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Fukui, Yasuhito
Nihon Genshiryoku Gakkai-Shi ATOMO
, 65(9), p.564 - 567, 2023/09
This article explains that how the international law prevents armed attacks to nuclear power plant based on the lex lata basis. Four points are raised, in other words, first, how the current international law prohibit armed attacks to the nuclear power plant. Second, the current international law can prevent the armed attacks effectively. Third, if the law lacks the effectiveness, what kind of framework or response are necessary. Fourth, if these legal frameworks are applied to the nuclear power plants in Japan, how these will be accommodated are explained.
Hamaguchi, Takumi; Yamada, Junya; Komatsuzaki, Naoya*; Hatakeyama, Takumi; Seya, Natsumi; Muto, Yasunobu; Miyauchi, Hideaki; Hashimoto, Makoto
JAEA-Technology 2022-038, 65 Pages, 2023/03
JAEA-Technology-2022-038.pdf:4.3MB
New regulatory requirements were developed taking into account the lessons-learnt from the accident at Fukushima Daiichi Nuclear Power Station on March 2011. The new regulatory standards required that monitoring posts should be diversified in transmission systems and equipped with backup power supply equipment for design basis accidents. In this report, we look back on the history of monitoring posts in Oarai Research and Development Institute, explained the application for the permission of reactor installment license, application for approval of the design and construction method, pre-use operator's inspection and improvement design of monitoring posts. This report also includes about inspection based on act on special measures concerning nuclear emergency preparedness and the installation of KURAMA-II, which was carried out in conjunction with the improvement of monitoring post for new regulatory standards. As an appendix, application document for approval of the design and construction method are included.
Hamamoto, Shimpei; Shimizu, Atsushi; Inoi, Hiroyuki; Tochio, Daisuke; Homma, Fumitaka; Sawahata, Hiroaki; Sekita, Kenji; Watanabe, Shuji; Furusawa, Takayuki; Iigaki, Kazuhiko; et al.
Nuclear Engineering and Design, 388, p.111642_1 - 111642_11, 2022/03
Times Cited Count：2 Percentile：53.91(Nuclear Science & Technology)Following the Fukushima Daiichi Nuclear Power Plant accident in 2011, the Japan Atomic Energy Agency adapted High-Temperature engineering Test Reactor (HTTR) to meet the new regulatory requirements that began in December 2013. The safety and seismic classifications of the existing structures, systems, and components were discussed to reflect insights regarding High Temperature Gas-cooled Reactors (HTGRs) that were acquired through various HTTR safety tests. Structures, systems, and components that are subject to protection have been defined, and countermeasures to manage internal and external hazards that affect safety functions have been strengthened. Additionally, measures are in place to control accidents that may cause large amounts of radioactive material to be released, as a beyond design based accident. The Nuclear Regulatory Commission rigorously and appropriately reviewed this approach for compliance with the new regulatory requirements. After nine amendments, the application to modify the HTTR's installation license that was submitted in November 2014 was approved in June 2020. This response shows that facilities can reasonably be designed to meet the enhanced regulatory requirements, if they reflect the characteristics of HTGRs. We believe that we have established a reference for future development of HTGR.
Yoshinaka, Kazuyuki; Suzuki, Masafumi*
Gijutsushi, (659), p.4 - 7, 2021/11
The regulatory standards for nuclear facilities were revised, reflecting the lessons learned from Fukushima-Daiichi NPS accident. Many requirements for safety measures, in case there are natural disaster or severe accidents, are added for nuclear fuel cycle facilities. Aiming achievement of the nuclear fuel cycle, various safety measures for conforming to new regulatory standard and improving, have been taken at Rokkasho reprocessing plant.
Tamai, Hiroshi
Nihon Genshiryoku Gakkai-Shi ATOMO, 63(9), p.677 - 678, 2021/09
The International Atomic Energy Agency, IAEA, has issued a technical report on national approaches to the interface between nuclear safety and nuclear security, which is essential for strengthening through mutual complementation. The report aims to provide Member States with insights on good practices, each of which is important in coordinating the interface. Those are states' experiences in (i) legal and regulatory framework, (ii) nuclear installations, (iii) radioactive sources and associated facilities and activities, (iv) management systems and nuclear safety and nuclear security culture, (v) emergency preparedness and response, and common issues in cross-cutting field.
