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Onishi, Takashi; Sekioka, Ken*; Suto, Mitsuo*; Tanaka, Kosuke; Koyama, Shinichi; Inaba, Yusuke*; Takahashi, Hideharu*; Harigai, Miki*; Takeshita, Kenji*
Energy Procedia, 131, p.151 - 156, 2017/12
Times Cited Count:11 Percentile:98.3(Energy & Fuels)no abstracts in English
Matsuura, Hideharu*; Minohara, Nobumasa*; Inagawa, Yusuke*; Takahashi, Miyuki*; Oshima, Takeshi; Ito, Hisayoshi
Materials Science Forum, 556-557, p.379 - 382, 2007/00
no abstracts in English
Matsuura, Hideharu*; Minohara, Nobumasa*; Takahashi, Miyuki*; Oshima, Takeshi; Ito, Hisayoshi
Proceedings of 7th International Workshop on Radiation Effects on Semiconductor Devices for Space Application (RASEDA-7), p.181 - 184, 2006/10
no abstracts in English
Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Takahashi, Masashi; Tobita, Tsutomu*; Hayashi, Kimio; Saito, Takashi; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Kato, Shigeru*
JAERI-Research 2002-012, 39 Pages, 2002/06
no abstracts in English
Takahashi, Masashi; Ueta, Shohei; Yasuda, Atsushi*; Yoshimuta, Shigeharu*; Kato, Shigeru*; Sawa, Kazuhiro
JAERI-Tech 2001-091, 29 Pages, 2002/01
no abstracts in English
Sato, Masuo*; Fukawa, Naohiro*; Tamaoki, Tetsuo*; Takahashi, Hideji*; Ito, Atsushi*; Yoshida, Megumi*; Sonoda, Yukio*; Yamamoto, Kazuhiko*; Maruyama, Fumi*
PNC TJ9164 89-003, 200 Pages, 1989/03
In nuclear power plant, we need to realize the computerization for the management of the plant operation and maintenance. Especially, in a periodic inspection, lots of works are concentrated. A great deal of man power is required for examining the permission of works, publishing the component isolation tags and making or revising the documents to control the schedules. Recently, in Light Water Reactor, a lot or computerization systems are developed. We design the plant management system in consideration of the characteristics of a Fast Breeder Reactor. We embody the softwear methods and hardwear systems widely to systematize the plant management technology that is accumulated at the experimental reactor JOYO. We can expect an economization and an inprovment of realiability and efficiency of the plant management.
Takahashi, Hideji*; *; *; *; *; *
PNC TN941 85-118, 415 Pages, 1985/08
Loss of electric power supply test and manual scram test were conducted as the transient response test on anomaly condition, in 100 MW power ascension test of JOYO MK-II core. The above transient response tests were performed to confirm the following items. (1)The thermal transient characteristics in comparison with the design criteria. (2)Sequential operation of the plant protection system, electric supply system for emergency and other components, and finally the shut down of the reactor in safe. Among the above two transient response tests, this report describes the result of the loss of power test. Main results obtained by the test are as follows. (1) The thermal transient characteristics of each part of main coolant system are within the design criteria. (2) The plant protection system and other components start to operate within the time required by the design. (3) The non-cut-off and the emergency power supply system operate as expected. (4) Both the flow coast down characteristics of the primary main cooling system and the flow rate generated by the pony motors are satisfactory in comparison with the design criteria. (5) The natural circulation of the secondary main loop is observed after the power cut-off. The measured flow rate of the natural circulation is about. 5.7% of the normal flow rate, just after the scram. (6) By the improvement of the secondary loop temperature control system, hunching of the main cooler outlet temperature clarified to be small, enough to satisfy the design criteria.
Takahashi, Hideji*; *; *; *; *; *
PNC TN941 85-115, 79 Pages, 1985/08
This test was carried out after restart of secondary main pump at the end of 100 MW loss of electric power test. The purpose of this test is to confirm that the decay heat can be removed by main cooling system after reactor shut-down of loss of power test. Summary of this test result is as in the following. (1)The decay heat was removed by the maincooling system after the loss of electric power test from 100 MW power operation. Furthermore the plant mode transfered to hot stand-by phase. (2)At the test, the rate of the coolant temperature decrease did not exceed -50C/hr. (3)There was no anomalous sodium temperature rise at the outlet of the center fuel sub-assembly.
Takahashi, Hideji*; *; *; *; *; *
PNC TN941 85-114, 280 Pages, 1985/08
Manual scram test and loss of electric power supply test were conducted as one of the thermal transient test during MK-II core performance test term. Following items are confirmed by the test. (1)The thermal transient characteristics were within the design criteria. (2)The plant protection system, the electric supply system for emergency and other components operated in design sequence, and the plant system shut down in safety. In this report, the results of the manual scram test were described. Summary of the test result is as in the following. (1)During to improvement of secondary coolant temperature control system, the thermal transient characteristics of each part of main cooling system are within the design criteria. (2)An operation time of safety protection system are within the design criteria. (3)The scram time of No.5 control rod have changed with passage of time, but recently the change of the time was stabilized.
Onishi, Takashi; Sekioka, Ken*; Suto, Mitsuo*; Tanaka, Kosuke; Koyama, Shinichi; Takahashi, Hideharu*; Inaba, Yusuke*; Harigai, Miki*; Takeshita, Kenji*
no journal, ,
no abstracts in English
Okada, Hidetoshi*; Uchida, Shunsuke*; Naito, Masanori*; Chimi, Yasuhiro; Hanawa, Satoshi; Kojima, Masayoshi*; Takahashi, Hideharu*; Kikura, Hiroshige*
no journal, ,
no abstracts in English
Shizume, Yuki*; Takata, Atsushi*; Nabae, Hiroyuki*; Suzumori, Koichi*; Oba, Hironori; Akaoka, Katsuaki; Wakaida, Ikuo; Kikura, Hiroshige*; Takahashi, Hideharu*; Endo, Gen*
no journal, ,
no abstracts in English