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Tazaki, Makiko; Kimura, Takashi; Shimizu, Ryo; Tamai, Hiroshi; Nakatani, Takayoshi; Suda, Kazunori
JAEA-Review 2022-056, 54 Pages, 2023/01
JAEA-Review-2022-056.pdf:1.86MB
As part of the "Research on Factor Analysis and Technical Processes for Achieving Denuclearization" South Africa's nuclear development and denuclearization cases were investigated then analyzed from seven denuclearization factors namely (1) motivation for nuclear development, (2) internal and external situations at the time of denuclearization decision, (3) progress of nuclear development, (4) effects of sanctions, (5) incentives for denuclearization, (6) international framework for denuclearization, (7) denuclearization and verification methods. At the same time, characteristics of its denuclearization and lessons learned from the denuclearization were also analyzed. South Africa shifted its nuclear activities from research and development of "peaceful nuclear detonation" in the 1970s to developing "limited nuclear deterrence" and finally to manufacturing "transportable nuclear weapons" in the late 1980s. By then, it had completed producing six nuclear explosive devices using highly enriched uranium. However, in 1989, along with the abolition of the apartheid policy, South Africa decided denuclearization and dismantled its nuclear explosive devices and related facilities. Upon completion of dismantlement, it joined the Treaty on the Non- Proliferation of Nuclear Weapons and concluded a Comprehensive Safeguards Agreement (CSA) with the International Atomic Energy Agency (IAEA). The South Africa has remained one of the rare countries that has continued to the peaceful use nuclear energy, and its voluntary denuclearization is considered as a good example of denuclearization in the future.
Tazaki, Makiko; Kimura, Takashi; Shimizu, Ryo; Tamai, Hiroshi; Nakatani, Takayoshi; Suda, Kazunori
JAEA-Review 2022-020, 82 Pages, 2022/09
JAEA-Review-2022-020.pdf:2.14MB
As part of the "Research on Factor Analysis and Technical Processes for Achieving Denuclearization" started in 2018, comprehensive survey of nuclear development and denuclearization of Iraq was conducted, together with analysis of the characteristics and lessons learned from the denuclearization. Iraq's clandestine nuclear weapon related activities were initially focused on plutonium production, but it then switched its focus on producing highly enriched uranium, and built various facilities, including electromagnetic isotope separation (EMIS) and centrifuge uranium enrichment facilities. Denuclearization of Iraq began with the defeat in the 1991 Gulf War, which forced Iraq to accept United Nations Security Council Resolution 687 (1991) that year. The Resolution set out a framework for destruction, removal, or rendering harmless of Iraq's weapons of mass destruction (WMD) programs. Within the framework, the International Atomic Energy Agency (IAEA), with the support and cooperation of the newly established United Nations Special Commission (UNSCOM), had verified Iraq's past nuclear activities and denuclearization. Characteristics of Iraq's denuclearization include that 1) Iraq had no choice but to accept denuclearization, 2) IAEA was empowered to implement detectable inspection measures and methods, which later came to fruition as the IAEA Safeguards Agreement Additional Protocol (AP), 3) economic sanctions for the purpose of promoting denuclearization of Iraq were not very successful, and 4) denuclearization of Iraq and subsequent Iraq war, together with collapse of the Hussein regime, has affected the denuclearization of Libya, North Korea and Iraq. Furthermore, the lessons learned from the denuclearization are 1) the need for universalization of AP, and necessities for 2) economic sanctions that are suitable for the original purposes without being abused, 3) the need for diplomatic efforts including denuclearization frameworks and measures with a clear roadmap
Suda, Kazunori; Kimura, Takashi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(6), p.334 - 338, 2020/06
Amid growing concerns about potential nuclear terrorism, discussions have been conducted internationally to strengthen the nuclear security. In this series, we will explain the efforts of the international community to strengthen the nuclear security and the reflection of the treaty for the nuclear security and the IAEA nuclear security recommendations in the domestic laws.
