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Kobayashi, Naoki
Enerugi Rebyu, 43(11), p.18 - 21, 2023/10
no abstracts in English
Ac for Targeted Alpha Therapy (TAT) using the experimental fast reactor JoyoMaeda, Shigetaka; Kitatsuji, Yoshihiro
Enerugi Rebyu, 42(10), p.19 - 22, 2022/09
Ac-225 is attracting attention as an alpha-emitting medical radioisotope. Since its demand is expected to increase, domestic production of Ac-225 is required from the viewpoint of Japan's medical research and economic security. To establish the technical bases for the Ac-225 production, JAEA has evaluated the radioactivity that can be produced in the experimental fast reactor Joyo and designed the concept that upgrades the existing facilities for transporting the irradiated target from Joyo to a neighboring PIE facility rapidly. Efficient Actinium-225 Separation from Ra-226 irradiated in a fast reactor was studied. Ba and La were used as alternatives to Ra and Ac, respectively. By using DGA resin as an adsorbent, it can be expected that Ra and impurities generated by irradiation will be removed and Ac will be isolated. This study has revealed that Joyo can sufficiently produce Ac-225 as a raw material for pharmaceuticals.
Mo/
Tc by PWRNasu, Takuya*; Fujita, Yoshitaka
Enerugi Rebyu, 42(10), p.15 - 18, 2022/09
no abstracts in English
Tazaki, Makiko; Kimura, Takashi
Enerugi Rebyu, 42(9), p.62 - 63, 2022/08
no abstracts in English
Sagayama, Yutaka
Enerugi Rebyu, 42(7), p.38 - 42, 2022/06
An overview of the world's past developments in fast reactor development and the history of Japan-U.S. cooperation in this area, as well as an explanation of the possibilities and expectations for future Japan-U.S. cooperation.
Koito, Yuko
Enerugi Rebyu, 42(4), P. 24, 2022/03
no abstracts in English
Sagayama, Yutaka
Enerugi Rebyu, 41(8), P. 42, 2021/07
GIF was launched in 2001 to develop of GEN-4 reactors through international cooperation. The Policy Group chair rotates among the US, France, and Japan, and Hideki Kamide, Advisor to MEXT of the JAEA, is currently the Chair. The development goals and reactor concept have been summarized as follows, Establishment of the development goals of economic, security, sustainability and proliferation resistance. Selection of reactor types of GFR, SCWR, SFR, VHTR, LFR and MSR. The major achievement is establishment of the safety design criterion, which will become an international standard for SFR and has been developed under the leadership of Japan. In the future, it is important to establish a new mechanism in the demonstration stage and to develop design standards and criteria for maintenance and servicing for international standards for GEN-4 reactors.
Sato, Ikken
Enerugi Rebyu, 41(4), p.17 - 19, 2021/03
The accident progression behavior leading to core melting and after the start of the core melting at Fukushima Daiichi Nuclear Power Station Unit 3 were estimated based on data analysis mainly based on plant data such as pressure and knowledge obtained from existing analysis evaluations. In Unit 3, it is estimated that it took several hours for fuel debris to fall on to the pedestal floor, and it is likely that it was cooled by liquid coolant presented on the containment floor.
Yamashita, Takuya
Enerugi Rebyu, 41(4), p.14 - 16, 2021/03
no abstracts in English
Maruyama, Yu
Enerugi Rebyu, 41(4), p.20 - 24, 2021/03
no abstracts in English
Mochiji, Toshiro; Senzaki, Masao*; Tamai, Hiroshi; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Enerugi Rebyu, 40(8), p.56 - 57, 2020/07
Strict application of IAEA safeguards and nuclear security should be implemented for Japan's full-scale nuclear fuel cycle. Based on the knowledge and experience of research and development in the nuclear fuel cycle, nuclear material management, the effective and efficient promotion of new technologies should be promoted with scientific and demonstrative measures to strengthen the world's nuclear non-proliferation and nuclear security. Development or sophistication of new technologies, human resource development, and reinforcement of the international framework are future challenge in the international community.
Mochiji, Toshiro; Senzaki, Masao*; Tamai, Hiroshi; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Enerugi Rebyu, 40(7), p.58 - 59, 2020/06
Japan have promoted the peaceful use of plutonium with the nuclear non-proliferation commitment based on IAEA safeguards agreement and Japan-US nuclear cooperation agreement, as well as ensuring transparency of the policy that Japan has no plutonium without purpose of use. In promoting the nuclear fuel cycle, adherence to those measures and maintaining plutonium utilization by means of plutonium-thermal, and a fast reactor cycle to achieve large-scale and long-term energy supply and environmental improvement, therefore, further research and development is essential.