Ozawa, Masaaki*; Amaya, Masaki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(4), p.185 - 200, 2020/12
no abstracts in English
Manabe, Kentaro
Hoken Butsuri, 52(1), p.35 - 38, 2017/03
Health Physics Seminar 2016 was held at the Osaka Science & Technology Center with 150 participants on Nov. 2, 2016. The seminar was consisted of three themes: "current movements of protection and operational quantities", "future risk communications inspired by the Fukushima accident", and "effects of low dose radiation on human". Eminent specialists gave lectures about the news in their particular fields and suggestions to problems. In addition, a special lecture entitled "recent movements of issues about Act on Prevention of Radiation Hazards due to Radioisotopes, etc." was given by a specialist of the Secretariat of Nuclear Regulation Authority. This lecture introduced the examples of trouble incidents, reports on implementation status of inspections, results of Integrated Regulatory Review Service by IAEA, etc. There were vigorous questioning and discussions through the seminar. This document reported the summary of the lectures and discussions, and the author's impressions of the seminar.
Seya, Michio; Hajima, Ryoichi*; Kureta, Masatoshi
Dai-37-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu (CD-ROM), 10 Pages, 2017/02
Large size freight cargo containers are the most volunurable items from nuclear security points of view because of their large volume and weight of cargo inside for hiding heavily shielded objects. For strengthning nuclear security, secure detection of NMs in heavily shielded objects, and safe handling (dismatlement) of detected / suspicious objects for taking out of NMs, are essential. These require the following things, (1) Introduction of secure detection system of NMs, (2) Inspection of deteiled and interior structures of detected objects, (3) Rough chracterization of NMs (for nuclear bomb or RDD etc.) / Confirmation of existence of explosives etc.. By using information obtained by interior inspections, safe dismantlement of objects and taking NMs out are possible. In this papaer, we propose a combined system of X-ray scanning system with NRF-based NDD system using monochromatic 
-ray beam not only as a secure detection system of NMs but also interior inspection system (covering (1) and (2)). Also we propose active neutron NDA system using a D-T source for interior inspection of NM part (covering (3)).
Uesaka, Mitsuru*; Mineo, Hideaki
Nihon Genshiryoku Gakkai-Shi ATOMO, 58(8), p.468 - 473, 2016/08
All the research reactors and critical assemblies (hereinafter RRCAs) in Japan are stopped in order to fulfil the new regulatory requirements, which were reinforced after the accident at the Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station. These RRCAs have played important roles in the areas of human resource development, academic research, medical and industrial application of nuclear technology. Prolonged stoppage of RRCAs affects adversely those activities. Atomic Energy Society of Japan set up a group to discuss this issue. The group has shown a proposal that the roles of the RRCAs, which are indispensable facilities to nuclear human resource development, should be placed positively in the energy policy and the science and technology policy of the country.
Holland, M. K.*; Cordaro, J. V.*; Morales-Arteaga, M. E.*; Yamamoto, Masahiko; Kuno, Takehiko; Surugaya, Naoki
Proceedings of INMM 57th Annual Meeting (Internet), 10 Pages, 2016/07
Since 2007, the laboratory at the Japan Atomic Energy Agency (JAEA) and Savannah River National Laboratory (SRNL) have collaborated on a new mission to apply controlled-potential coulometry as a primary method for characterizating plutonium master solutions. Measurement results are being used to prepare traceable and certifiable large-size dry (LSD) spike standards for safeguards measurements by isotope dilution mass spectrometry. The collaboration activities performed by JAEA and SRNL were authorized and funded under the JAEA & United States NNSA/DOE Permanent Coordinating Group. This report will chronicle the collaboration activities of JAEA and SRNL, and provide the detail on the periodic coulometer component calibration, the coulometric plutonium measures and measure practices, including the uncertainty propagation for the most recent plutonium master solution used for LSD Spike preparation.
Yamamoto, Masahiko; Shirozu, Hidetomo; Mori, Eito; Surugaya, Naoki
JAEA-Technology 2016-009, 58 Pages, 2016/05
JAEA-Technology-2016-009.pdf:3.95MB
The panels of glove box installed at Tokai Reprocessing Plant have been deteriorated and transparencies have been decreased due to the long-term use. Therefore, the panels have been replaced from the view point of preventive maintenance. In the new regulation formulated since the Fukushima Daiichi Nuclear Power Plant accident, it is demanded that the glove box consists of incombustible or inflammable materials. In this replacement, new panels have been manufactured with polycarbonate which satisfied the UL94 V-0 incombustible class. The inside of glove box has been contaminated with radioactive materials. Thus, the contamination and operator's exposure have been investigated. Then radiation protection equipment have been selected. Also, it is necessary to maintain the glove box enclosure during the replacement. The replacement has been conducted by covering the opening parts with vinyl sheets. The enclosure function has been verified by the inspection of the new panels and glove box.
