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Yuasa, Wataru; Uchida, Shinichi; Hayashi, Akihiko; Inose, Shoichi; Ouchi, Yuichiro
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 6 Pages, 2011/07
The Japan Atomic Energy Agency (JAEA) has developed a transport monitoring system (TMS), which tracks the movement of nuclear material convoys in real time, and which is consistent with the physical protection requirements for transport of Category 1 nuclear materials. The TMS has been used for land transport of MOX fuels since 2005. JAEA solved some problems that were observed during operational experience and upgraded the system by adding the following features. In the case of emergency during transport, the upgraded TMS can send much more detailed visual information of the accident site to the TCC, which is useful for planning and executing an effective response. This paper presents the features of the TMS and the results obtained from operational experiences.
Ninagawa, Junichi; Asano, Takashi; Nagatani, Taketeru; Nakajima, Shinji; Nomi, Takayoshi; Fujiwara, Shigeo
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 8 Pages, 2011/07
Japan was transferred to the Integrated Safeguards (IS) scheme in September 2004. The IS approach for JNC-1 site, including PFPF, was developed to improve the efficiency of safeguards while maintaining the effectiveness and has been implemented since August 2008. JAEA has evaluated the validity of the IS approach for PFPF based on the historical performance over about three-year period. As the result of evaluation, JAEA confirmed the improvement of efficiency of inspection activities and the reduction of the impact of inspection activities on plant operation. On the other hand, the IAEA has also evaluated the validity of IS approach and considered to modify based on the result of its evaluation. In order to maintain or improve the validity of the IS approach, JAEA thinks that it will be necessary to work very closely and honestly with the inspectorate to address this modification process.
Nakamura, Hironobu; Mukai, Yasunobu; Yoshimoto, Katsunobu; Tamura, Takayuki*; Iwamoto, Tomonori*
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 9 Pages, 2011/07
JNFL and JAEA are collaboratively developing an Advanced Solution Measurement and monitoring System (ASMS) that is direct Pu measurement NDA system in the large scale solution tank containing purified plutonium nitrate for the improvement of current safeguards subjects to be solved, and for next generation safeguards instrument (NGSI). In this report, we summarize the first step results of ASMS development regarding quantitative measurement methodology. In order to establish quantitative measurement, accurate MCNPX modeling and calculations are very important and necessary. After calibration exercise implementation, we successfully obtained calibration constants (slope), and the total measurement uncertainty was about 3% for 
Pu effective mass for 2 hours measurement except for the low level region. In addition, the image of safeguards by design and collaboration of SMMS are also presented.
Kureta, Masatoshi; Soyama, Kazuhiko; Seya, Michio; Ozu, Akira; Haruyama, Mitsuo; Nakamura, Tatsuya; To, Kentaro; Sakasai, Kaoru
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 10 Pages, 2011/07
Alternative techniques to neutron detection by 
He for nuclear security and safeguards systems are necessary to be developed since He shortage is serious. With support of Japanese government (MEXT), we have started an development project of ZnS ceramic scintillation neutron detectors for non-destructive assay of Pu in Fresh MOX fuel and other types of nuclear material for a use of safeguards verification. Here we present master plan of the project and feasibility study on neutron absorption probability between neutron and Lithium/Boron in our scintillator by using Monte Carlo code, MVP.
Hoffheins, B.; Miyaji, Noriko; Asano, Takashi; Nagatani, Taketeru; Ishiyama, Koichi; Kimura, Takashi; Kodani, Yoshiki
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 10 Pages, 2011/07
Following Japan's conclusion of the Additional Protocol and the IAEA's broader conclusion regarding the peaceful nature of Japan's nuclear activities, the Japan government and facility operators have worked with the IAEA to apply integrated safeguards to increase inspection efficiency and to ensure verification correctness and completeness. These safeguards approaches rely heavily on the implementation of advanced technologies such as unattended surveillance and non-destructive assay measurement, automated nuclear material accounting, solution monitoring and remote monitoring. These technologies have enabled random interim inspections; they have also reduced the level of effort required for nuclear material accounting and inspection activities. A more comprehensive understanding of the impact of advanced technologies on operation and inspection processes would be useful for developing methodologies to support better system design and evaluation of existing systems.
Seya, Michio; Wakabayashi, Shuji; Senzaki, Masao; Okubo, Michiaki; Naoi, Yosuke
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 10 Pages, 2011/07
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of JAEA established in December, 2010 has development programs of cutting-edge technologies for measurement and detection of nuclear materials, in addition to its functions of "assistance for human resources development and capacity buildings", "institutional infrastructure development and technical support" and "international cooperation and collaboration" under the sponsorship of MEXT. ISCN started development programs of "NRF (Nuclear Resonance Fluorescence) NDA technology using laser Compton scattering (LCS) 
-rays", "Alternative to He neutron detection technology using inorganic solid scintillator". ISCN is also going to conduct a demonstration test of a spent fuel Pu-NDA system using very sophisticated neutron measurement technologies, that are to be developed by LANL after conclusion of a JAEA/US.DOE cooperation agreement. This paper presents the development programs of ISCN.
Kuno, Yusuke; Oda, Takuji*; Tanaka, Satoru*; Fukasawa, Tetsuo*; Tanabe, Tomoyuki*; Tamai, Hiroshi; Horio, Kenta*; Hamasaki, Manabu*; Shinohara, Nobuo*; Ikeda, Yuta*
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 10 Pages, 2011/07
The substance and implication of PR from the viewpoints of risk evaluation on nuclear proliferation was studied in this paper. As an example, ten next-generation reprocessing technology candidates were evaluated with GIF PR and PP methodology to find degree of relative difference in PR from the presently available technology - PUREX. PR effectiveness in proliferation risk was also assessed and it was found that the effectiveness of PR measures is subject to the status of each nation.
Sakurai, Satoshi; Watahiki, Masaru; Suzuki, Mitsutoshi; Kuno, Yusuke
Proceedings of INMM 52nd Annual Meeting (CD-ROM), 6 Pages, 2011/07
The national statement made by the Japan Government at 2010 Nuclear Security Summit at Washington D.C., U.S.A. was to develop its nuclear forensics detection and analysis technologies in a three-year period and to share them with the international community to contribute to strengthening the nuclear security regime. The Japan Atomic Energy Agency, JAEA, is the organization that possesses analytical capabilities with the potential to fulfill this nuclear forensics mission, since JAEA has been developing a wide range of analytical techniques for nuclear material samples from large size ones to trace level ones of environmental sampling. For this reason, JAEA starts R&D on nuclear forensics technology from JFY 2011. In the presentation reported will be JAEA's outline of R&D to establish nuclear forensics analytical capabilities including international cooperation. The summary of International Workshop on Nuclear Forensics on 5-6 October 2010 at Tokai, Japan will be also reported.
Ouchi, Yuichiro; Tadokoro, Noboru; Kitamura, Takafumi; Yoshida, Sachimasa; Kurita, Ichiro
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The Japan Atomic Energy Agency (JAEA) is planning to procure uranium and plutonium mixed oxide (MOX) powder necessary for the prototype fast breeder reactor MONJU and experimental reactor JOYO from Rokkasho Reprocessing Plant (RRP), which is operated by the Japan Nuclear Fuel Limited (JNFL). When both reactors operate as planned, an annual quantity of MOX is estimated at two tons (600 kg of fissile Pu). JAEA has developed a sea transport system including a transport package, shipping containers, vehicles, a ship, and ports, etc., to safely and securely transport large amounts of MOX powder compliant with physical protection measures for Category I materials. This paper describes development of the transport package and shipping container, and will outline the sea transport plan.