Mochiji, Toshiro; Senzaki, Masao*; Tamai, Hiroshi; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Enerugi Rebyu, 40(6), p.58 - 59, 2020/05
In order to promote the peaceful use of nuclear energy, it is important not only to ensure safety but also to ensure nuclear non-proliferation and nuclear security. Japan has contributed to the international community through strengthening nuclear non-proliferation and nuclear security capabilities with technical and human resource development. However, in the wake of the accident at the Fukushima Daiichi Nuclear Power Plant in 2011, Japan's nuclear power plants have not restarted or plutonium use has not progressed smoothly. Concerns have been shown. Towards appropriate steps of Japan's nuclear fuel cycle policy, such concerns are examined and future efforts are summarized.
Yoshida, Kazuo
Enerugi Rebyu, 40(4), p.19 - 20, 2020/03
The probabilistic Risk Assessment has been recognized to have important role for the safety enhancement of nuclear facilities in Japan. Efforts of developing methodologies and basic data for risk assessment are undertaken actively for NFFs (Nuclear Fuel Facilities) in Japan. The standard for risk assessment for NFFs is consist of simplified assessment detailed one based on the concept of Graded Approach depending on the risk levels of their facilities. Risk-informed application is useful for activities of enhancing safety measures by the licensee rather than in regulatory decision making because of lower risk level of NFFs. The risk assessment has been also required in the periodic safety self-review by the licensees. The correct understanding of significance of risk assessment for safety management of facilities is essential for the risk-informed application. It is key event to apply the risk assessment in the safety self-review and new regulatory inspection system.
Otsuka, Satoshi; Kaito, Takeji
Enerugi Rebyu, 39(1), p.44 - 46, 2019/01
For performance improvement of next-generation nuclear system such as fast reactor, it has been expected to develop advanced material resistant to severe in-reactor environment (i.e. high-dose neutron irradiation at high-temperature). Japan Atomic Energy Agency (JAEA) has been developing Oxide Dispersion Strengthened (ODS) ferritic steel for long life fuel cladding tube of fast reactor. Application of ODS ferritic steel to fast reactor fuel can extend the fuel life time twice or more as long as the fuel with conventional cladding tube (i.e. modified SUS316), thus reducing fuel exchange frequency and fuel cost. It can be adaptable to high-temperature plant operation, which is favorable for improvement of power generation efficiency. This paper interprets the development of ODS ferritic steel cladding tube for sodium-cooled fast reactor, which has been led by JAEA for dozens of years.
Suda, Kazunori
Enerugi Rebyu, 38(10), p.38 - 41, 2018/09
no abstracts in English
Shobu, Nobuhiro
Enerugi Rebyu, 37(10), p.21 - 22, 2017/10
After the Fukushima-Daiichi Nuclear Power Plant Accident, Japan Atomic Energy Agency (JAEA) has been carrying out research and development activities towards the environmental restoration of Fukushima. This paper describes the following representative activities in Fukushima Environmental Safety Center of JAEA, such as the development of environmental monitoring and mapping technologies, the long-term assessment of transport of radio-cesium in the environment of Fukushima, and the technology development for advancing decontamination and volume reduction technologies.
Arakawa, Ryoki
Enerugi Rebyu, 37(10), p.17 - 18, 2017/10
The Naraha Remote Technology Development Center was established in Naraha-town, Fukushima in 2013. This report introduces facilities, research and development, use of facilities.
Yoshikawa, Hideki
Enerugi Rebyu, 37(10), p.13 - 14, 2017/10
We introduce the R&D activities of Japan Atomic Energy Agency immediately after the accident at Fukushima Daiichi Nuclear Power Station and some facilities established in Fukushima Prefecture.
Miyachi, Shigehiko
Enerugi Rebyu, 37(10), p.19 - 20, 2017/09
The JAEA is currently constructing the Okuma Analysis and Research Center near the TEPCO's Fukushima Daiichi Nuclear Power Station site. These are consists of three buildings; Administrative building and hot laboratories; Laboratory-1 and Laboratory-2. Radioactive analysis in hot laboratories will provide the data needed to establish the strategy and methodology for treatment and disposal of radioactive rubbles, and for the removal methods of fuel debris in the reactors.