Shimomura, Yusuke; Hanari, Akira*; Sato, Isamu*; Kitamura, Ryoichi
JAEA-Technology 2015-062, 47 Pages, 2016/03
JAEA-Technology-2015-062.pdf:1.85MB
In response to new standards for regulating waste management facilities, it was carried out impact assessment of forest fires on the waste management facilities existed in Oarai Research and Development Center of Japan Atomic Energy Agency. At first, a fire spread scenario of forest fires was assumed. The intensity of forest fires was evaluated from field surveys, forest fire evaluation models and so on. As models of forest fire intensity evaluation, Rothermel Model and Canadian Forest Fire Behavior Prediction (FBP) System were used. Impact assessment of radiant heat to the facilities was carried out, and temperature change of outer walls for the assumed forest fires was estimated. The outer wall temperature of facilities was estimated around 160
C at the maximum, it was revealed that it doesn't reach allowable temperature limit. Consequently, it doesn't influence the strength of concrete. In addition, a probability of fire breach was estimated to be about 20%. This report illustrates an example of evaluation of forest fires for the new regulatory standards through impact assessment of the forest fires on the waste management facilities.
Arai, Masaji; Wada, Shigeru; Murayama, Yoji
Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.403 - 408, 2016/03
In response to the accident at Fukushima Daiichi NPS, the new safety standards for research and test reactor facilities came into force on December 18, 2013. The evaluation of natural disasters and prevention of spread of accidents beyond design basis mainly were enhanced in the standards. We have completed the necessary checks and assessments, and submitted an application for reviewing if JRR-3 complies with the new standards to the Nuclear Regulation Authority on September 26, 2014.
Suyama, Kenya; Hirao, Yoshihiro*; Sakamoto, Hiroki*
Nihon Genshiryoku Gakkai-Shi ATOMO, 57(12), p.787 - 791, 2015/12
In the measures to pursue the world's highest level of safety of the nuclear installations, it is required to maintain the technical revel of the safety analyses codes as higher as possible. Because many of them were introduced from US at the initial phase of the nuclear energy introduction, development of computer codes and relevant tools in Japan have not been continued successfully. Accordingly, many old US-oriented code has been used. This manuscript presents the current status and the problems of computer codes for nuclear safety evaluation, and a scheme to introduce the computer codes of Japan, which in-cooperate the latest knowledge, in the scene of nuclear safety regulation and practical purpose.
Tamaki, Hitoshi
Tekisuto "Kakunenryo Saikuru" (Internet), 3 Pages, 2014/12
Revised regulatory rule of nuclear facilities in Japan defines "Serious accident", and require accident measures for them to not only power reactors, but also fuel reprocessing and fabrication facilities. This document describes the basis of accident measures for Serious accident at nuclear fuel reprocessing and fabrication facilities, as a part of "Text of Nuclear Fuel Cycle".
Watanabe, Norio
JAERI-Review 2004-015, 144 Pages, 2004/07
JAERI-Review-2004-015.pdf:25.58MB
In March 6, 2002, significant degradation to the reactor vessel head material adjacent to a control rod drive nozzle was discovered at a U. S. pressurized water reactor (PWR), Davis Besse. Based on the documents issued by the U.S. Nuclear Regulatory Commission (USNRC) and the licensee, this report provides a brief description on circumstances related to discovery of the reactor vessel head degradation, and describes the degraded condition and causes, the USNRC's responses to this event and so on. In attachments, given are the contents of the generic communications (Bulletins, Generic Letters and Information Notices) issued by the USNRC for the events involving boric acid corrosion and degradation of reactor coolant pressure boundary components and the summary of the investigation reports issued by the USNRC's lessons-learned task force.
Yanagihara, Satoshi
Dekomisshoningu Giho, (28), p.2 - 9, 2003/10
Decommissioning of nuclear facilities has been actively progressed in the major member countries participating to OECD/NEA. The NEA has recognized necessity of studying various issues related to decommissioning nuclear facilities and it has made an approach to solve the issues from various ways. In the cooperative program for decommissioning (CPD), information on decommissioning projects has been exchanged among the member countries. In the working party on decommissioning and dismantling (WPDD), recent issues have been studied in terms of regulation, implementation of decommissioning projects and research and development on technologies. Decommissioning cost and regulatory practices were also studies and the reports were published, which will be useful for understanding the present issues on decommissioning in the world. The NEA's activity on decommissioning will be valuable for us to implement decommissioning projects in safe and economical manner in Japan. This report deals with the recent NEA activities on decommissioning.
Hada, Kazuhiko
Nihon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, (25), p.2 - 3, 2002/10
no abstracts in English
Watanabe, Hiroshi
Genshiryoku eye, 48(9), p.70 - 71, 2002/09
no abstracts in English
Oishi, Tetsuya
Hoken Butsuri, 36(1), p.93 - 94, 2001/03
no abstracts in English