Tazaki, Makiko; Shimizu, Ryo; Kimura, Takashi; Tamai, Hiroshi; Nakatani, Takayoshi; Suda, Kazunori
Nihon Kaku Busshitsu Kanri Gakkai Dai-40-Kai Nenji Taikai Puroshidhingusushu, p.93 - 96, 2019/11
Iraq, defeated by the Gulf War, had to accept denuclearization under UN Security Council Resolution (UNSCR) 687, but did not immediately and accurately report all its past nuclear activities to the IAEA. IAEA, as an internationally authorized nuclear inspection and verification organization to Iraqi denuclearization by the UNSCR 687, gradually revealed existence and the whole picture of Iraqi clandestine nuclear activities and verified destruction of weapon related facilities and equipment as well as removal of nuclear materials outside Iraq. Analyzing Iraq's characteristics of denuclearization could serve as a good reference for not only preventing nuclear weapons development but also considering their denuclearization in current and future states.
Tazaki, Makiko; Kimura, Takashi; Shimizu, Ryo; Tamai, Hiroshi; Nakatani, Takayoshi; Suda, Kazunori
Nihon Kaku Busshitsu Kanri Gakkai Dai-40-Kai Nenji Taikai Puroshidhingusushu, p.81 - 84, 2019/11
South Africa had developed, manufactured, and possessed nuclear weapons, but later dismantled them all together with related facilities and equipment. After joining Treaty on the Non-Proliferation of Nuclear Weapons as a non-nuclear weapon state and concluding a Comprehensive Safeguards Agreement with the Atomic Energy Agency (IAEA), it started peaceful use of nuclear energy. In that sense, South Africa's denuclearization is one of good examples of past denuclearization in the world, although the South Africa's specific policy of apartheid had been deeply connected with its nuclear weapons development and denuclearization. Analysing South Africa's motivations for nuclear weapons development, incentives for denuclearization, and characteristics of its denuclearization could serve as a good reference for not only preventing nuclear weapons development but also considering their denuclearization in current and future states.
Nakanishi, Hiroaki; Kimura, Takashi; Shimizu, Ryo; Kitade, Yuta; Tazaki, Makiko; Tamai, Hiroshi; Suda, Kazunori
Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2018/11
To extract the possible requirements for the Broader Conclusion (BC) drawn by the IAEA in the Member States, this study is to conduct the comparative analysis of the tendencies on the Member States from which the BC has been drawn and those from which the BC has not been drawn yet.
Kono, Yuko; Ayame, Junko; Yoshida, Tomoo*; Ikuta, Yuko; Kawase, Keiichi; Yamashita, Kiyonobu
JAEA-Review 2018-007, 36 Pages, 2018/06
JAEA-Review-2018-007.pdf:6.72MB
English translation of the material used at "Meeting to Answer Questions on Radiation" was made. "Meeting to Answer Questions on Radiation" was planned, just after the TEPCO Fukushima Daiichi Nuclear Power Plant Accident, by Japan Atomic Energy Agency (JAEA) with the purpose of providing comprehensive knowledge of radiation to the public. A total of 220 meetings was carried out from July, 2011 to February, 2013 mainly in Fukushima prefecture. Since the material used in the meetings contains many charts and is easy to understand, it has drawn attention of the International Atomic Energy Agency (IAEA) who has in recent years actively supported outreach activities to disseminate knowledge on nuclear and radiation. At one of the IAEA meetings in May, 2017, Asian Network for Education in Nuclear Technology (ANENT), it was requested to make it for the usage of all. Providing IAEA and the member states with the English translation of the material will be a meaningful contribution sharing the outreach activity experiences in Japan.
Tazaki, Makiko; Suda, Kazunori
Nihon Genshiryoku Gakkai-Shi ATOMO, 58(10), p.594 - 598, 2016/10
The 4th (and the last) Nuclear Security Summit was held in Washington D.C. in 31 March and 1 April 2016. Brief reviews of pas 3 nuclear security summits, including the 4th one, Japan contribution to the summits, future challenges of post nuclear security summits and Japan role are described in the paper.
Ohira, Hiroaki; Doda, Norihiro; Kamide, Hideki; Iwasaki, Takashi*; Minami, Masaki*
Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.2585 - 2592, 2015/05
IAEA's Coordinated Research Project on Benchmark Analyses of Shutdown Heat Removal Test (SHRT) performed at the Experimental Breeder Reactor-II (EBR-II) has been carried out since 2012. The benchmark specifications were provided by the Argonne National Laboratory (ANL) and the model development for thermal-hydraulics codes and/or plant dynamics codes has been conducted by participating organizations. The experimental data were also provided by the ANL after the calculations have been performed as the blind simulation. JAEA participated in this benchmark analyses, and the plant dynamics analysis code; Super-COPD was applied to the SHRT-17 simulation. The calculated inlet temperature of the high pressure plenum agreed well with the test data in all simulation time. Although the Z-pipe inlet temperature and the IHX intermediate outlet temperature had some discrepancy in the first 400 sec. caused by larger mass flow rate of the primary pump and the perfect mixing model of upper plenum, these temperatures and the flow rate agreed well with the measured data after 400 sec. Hence it was concluded the present analytical model could predict the natural circulation in good accuracy.
