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Kitade, Yuta; Tamai, Hiroshi; Tazaki, Makiko; Shimizu, Ryo; Kimura, Takashi; Nakanishi, Hiroaki; Suda, Kazunori
Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2018/11
Regional Safeguards is considered as one of the measures for strengthening IAEA safeguards and its concept is recognized at NPT Review Conference and also NSG Guidelines amended in 2011. This Study examines the elements for the proper establishment of Regional Safeguards.
Ozu, Akira; Maeda, Makoto; Komeda, Masao; Furutaka, Kazuyoshi; Toh, Yosuke
Nihon Kaku Busshitsu Kanri Gakkai Dai-38-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2018/04
no abstracts in English
Ozu, Akira; Komeda, Masao; Kureta, Masatoshi; Nakatsuka, Yoshiaki; Nakashima, Shinichi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 59(12), p.700 - 704, 2017/12
no abstracts in English
Ozu, Akira; Komeda, Masao; Kureta, Masatoshi; Zaima, Naoki; Nakatsuka, Yoshiaki; Nakashima, Shinichi
Nihon Genshiryoku Gakkai Wabun Rombunshi, 15(2), p.115 - 127, 2016/06
A non-destructive assay system using the fast neutron direct interrogation method has been developed to put its method into practical use for the determination of uranium (
U) mass contained in actual uranium-contaminated waste drums. The method is capable of measuring the fissile mass in a drum by counting the number of fission neutrons resulting from nuclear fission reactions between the fissile materials contained in a drum and thermal neutrons generated by 14 MeV fast neutrons irradiated from outside the drum. The performance test employing simulated metal waste drums demonstrated that a natural uranium mass of as low as 10 g could be detected within an error of 
20% regardless of the distribution of uranium samples in the drum. A demonstration test employing actual waste drums could determine the uranium mass by using a newly developed correction method for deriving the fissile mass in a drum. It has been proved by the experimental validation tests that the assay system equipped with the correction method is very useful for the accountancy of the waste drums.
He Alternative Neutron Detectors (ASAS), 1; Design and fabrication of ASAS detectorOzu, Akira; Tobita, Hiroshi; Kureta, Masatoshi; Tanigawa, Masafumi; Mukai, Yasunobu; Nakamichi, Hideo; Nakamura, Hironobu; Kurita, Tsutomu; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-36-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/12
Against the background of the serious shortage of He gas, the Japan Atomic Energy Agency (JAEA) has newly developed an alternative ZnS ceramic scintillation neutron detector for the safeguards, with the support of the government (MEXT). A demonstrator of plutonium inventory sample assay system (ASAS) has been also developed as an alternative HLNCC (High Level Neutron Coincidence Counter). The results from numerical simulations using Monte-Carlo code MCNPX showed that the fundamental performances of ASAS equipped with the 24 alternative neutron detectors, such as neutron detection efficiency and die-away time, equal to or higher than those of conventional HLNCC could be obtained. Here we present the inner mechanical structure of ASAS, together with the results of the simulating design.
Nakamura, Hironobu; Mukai, Yasunobu; Kurita, Tsutomu
Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03
The Distributed Source-Term Analysis (DSTA) technique has been used in a variety of safeguards applications to determine location and quantity of material contained within large sample volumes. By applying this method, JAEA developed and applied two different neutron measurement techniques in order to improve own MC&A. The first advanced technique is a Glove Box Cleanout Assistance Tool (BCAT). It is used by operator during cleanout just before PIT to increase recovered material, to decrease unmeasured inventory, and to perform the cleanout activity effectively. The BCAT is being introduced to the actual cleanout since 2011. The second advanced technique is a dynamic cross-talk correction (DCTC) method. The DCTC can obtain actual doubles signal cross-talk between multiple gloveboxes. In order to assay Pu amount in the holdup correctly, we implemented an improved HBAS system using DCTC. Two advanced holdup measurement technologies provide appropriate safety and safeguards environment to conduct nuclear cycle with operator and inspector.
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ceramic scintillator detectorsNakamura, Hironobu; Ozu, Akira; Kobayashi, Nozomi*; Mukai, Yasunobu; Sakasai, Kaoru; Nakamura, Tatsuya; Soyama, Kazuhiko; Kureta, Masatoshi; Kurita, Tsutomu; Seya, Michio
Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07
To establish an alternative technique of He-3 neutron detector that is used for nuclear material accountancy and safeguards, we have started an R&D project to develop a new type of neutron detector (Pu NDA system) using ZnS/BO ceramic scintillator with support of Japanese government. The design of the alternative system (ASAS: Alternative Sample Assay System) is basically referenced from INVS (INVentory Sample assay system) which is passive neutron assay system of plutonium and has total 18 He-3 tubes (about 42% of counting efficiency), and the small amount of Pu in the MOX powder or Pu nitrate solution in a vial can be measured. In order to establish the technology and performance after the fabrication of the new detector progresses, we are planning to conduct demonstration activity in the early 2015 experimentally. The demonstration activity implements the confirmation of reproducibility about sample positioning, optimization of detector parameters, counting statistical uncertainty, stability (temperature and 
-ray change) check and figure of merit (FOM) using check source and actual MOX powder. In addition to that, performance comparison between current INVS and the ASAS are also conducted. In this paper, we present some analytical study results using a Monte-Carlo simulation code (MCNP), entire ASAS design and demonstration plan to prove technology and performance.
