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Uchida, Shinichi; Yuasa, Wataru; Hayashi, Akihiko; Inose, Shoichi; Ouchi, Yuichiro; Asakawa, Kenichi*; Uchikoshi, Yuta*
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 7 Pages, 2011/11
JAEA has developed a TMS which can monitor the movement of nuclear material convoys to make safe and proper transport of nuclear materials. The TMS mainly consists of the location information monitoring system to monitor the location of the convoys and the visual information monitoring system to survey around the convoys. The TMS can send information in real-time to the TCC located at the shipper site. The JAEA has operated the TMS for ground transportation of MOX fuels since 2005, and the JAEA solved visual control problems that were observed during the operational experience and upgraded the system by adding the automatic communication control system, etc. In the case of emergency during transport, the 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 reports the overview of the upgraded TMS and its effectiveness.
Nomi, Takayoshi; Nagatani, Taketeru; Ninagawa, Junichi; Nakajima, Shinji; Maruyama, Hajime; Asano, Takashi; Fujiwara, Shigeo
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2011/11
The IS approach for the JNC-1 site was implemented in August 2008, and this was the first experience in the world. This IS approach aimed not only to improve efficiency and effectiveness of safeguards but also to reduce burden of the plant operation by improvement of efficiency of the inspection activity. It was planned to review effectiveness of this new approach after three years from implementation. And JAEA also evaluated effects by application of the IS approach for two MOX fuel facilities in the JNC-1 site based on the three years experiences from the operator's view point. As the result of evaluation, it was confirmed that there were some difference of benefits by application of the IS approach depending on features of the facility, automation level of equipment and advance level of safeguards systems.
Shoji, Kaoru; Mukai, Yasunobu; Nakamura, Hironobu; Yoshimoto, Katsunobu; Hayashi, Hiroyuki*
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2011/11
In general, electro manometer system for volume measurement in high concentrated Pu, U solution is used. The measurement uncertainty of volume measurement should be kept within 0.36% in the nuclear material accountancy. Not only manometer censors are calibrated periodically, but also operator should maintain the integrity of entire volume measurement system. If clogging at a tip of dip-tube is occurred, it causes measurement bias. Therefore, we studied confirmation procedure of healthiness in the system during solution storage. As result, it is confirmed that following points are effective: (1) Confirmation of consistency in the Kumar's density formula by using actual Pu, U concentration, density and acidity determined by periodical sampling and high accuracy DA. In addition, Pu, U mass is maintained within the uncertainty from the previous sampling/DA result. (2) In order to confirm the integrity of differential pressure for density that may be impacted regarding the measurement bias by clogging, comparison between measured differential pressure for density and analyzed density with high accuracy is important. In the confirmation for density, correction method between different temperatures was established by the result of evaluation of temperature effect derived by Kumar's density formula.
Mukai, Yasunobu; Nakamura, Hironobu; Yoshimoto, Katsunobu; Tamura, Takayuki*; Iwamoto, Tomonori*
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2011/11
JNFL and JAEA are collaboratively developing an advanced solution monitoring and measurement system (ASMS) that is direct Pu measurement NDA system in the solution tank containing plutonium nitrate solution for the improvement of current safeguards subjects to be solved, and for next generation safeguards instrument. The target measurement uncertainty of ASMS is set less than 6% that is equivalent to detection level of partial defect at interim inventory verification by NDA. The ASMS detector was designed based on MCNPX calculation, and then manufactured. As an actual test, the detector was set in a process tank at Plutonium Conversion Development Facility, the calibration tests (known-alpha) for quantitative measurement was conducted. As a result, the total measurement uncertainty for Pu mass is about 3.4% except for the low liquid height region that is satisfied the target value. In addition, the monitoring capability of ASMS was confirmed.
Ishiyama, Koichi; Kimura, Takashi; Miura, Yasushi; Yamaguchi, Katsuhiro*; Kabuki, Toshihide*
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2011/11
To support inspections under an Integrated Safeguards regime into Tokai Reprocessing Plant (TRP), the IAEA suggested making use of Remote Monitoring (RM) capabilities to the inspection equipment (surveillance camera and NDA systems) installed in the spent fuel storage area at TRP. Since the spent fuel storage area in TRP did not have pre-prepared cabling infrastructure for data transmission, the option of wireless LAN was chosen over the telephone line due to its lower installation costs. Feasibility studies and tests were performed by TRP on communication and particularly on long-term continuous communication using wireless LAN equipment (AP: Access Point) and an external antenna for introducing wireless LAN technology to RM. As a result it was recognized that wireless LAN has enough ability to communicate for long periods of time and consequently the IAEA installed AP and an external antenna to each inspection equipment and the wireless LAN technology was applied for RM.
Sagara, Hiroshi; Inoue, Naoko; Kawakubo, Yoko; Watahiki, Masaru
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2011/11
The Generation IV (GEN IV) Nuclear Energy Systems International Forum (GIF) Proliferation Resistance and Physical Protection Working Group (PRPP WG) was established in December 2002 in order to develop the PR&PP evaluation methodology for GEN IV nuclear energy systems. In the final report of "PR&PP Evaluation; Example Sodium Fast Reactor (ESFR) Full System Case Study," issued in October 2009, the demonstration study of PR&PP evaluation with the qualitative approach are summarized using ESFR with four scenario threats. The present paper reviews and analyzes some results of the ESFR case study, and identifies the challenges and direction for the PR&PP evaluation methodology with quantitative approach.
Kureta, Masatoshi; Soyama, Kazuhiko; Seya, Michio; Ozu, Akira; Haruyama, Mitsuo; Nakamura, Tatsuya; To, Kentaro; Sakasai, Kaoru
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2011/11
Alternative techniques to neutron detection by He-3 for safeguards and nuclear security systems are necessary to be developed since He-3 gas shortage is serious. With support of Japanese government (MEXT), we have started the project of ZnS ceramic scintillation neutron detectors for non-destructive assay (NDA) 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 in our scintillator by using Monte Carlo code.
Wakabayashi, Shuji; Naito, Aisaku
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 6 Pages, 2011/11
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security of the Japan Atomic Energy Agency will set up exercise facilities for training people of nuclear power emerging countries in Asia and other regions involved in physical protection (PP) including government officers in charge of nuclear security policy or nuclear security regulation, planning and management staff of PP facilities of operating companies, design professionals for PP facilities, and security personnel responsible for PP. In order to provide effective and practical exercises, we will set up the training facilities with basic measures and equipment typical of those used in actual PP facilities, e.g., protective fences, sensors, and cameras. This paper introduces an outline of the facilities.
Seya, Michio; Wakabayashi, Shuji; Naoi, Yosuke; Okubo, Michiaki; Senzaki, Masao
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-32-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2011/11
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN, hereafter) of Japan Atomic Energy Agency (JAEA) has development programs of cutting-edge technologies for measurement and detection of nuclear materials for nuclear safeguards and security, under the sponsorship of Japanese government (MEXT: Ministry of Education, Culture, Sports, Science and Technology). ISCN started development programs of the following technologies this year. (1) NRF (Nuclear Resonance Fluorescence) NDA technology using laser Compton scattering (LCS) 
-rays (2) 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 that is to be developed by LANL (Los Alamos National Laboratory) using very sophisticated neutron measurement technologies, under JAEA/USDOE cooperation agreement. This presentation shows the above programs of ISCN.