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Suzuki, Mitsutoshi; Izumi, Yoshinori; Kimoto, Toru; Naoi, Yosuke; Inoue, Takeshi; Hoffheins, B.
IAEA-CN-184/64 (Internet), 8 Pages, 2010/11
In support of the 3S initiative, Japan Atomic Energy Agency (JAEA) has been conducting detailed analyses of the R&D programs and cultures of each of the S areas to identify overlaps where synergism and efficiencies might be realized, to determine where there are gaps in the development of a mature 3S culture, and to coordinate efforts with other Japanese and international organizations. Lessons learned in these activities can be applied to developing more efficient and effective 3S infrastructures for incorporating into Safeguards by Design methodologies. In this presentation, a risk-informed approach regarding integration of 3S will be introduced. An initial examination of incident probability and postulated consequence analyses, which are tools familiar to the nuclear safety culture, will be applied to predict and evaluate inherent uncertainties of proliferation and security risks.
Oba, Toshinobu; Inoue, Takeshi; Unesaki, Hironobu*
Proceedings of International Meeting on Reduced Enrichment for Research and Test Reactors 2008 (RERTR 2008) (Internet), 10 Pages, 2008/10
The current status of research and test reactors relevant to RERTR program is described. The reduced enrichment programs for the JRR-3, JRR-4 and JMTR of Japan Atomic Energy Agency (JAEA) were completed by 1999. The core of JRR-3 was converted from aluminide (UAl
-Al) to silicide (U
Si
-Al) in order to reduce the amount of spent fuel. The JRR-3 has been well operated with LEU fuel since 1990 and reached 55,400 MWD in December 2007 at the last operation cycle. Operation with 10 cycles (26 days/cycle) is scheduled for one year from July 2008 to July 2009. The JRR-4 is under shut down condition to replace reflector elements with new ones. It will restart in July 2009. The JMTR is under refurbishment of irradiation facilities. Kyoto University Research Reactor (KUR) has terminated its operation with HEU on February 2006. Shipment of all HEU spent fuel elements to the United States has been successfully completed. The full core conversion of KUR to LEU fuel, including fuel fabrication, is currently under progress and the reactor restart using LEU core is expected to be achieved in May 2009.
Sakazume, Yoshinori; Aoki, Hiromichi; Haga, Takahisa; Fukaya, Hiroyuki; Sonoda, Takashi; Shimizu, Kaori; Niitsuma, Yasushi*; Ito, Mitsuo; Inoue, Takeshi
JAEA-Technology 2007-069, 44 Pages, 2008/02
JAEA-Technology-2007-069.pdf:4.55MB
Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2006 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. The total number of the samples analyzed in FY 2006 was 254. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2006.
Fukaya, Hiroyuki; Aoki, Hiromichi; Haga, Takahisa; Nishizawa, Hidetoshi; Sonoda, Takashi; Sakazume, Yoshinori; Shimizu, Kaori; Niitsuma, Yasushi*; Shirahashi, Koichi; Inoue, Takeshi
JAEA-Technology 2007-005, 27 Pages, 2007/03
JAEA-Technology-2007-005.pdf:1.97MB
Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2005 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. Also analyzed were the samples from raffinate treatment and its preliminary tests. The raffinate was generated, since FY 2000, during preliminary experiments on U/Pu extraction-pulification to fix the operation condition to prepare plutonium solution fuel to be used for criticality experiments at STACY. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2005.
Unesaki, Hironobu*; Ota, Kazunori; Inoue, Takeshi
Proceedings of International Meeting on Reduced Enrichment for Research and Test Reactors 2007 (RERTR 2007) (Internet), 11 Pages, 2007/00
The status of reduced enrichment program for research reactors in Japan will be reviewed. Among the fourteen research reactors and critical assemblies in operation in Japan, those concerned with the RERTR program are the JRR-3, JRR-4 and JMTR of Japan Atomic Energy Agency (JAEA) and KUR of Kyoto University Research Reactor Institute (KURRI). Reduced enrichment programs for the JRR-3, JRR-4 and JMTR of JAEA has been completed by 1999, and the reactors are being satisfactory operated using LEU fuels. In KURRI, the KUR has terminated its operation with HEU on February 2006. Licensing for the full core conversion of KUR to LEU fuel is under progress and the core conversion to LEU is expected to be completed in 2008.
