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X
KURISAKA, Kenichi
20  Ergebnisse:
Personensuche X
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1

Reduction of accident occurrence frequencies by taking safe..:

NISHINO, Hiroyuki ; KURISAKA, Kenichi ; NARUTO, Kenichi..
Mechanical Engineering Journal.  11 (2024)  2 - p. 23-00409-23-00409 , 2024
Link: https://doi.org/10.1299/..
 
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2

Time-dependent change in occurrence rate of steam generator..:

KURISAKA, Kenichi
Mechanical Engineering Journal.  11 (2024)  2 - p. 23-00377-23-00377 , 2024
Link: https://doi.org/10.1299/..
 
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3

Development of probabilistic risk assessment methodology ag..:

NISHINO, Hiroyuki ; YAMANO, Hidemasa ; KURISAKA, Kenichi
Mechanical Engineering Journal.  10 (2023)  4 - p. 22-00387-22-00387 , 2023
Link: https://doi.org/10.1299/..
 
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4

Development of a probabilistic risk assessment methodology ..:

YAMANO, Hidemasa ; NISHINO, Hiroyuki ; KURISAKA, Kenichi
Mechanical Engineering Journal.  5 (2018)  4 - p. 18-00093-18-00093 , 2018
Link: https://doi.org/10.1299/..
 
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5

Development of probabilistic risk assessment methodology of..:

NISHINO, Hiroyuki ; YAMANO, Hidemasa ; KURISAKA, Kenichi
Mechanical Engineering Journal.  5 (2018)  4 - p. 18-00079-18-00079 , 2018
Link: https://doi.org/10.1299/..
 
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6

Updating of local blockage frequency in the reactor core of..:

Nishimura, Masahiro ; Fukano, Yoshitaka ; Kurisaka, Kenichi.
Journal of Nuclear Science and Technology.  54 (2017)  11 - p. 1178-1189 , 2017
Link: https://doi.org/10.1080/..
 
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7

Fundamental safety strategy against severe accidents on pro..:

Onoda, Yuichi ; Kurisaka, Kenichi ; Sakai, Takaaki
Journal of Nuclear Science and Technology.  53 (2016)  11 - p. 1774-1786 , 2016
Link: https://doi.org/10.1080/..
 
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8

Development of probabilistic risk assessment methodology ag..:

Yamano, Hidemasa ; Nishino, Hiroyuki ; Kurisaka, Kenichi
Nuclear Engineering and Design.  308 (2016)  - p. 86-95 , 2016
Link: https://doi.org/10.1016/..
 
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9

Updating of adventitious fuel pin failure frequency in sodi..:

Fukano, Yoshitaka ; Naruto, Kenichi ; Kurisaka, Kenichi.
Journal of Nuclear Science and Technology.  52 (2014)  9 - p. 1122-1132 , 2014
Link: https://doi.org/10.1080/..
 
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10

Evaluation of MONJU Core Damage Risk due to Control Rod Fun..:

SOTSU, Masutake ; KURISAKA, Kenichi
Journal of Power and Energy Systems.  6 (2012)  3 - p. 462-471 , 2012
Link: https://doi.org/10.1299/..
 
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11

Development of System Based Code (2) Application of Reliabi..:

TAKAYA, Shigeru ; OKAJIMA, Satoshi ; KURISAKA, Kenichi...
Journal of Power and Energy Systems.  5 (2011)  1 - p. 60-68 , 2011
Link: https://doi.org/10.1299/..
 
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12

Development of System Based Code (1) Reliability Target Der..:

KURISAKA, Kenichi ; NAKAI, Ryodai ; ASAYAMA, Tai.
Journal of Power and Energy Systems.  5 (2011)  1 - p. 19-32 , 2011
Link: https://doi.org/10.1299/..
 
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13

Technological Feasibility of Two-Loop Cooling System in JSF:

Yamano, Hidemasa ; Kubo, Shigenobu ; Kurisaka, Ken-Ichi..
Nuclear Technology.  170 (2010)  1 - p. 159-169 , 2010
Link: https://doi.org/10.13182..
 
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14

Assessment of FBR MONJU Accident Management Reliability in ..:

SOTSU, Masutake ; KURISAKA, Kenichi
Journal of Nuclear Science and Technology.  47 (2010)  10 - p. 867-883 , 2010
Link: https://doi.org/10.1080/..
 
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15

Evaluation of MONJU Core Damage Risk with Change of AOT Usi..:

SOTSU, Masutake ; KURISAKA, Kenichi
Journal of Power and Energy Systems.  4 (2010)  1 - p. 84-93 , 2010
Link: https://doi.org/10.1299/..
 
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