Senzaki, Masao; Naoi, Yosuke; Kuribayashi, Toshihiro; Hamada, Kazuko; Okumura, Yukiko
Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07
JAEA has supported to HRD of mainly Asian countries in the field of SGs and SSAC, and works closely with governmental organizations in Japan, and with the IAEA, the U.S. DOE, EC, the flame work of FNCA, APSN. This paper presents the efforts, contributions and future challenges of JAEA to HRD regarding SGs and SSAC, through international cooperation, which have been taking place for around 20 years.
Nishi, Masataka; Yamanishi, Toshihiko; Hayashi, Takumi; DEMO Plant Design Team
Fusion Engineering and Design, 81(1-7), p.745 - 751, 2006/02
Times Cited Count：31 Percentile：88.1(Nuclear Science & Technology)The fusion DEMO plant is under designing at JAERI as a fusion machine following ITER, and it is designed with long-term steady operation and tritium breeding blanket in which more tritium is produced than consumption. Therefore, proper tritium accountancy control concept should be discussed and developed for its safety and operation. From the viewpoint of regulation for the radioisotopes, at first, it will be suitable to divide facilities of the fusion DEMO plant into three accountancy control blocks, that is, (1) the contaminated waste management facility, (2) the long term tritium storage facility, and (3) the fuel processing plant. In each block, tritium amount of receipt and delivery should be carefully accounted. The fuel processing plant involves tritium production in the blanket, therefore proper accounting method for produced tritium should be established. Furthermore, dynamic accountancy is indispensable to the fuel processing plant to monitor tritium inventory distribution for safety and optimum system control in addition to the accountancy under regulation.
Fukada, Satoshi*; Hayashi, Takumi
Nihon Genshiryoku Gakkai-Shi, 47(9), p.623 - 629, 2005/09
no abstracts in English
Ono, Akio*
Kaku Busshitsu Kanri Senta Nyusu, 33(9), p.12 - 15, 2004/09
no abstracts in English
Nishi, Masataka; Yamanishi, Toshihiko; Hayashi, Takumi; Yamada, Masayuki; Suzuki, Takumi
Purazuma, Kaku Yugo Gakkai-Shi, 79(10), p.1078 - 1084, 2003/10
Research and development work of fuel processing technology and tritium safe-handling technology for fusion reactors has been performed at the Tritium Process Laboratory (TPL) of JAERI. The TPL is the first facility in Japan permitted to handle tritium of more than 1g (about 0.36PBq), and its operation itself is also important for the development of fusion reactor facility in the viewpoint of tritium control. Various experiments have been performed at the TPL safely since 1988 controlling 22PBq of tritium as the maximum observing regulations. In addition to the regulatory control, detailed independent control in the TPL was planned and was established through its 15-year safe-operation. For future fusion fuel facility where kilograms of tritium will be handled, method of tritium accounting has been researched and some new techniques have been developed at the TPL. The results of the TPL operation and of the research activity in it, which contributed the completion of the engineering design of the ITER, are summarized in this paper together with the subjects to be reserched.
Obata, Takashi; Numata, Kazuyoshi; Namiki, Shinji; Suzuki, Tsuneo*; Yamauchi, Takahiro*
Dai-24-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, p.65 - 70, 2003/00
For the nuclear material accounting system, the mainframe computer had been used in Japan Atomic Energy Research Institute (JAERI). For the purpose of more flexible use and easy operation, the PC base accounting system has been developed since 1999, and operation started from October, 2002. This system consists of the server with the database software and the client PC with original application software. The functions of this system are the input and edit of data, the creation of inspection correspondence data, and creation of a report to the states. Furthermore, it is also possible to create the Web application which used accounting data on a user level by using the programming language. Now, this system is being specialized in JAERI, but it is during a plan to develop as a system which can be also used at other institutions and organization. In the paper, the outline and operating situation of the nuclear material accounting system of JAERI are presented.
Yamanishi, Toshihiko
Purazuma, Kaku Yugo Gakkai-Shi, 78(12), p.1295 - 1300, 2002/12
no abstracts in English
Hayashi, Takumi; Suzuki, Takumi; Yamada, Masayuki; Nishi, Masataka
Fusion Technology, 34(3), p.510 - 514, 1998/11
no abstracts in English
Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Tadokoro, Takahiro*; Nakamura, H.*; Ito, Takeshi*; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; et al.
Fusion Energy 1998, 3, p.1069 - 1072, 1998/10
no abstracts in English
Yamanishi, Toshihiko; Nishikawa, Masabumi*; *
Purazuma, Kaku Yugo Gakkai-Shi, 73(12), p.1326 - 1332, 1997/12
no abstracts in English
Mineo, Hideaki; ; Miyauchi, Masakatsu; Okazaki, Shuji; *; Takeshita, Isao; S.-T.Hsue*
JAERI-Tech 96-033, 36 Pages, 1996/07
no abstracts in English
Mineo, Hideaki; Yanagisawa, Hiroshi; Tonoike, Kotaro; ; Hirose, Hideyuki; Murakami, Kiyonobu; *; Dojiri, Shigeru; Takeshita, Isao
JAERI-Tech 96-027, 209 Pages, 1996/06
no abstracts in English
Yanagisawa, Hiroshi; Mineo, Hideaki; Dojiri, Shigeru; Takeshita, Isao
Dai-16-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, 0, p.117 - 124, 1996/00
no abstracts in English