; ; *;
JNC TN9400 2000-043, 23 Pages, 2000/03
ln the feasibility study on commercialized fast breeder reactor (FBR) cycle systems conducted in JNC, it is required for candidate FBR plants that the level of safety should be enhanced so as to assure: (1)Comparative or superior safety level to that of light water reactors (LWRs), and (2)releaf of the public from anxiety about potential nuclear hazard. Adopting Passive safety characteristics is one of the measures. To attain the above safety objective, we considered implication of the basic safety principles for nuclear power plants that were created by the international nuclear safety advisory group of IAEA. The way to relieve from the anxiety was also taken into account. Then a definite safety objective was set from the standpoint of prevention of core disruptive accident (CDA). Furthermore, as a definite safety goal relating to reactor coresafety, elimination of re-criticality issues under CDA was set by considering characteristics of FBR in comparison with those of LWR. To examine measures for elimination of re-criticality issues, we developed a quick method to estimate possibility of re-criticality under CDA, by drawing a map about criticality characteristics under CDA in various degraded cores. Then hopeful measures were proposed for elimination of re-criticality issues in sodium-cooled FBR with mixed-oxide fuel. Molten fuel discharge behavior of their measures was preliminarily analyzed. We concluded that discharge capability of "a subassembly with an internal duct" was effective, and that "partial removal of axial blanket" was also effective as one of the measures though it has small effect on core performance.
Ikeda, Takao*; Yoshida, Hideji*; Miki, Takahito*
JNC TJ8400 2000-046, 264 Pages, 2000/02
JNC-TJ8400-2000-046.pdf:6.73MB
This report contains discussions about methodology for the selection of parameter values, stochastic approach for the biosphere assessment and biosphere modelling for marine discharge case are described. Regarding the methodology for the selection of parameter values, important aspects for the data selection were discussed, and data selection protocol was developed. Regarding the stochastic approach for the biosphere assessment, it is confirmed that Straightforward Monte Carlo Method and Latin Hypercube Sampling Method are the most adequate based on a literature survey. Then stochastic assessment by using biosphere model that was developed in the second progress report was carried out to check the sensitivity of parameter values. Finally, availability of several kind of assessment models for marine discharge case were discussed. It was confirmed that Multiple Compartment Model was the most applicable. Assessment using Multiple Compartment Model was carried out. The results were compared with those derived by numerical model. As a result, the difference between two models were small enough.
Ikeda, Takao*; Yoshida, Hideji*; Miki, Takahito*
JNC TJ8400 2000-045, 134 Pages, 2000/02
JNC-TJ8400-2000-045.pdf:4.12MB
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Yoshida, Hiroko*; Yasuda, Hiroshi*; Takahashi, Fumiaki; Dobashi, Ryuta*; Hattori, Takatoshi*
no journal, ,
The Japan Health Physics Society (JHPS) is a member of the International Radiation Protection Association (IRPA). Many researchers and technicians of radiation protection join JHPS in Japan. The international affairs committee in JHPS holds a session to introduce recent trends and information about radiation protection over the world in annual meeting. In the 51st Meeting, Dr. Yoshida (Tohoku Univ.) will talk about the recent activities of task groups in IRPA. Dr. Yasuda will explain radiation protection in aviation given by ICRP Publication 132. Dr. Dobashi will introduce recent discussions on the safety standards by IAEA. Takahashi (JAEA) will explain Occupational Intakes of Radionuclides (OIR) given by ICRP Publications 130, 134 and 137.
Saito, Kimiaki
no journal, ,
no abstracts in English
Manabe, Kentaro
no journal, ,
The Radiation Safety Standards Committee (RASSC) of the International Atomic Energy Agency (IAEA) is the committee responsible for radiation safety and radiological protection documents in nuclear and radiological applications. The RASSC meetings in 2022 were held in June and November to review and approve the draft guideline for application of the concept for exemption and to develop a new documents for radiological protection and safety in existing exposure situations. The RASSC also discussed the publication policy of safety documents was also initiated. The presentation will summarize these developments for this year.