Nishizawa, Hidetoshi; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Shimizu, Kaori; Haga, Takahisa; Sakai, Yutaka*; Akutsu, Hideyuki*; Niitsuma, Yasushi; Inoue, Takeshi; et al.
JAEA-Technology 2006-007, 24 Pages, 2006/03
JAEA-Technology-2006-007.pdf:1.81MB
Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF(Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY(Static Experiment Critical Facility), TRACY(Transient Experiment Critical Facility)and the fuel treatment system. Analyzed in FY 2004 were uranyl nitrate solution fuel samples taker before and after experiments of STACY and TRACY, samples for the preparation of uranyl nitrate solution fuel, and samples for nuclear material accountancy purpose. Also analyzed were the samples from raffinate treatment and its preliminary tests. The raffinate was generated, since FY 2000, during preliminary experiments on U/Pu extraction-pulification to fix the operation condition to prepare plutonium solution fuel to be used for criticality experiments at STACY. The total number of the samples analyzed in FY 2004 was 160. This report summarizes works related to the analysis and management of the analytical laboratory in the FY 2004.
Inoue, Takumi*; Sueoka, Atsuo*; Maehara, Takeshi*; Nakano, Hiroshi*; Kanemoto, Hiroyuki*; Murakami, Yukitaka*
Nihon Kikai Gakkai Rombunshu, C, 72(714), p.380 - 387, 2006/02
None
Shimizu, Kaori; Gunji, Kazuhiko*; Haga, Takahisa*; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Sakai, Yutaka*; Akutsu, Hideyuki; Niitsuma, Yasushi*; Inoue, Takeshi; et al.
JAERI-Tech 2004-078, 27 Pages, 2005/02
JAERI-Tech-2004-078.pdf:1.84MB
Analysis of the uranyl nitrate solution fuel are carried out at the analytical laboratory, NUCEF (the Nuclear Fuel Cycle Engineering Research Facility), which provide essential data for the operations of STACY (the Static Experiment Critical Facility), TRACY (the Transient Experiment Critical Facility) and the fuel treatment system.In the FY 2003, analysis of the uranyl nitrate solution fuel from STACY/TRACY on its pre- and post-operations, analysis of the uranyl nitrate solution under preparation stage for the fuel and analysis for nuclear material accountancy purpose, have been conducted. In addition, analysis on the third U/Pu extraction/separation tests among the preliminary tests to confirm adjustment condition of plutonium solution fuel for its further use at STACY from 2000, and analysis on the experiments to treat extraction waste, were conducted. A total number of analytical samples in the FY 2003 were 156.This report summarizes works related to the analysis and management of the analytical laboratory in the FY 2003.
Haga, Takahisa*; Gunji, Kazuhiko; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Sakai, Yutaka; Niitsuma, Yasushi; Togashi, Yoshihiro; Miyauchi, Masakatsu; Sato, Takeshi; et al.
JAERI-Tech 2004-005, 54 Pages, 2004/02
JAERI-Tech-2004-005.pdf:2.06MB
Criticality experiments using uranyl nitrate solution fuel are being conducted at STACY (the Static Experiment Critical Facility) and TRACY (the Transient Experiment Critical Facility) in NUCEF (the Nuclear Fuel Cycle Safety Engineering Research Facility). Chemical analyses of the solution have been carried out to take necessary data for criticality experiments, for treatment and control of the fuel, and for safeguards purpose at the analytical laboratory placed in NUCEF. About 300 samples are analyzed annually that provide various kinds of data, such as uranium concentration, isolation acid concentration, uranium isotopic composition, concentration of fission product (FP) nuclides, tri-butyl phosphoric acid (TBP) concentration, impurities in the solution fuel and so on. This report summarizes the analytical methods and quality management of the analysis for uranyl nitrate solution relating to the criticality experiments.
