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Journal Articles

Rehearsal and actual measurement of Fugen spent fuel assemblies by integrated PNAR and SINRD under the JAEA-USDOE collaboration program

Hayashi, Kenta; Nakamura, Takahisa; Takagi, Hisatsugu; Horie, Kaoru; Nakayama, Tamotsu; Hashimoto, Kazuhiko; Hayashi, Shoichi; Nakamura, Shinji; Takenaka, Shigeki; Ishizuka, Nobuo; et al.

Proceedings of INMM 54th Annual Meeting (CD-ROM), 10 Pages, 2013/07

JAEA and USDOE (Los Alamos National Laboratory (LANL)) have been collaborating on spent fuel measurements with a PNAR/SINRD NDA instrument at Fugen, in the course of the NGSI Spent Fuel Nondestructive Assay Project. In this collaboration, LANL's role has been to design and fabricate the detector (integrated PNAR and SINRD system), while JAEA's role has been to undertake the installation of the detector at the appropriate position in the spent fuel pool and to prepare for the actual measurements. In this paper we report the rehearsal of the measurement using a mock-up detector and a dummy fuel assembly in December 2012 and the plan of actual measurements in June 2013 (at the time of submission of this paper).

Journal Articles

Preparation for Pu measurement test of Fugen spent fuel assemblies by integrated PNAR/SINRD

Katano, Yoshiaki; Ebara, Noriyasu; Takagi, Hisatsugu; Nakamura, Takahisa; Bolind, A.; Seya, Michio

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2012/10

The ATR, "Fugen" was a prototype nuclear reactor moderated by heavy water but cooled by boiling light water. It terminated its operations in 2003 and is now being decommissioned. Nevertheless, the spent-fuel pool at Fugen still remains and currently contains both MOX spent-fuel assemblies, and it is flexible enough to be able to conduct Non Destructive Assays (NDA) experiments on the spent fuel assemblies. Therefore, JAEA and the U.S. Los Alamos National Laboratory (LANL) are planning to conduct a test of an integrated PNAR/SINRD NDA measurement system at Fugen in 2013. LANL is designing and constructing the system, and JAEA is preparing the Fugen site for the test. The total experience of preparing for and conducting NDA measurements on actual spent fuel assemblies will teach important lessons about the practicality of applying such measurements in the future to spent fuel assemblies from commercial LWR power plants, especially with regard to satisfying legal and safety requirements.

Journal Articles

The JAEA part of the joint JAEA-U.S. DOE project for Pu measurement of Fugen spent fuel assemblies by integrated PNAR and SINRD

Ebara, Noriyasu; Katano, Yoshiaki; Nakamura, Takahisa; Takagi, Hisatsugu; Bolind, A.; Seya, Michio

Proceedings of INMM 53rd Annual Meeting (CD-ROM), 10 Pages, 2012/07

The Fugen advanced thermal reactor stopped operations in 2003 and is now being decommissioned. Nevertheless, the spent-fuel pool at Fugen still remains and currently contains both MOX and UO$$_{2}$$ spent-fuel assemblies. Because Fugen was a prototype, the standard operations at the spent-fuel pool are flexible enough to be able to conduct NDA experiments on the spent fuel. Therefore, JAEA and the U.S.DOE are planning to conduct a test of an integrated PNAR and SINRD NDA measurement system at Fugen in 2013. LANL is designing and constructing the detector, and JAEA is preparing the Fugen site for the test. It will be report to select for install location of NDA test device in spent fuel pool, how to installation and study of test flow.

Journal Articles

TWENTY FOUR YEAR'S EXPERIENCE OF WATER CHEMISTRY IN THE FUGEN NUCLEAR POWER STATION

; Kitabata, Takuya; ; Takagi, Hisatsugu; ;

Dai-13-Kai Kantaiheiyo Genshiryoku Kaigi 2002, 0 Pages, 2002/00

None

Journal Articles

None

Takagi, Hisatsugu; ;

Saikuru Kiko Giho, (12), p.66 - 74, 2001/09

None

Oral presentation

Processing method of radioactive tetrachloroethylene liquid waste

Sato, Yuji; Takagi, Hisatsugu; Hamada, Nobuyuki; Sekine, Tomokazu*; Takeda, Masayuki*; Akiyama, Takashi*

no journal, , 

no abstracts in English

Oral presentation

Improvement of processing method for radioactive tetrachloroethylene liquid waste

Sato, Yuji; Takagi, Hisatsugu; Morita, Satoshi; Shimomura, Tatsuo*; Sekine, Tomokazu*; Takeda, Masayuki*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of effectiveness of SCC prevention technologies after long term operation at the Fugen Power Station

Yuasa, Toyotaka; Abe, Teruyoshi; Nakamura, Takahisa; Myochin, Munetaka; Takagi, Hisatsugu

no journal, , 

Suffered SCC (stress corrosion cracking) at the primary cooling system in 1980, the Fugen power station introduced the three preventive technologies immediately. After the upgrade of the plant, no SCC occurred during the operation period. We have inspected the actual structural materials of the Fugen power station on its decommissioning stage to evaluate effectiveness of SCC management technologies, which are combining material replacement, induction heating stress improvement (IHSI) to reduce the welding residual tensile stress, and application of hydrogen addition to reduce oxygen in the water. No crack in the materials was found by metallurgical structure observation. Moreover, judging from the analysis of residual stress and the heat affected zone in the materials, the effectiveness of SCC management technologies was verified.

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