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Journal Articles

Safety improvement in building layout design to meet the safety design criteria for the Generation IV SFR

Kato, Atsushi; Chikazawa, Yoshitaka; Nabeshima, Kunihiko; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.593 - 600, 2015/05

Japan sodium cooled fast reactor is the advanced loop type reactor developing in Japan. After the Fukushima-Dai-ichi NPP accident, system enhancement against severe accident have been investigated mainly for residual decay heat removal system, spent fuel storage system and emergency power sources in order to satisfy the safety design criteria for Generation IV SFR. This paper describes principle of the building layout design and the actual approach to be consistent with the recent design enhancement in JSFR. From the perspective of greater ability to withstand severe events, the principles of the building layout design as the measures against aircraft attack and the consequential fire, and tsunami are introduced in order to avoid local event initiating and simultaneous redundant failure of the safety grade facilities and could achieve lowering risk of the loss of all stuck and maintaining the essential power supply.

Journal Articles

Technical issues and their solutions in HTGR gas turbine system

Muto, Yasushi; Ishiyama, Shintaro

Nihon Genshiryoku Gakkai-Shi, 42(10), p.1020 - 1027, 2000/10

 Times Cited Count:1 Percentile:12.08(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Preliminary design of 600MWt HTGR-gas turbine plant

; Miyamoto, Yoshiaki; Shiozawa, Shusaku

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

JAEA Reports

None

PNC TN1700 93-014, 139 Pages, 1993/01

PNC-TN1700-93-014.pdf:3.38MB

no abstracts in English

JAEA Reports

None

PNC TN1700 93-013, 41 Pages, 1993/01

PNC-TN1700-93-013.pdf:0.66MB

no abstracts in English

JAEA Reports

None

PNC TN1700 93-001, 681 Pages, 1993/01

PNC-TN1700-93-001.pdf:11.85MB

no abstracts in English

Oral presentation

Safety improvement in SFR building layout design

Kato, Atsushi; Chikazawa, Yoshitaka; Nabeshima, Kunihiko; Iwasaki, Mikinori*; Akiyama, Yo*; Oya, Takeaki*

no journal, , 

Based on the Safety design criteria for the Generation-IV sodium cooled fast reactor and intrinsic features of SFR, we studied the reactor building layout design in order to improve its safety.

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