worth changed with burn-up of follower fuel elements

Hosoya, Toshiaki; Kato, Tomoaki; Murayama, Yoji

no journal, , 

Oral presentation

Investigation of modification on JRR-3 heavy water tank to produce a large diameter (12 inch) NTD-Si, 1; Nuclear properties analysis

Hosoya, Toshiaki; Yamaguchi, Atsushi; Kato, Tomoaki; Terakado, Yoshibumi

no journal, , 

no abstracts in English

Oral presentation

Inspection and repair in JRR-3 after the 2011 off the Pacific coast of Tohoku Earthquake

Hosoya, Toshiaki; Nagadomi, Hideki; Torii, Yoshiya

no journal, , 

no abstracts in English

Oral presentation

Consideration of let boric acid in JRR-3 reactor core for shutdown at the time of accident

Iwaasa, Masahiro; Hosoya, Toshiaki; Araki, Masaaki

no journal, , 

no abstracts in English

Oral presentation

The Effect of accumulation burnable poison during long-term shut down in the JRR-3

Kiba, Kazumasa; Hosoya, Toshiaki; Horiguchi, Hironori

no journal, , 

no abstracts in English

8 (Records 1-8 displayed on this page)
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