m-wavelength range by using proton beam writingMiura, Kenta*; Machida, Yuki*; Uehara, Masato*; Hanaizumi, Osamu*; Ishii, Yasuyuki; Sato, Takahiro; Takano, Katsuyoshi; Okubo, Takeru; Yamazaki, Akiyoshi; Inoue, Aichi; et al.
no journal, ,
no abstracts in English
Izumi, Yoshinori; Kitamura, Takafumi; Kimoto, Toru; Suzuki, Mitsutoshi; Inoue, Takeshi; Naoi, Yosuke; Tamai, Hiroshi; Yamamura, Tsukasa; Kadota, Koshu*
no journal, ,
With the growing number of countries being interested in nuclear energy as a means for climate change and energy security concern, the importance of the compliance is again pointed out not only with the nuclear safety but also with the nuclear non-proliferation. Based on the abovementioned common acknowledgement, with the international collaboration, 3S initiative for the assurance of the nuclear non proliferation (safeguards), safety, and security, was proposed in Toyako summit G8 leaders declaration, and its importance was reaffirmed in LAquila summit G8 leaders declaration. In the paper, the result of study for the concrete measure of the 3S initiative will be introduced from the point of synergy effect on Fostering the 3S culture, Enforcement of the 3S package between software and hardware, Technology development for 3S, and Public acceptance activity for 3S.
Machida, Yuki*; Uehara, Masato*; Miura, Kenta*; Hanaizumi, Osamu*; Ishii, Yasuyuki; Sato, Takahiro; Takano, Katsuyoshi; Okubo, Takeru; Yamazaki, Akiyoshi; Inoue, Aichi; et al.
no journal, ,
m wavelength range fabricated by proton beam writingMiura, Kenta*; Machida, Yuki*; Uehara, Masato*; Hanaizumi, Osamu*; Ishii, Yasuyuki; Sato, Takahiro; Takano, Katsuyoshi; Okubo, Takeru; Yamazaki, Akiyoshi; Inoue, Aichi; et al.
no journal, ,
no abstracts in English
-wavelength range by using proton beam writing, 2Miura, Kenta*; Machida, Yuki*; Uehara, Masato*; Hanaizumi, Osamu*; Ishii, Yasuyuki; Sato, Takahiro; Takano, Katsuyoshi; Okubo, Takeru; Yamazaki, Akiyoshi; Inoue, Aichi; et al.
no journal, ,
no abstracts in English
Oki, Keiichi; Murayama, Yoji; Sasajima, Fumio; Izumo, Hironobu; Inoue, Takeshi; Unesaki, Hironobu*
no journal, ,
no abstracts in English
Izumo, Hironobu; Hanawa, Nobuhiro; Nagadomi, Hideki; Torii, Yoshiya; Inoue, Takeshi; Kawamura, Hiroshi
no journal, ,
The refurbishment works of JMTR had been completed as scheduled. The renewed JMTR operation is expected to start as soon as possible after check for earthquake effect etc, and will be utilized mainly for safety evaluation on LWRs and 
Mo production by without uranium target. JRR-3 has been used mainly for neutron beam experiments and radio isotope production. The number of LEU silicide spent fuels (SFs) stored at the reactor facilities in JAEA will increase in future by the JMTR restart. It will be one of the key issues to decrease the number of stored SFs for stable reactor operation. Consequently, it is thought that accomplishment of the FRRSNF acceptance program and its extension or alternative measures are very important.
Inoue, Takeshi; Suzuki, Mitsutoshi; Yamaguchi, Tomoki
no journal, ,
no abstracts in English
