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Matsuba, Kenichi; Shinohara, Masanori; Toyooka, Junichi; Inaba, Yoshitomo; Sumita, Junya
Enerugi, Shigen, 43(4), p.218 - 223, 2022/07
In the global trend toward decarbonization, Japan has a policy to pursue all options, including nuclear power, to achieve carbon neutrality by 2050. In order to meet the public requirements for nuclear power, it is important to promote the development of advanced reactors, including the Small Modular Reactor (SMR), as one of the promising options. This article describes the domestic and international trends of SMR development, introduces the activities of Japan Atomic Energy Agency (JAEA) for the development of advanced reactors including SMRs, and concludes with the future prospect for the introduction of advanced reactor including SMRs in Japan.
Kamide, Hideki
Karyoku Genshiryoku Hatsuden, 71(11), p.638 - 648, 2020/11
Development status of next generation reactors is outlined mainly for sodium cooled fast reactor developed in Japan Atomic Energy Agency (JAEA). Development strategy in Japan, status of the advanced reactor developments including SMR over the world, and also results of research and development in JAEA are explained.
Mineo, Hideaki; Nishihara, Tetsuo; Ohashi, Hirofumi; Goto, Minoru; Sato, Hiroyuki; Takegami, Hiroaki
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(9), p.504 - 508, 2020/09
High-Temperature Gas-cooled Reactor (HTGR) is one of thermal neutron reactor-type that employs helium gas coolant and graphite moderator. It has excellent inherent safety and can supply high-temperature heat which can be used not only for electric power generation but also for a wide range of application such as hydrogen production. Therefore, HTGR is expected to be an effective technology for reducing greenhouse gases in Japan as well as overseas. In this paper, we will introduce the forefront of technological development that JAEA is working toward the realization of an HTGR system consisting of a high temperature gas reactor and heat utilization facilities such as gas-turbine power generation and hydrogen production.
Maeda, Seiichiro
no journal, ,
The uranium-plutonium mixed oxide (MOX) fuel bearing several percent minor actinides is adopted as the fast reactor fuel to reduce the high level radioactive waste volume and its toxicities. Their physical properties such as melting points and thermal conductivities are investigated symmetrically. It is getting clear that the effect of MA bearing is not so significant. The MOX fuel pins including up to 5% of Am were irradiated in Joyo to confirm their irradiation performance. Some types of irradiation experiments using MA-MOX fuels are planned after Joyo restart. The obtained data will contribute to develop fuel pin performance codes for MA-MOX fuels. SmART (Small Amount of Reuse Fuel Test) cycle program is in progress to demonstrate MA recycles starting from FR spent fuels. Furthermore, long life cladding with ODS steel is under development to enhance the transmutation efficiency of MA in one cycle. Thus, R&Ds in FR systems advances steadily to solve the waste issue.
Shibata, Taiju
no journal, ,
For the HTGR and FR, plans and status toward SMR development and deployment in Japan is presented at the technical working group meeting in IAEA.
Shibata, Taiju; Ohno, Shuji; Ohashi, Hirofumi
no journal, ,
no abstracts in English
Hashimoto, Naoyuki*; Isobe, Shigehito*; Oka, Hiroshi*; Hayashi, Shigenari*; Ueda, Mikito*; Yamashita, Shinichiro; Itakura, Mitsuhiro; Tsuru, Tomohito
no journal, ,
Owing to the reduced defects, low cost, and high efficiency, the additive manufacturing (AM) technique has attracted increasingly attention and has been applied in high-entropy alloys (HEAs) in recent years. For the purpose of creating new materials which show no radiation damage or prompt recovery of radiation damage, we launched a new program in which additive-manufactured HEAs are target materials and their fundamental properties are under investigation. In this presentation, we reported the some of new test results which are conducted in the program.
Sakaba, Nariaki
no journal, ,
The Japan Atomic Energy Agency (JAEA) has been developing High Temperature Gas-cooled Reactor technology since 1960s. In December 2020, Japanese Government clearly stated "Green Growth Strategy Through Achieving Carbon Neutrality in 2050" that noted a commitment to the milestone and developing and implementing significant efforts in various sectors for achieving carbon neutrality around 2050. High Temperature Gas-cooled Reactor (HTGR) is expected to play one of a dominant roles to reduce carbon generated from non-electric fields by utilizing heat and hydrogen produced by HTGR. To produce hydrogen from HTGR, it is necessary to establish a connecting technology including safety case between HTGR and hydrogen production process. The milestone for hydrogen production by HTTR (High Temperature Engineering Test Reactor) is given by the Green Growth Strategy. JAEA is now planning its R&D towards generation of hydrogen using heat from HTTR by 2030. This paper describes current status of HTGR R&D in JAEA.
Nakamura, Hirofumi
no journal, ,
This paper reports SMR's current status in the world and development status of advanced reactors in Japan.
Yamamoto, Tomohiko; Yan, X.; Shimada, Takahiro*; Motegi, Haruki*; Kai, Satoru*; Otani, Akihito*
no journal, ,
no abstracts in English
Shibata, Taiju
no journal, ,
no abstracts in English
Hori, Masato
no journal, ,
no abstracts in English
Kamide, Hideki
no journal, ,
Developments of advanced reactors, especially SMR, are highlighted in the world, e.g., US, Canada, and UK. In Japan recently Strategic Working Group for fast reactor development had a meeting and discussions about revision of Strategic Roadmap of fast reactor development issued in 2018 December. In relation to these topics, current status of advanced reactor developments in Japan and oversea countries is reported.
Fujii, Shoma*; Yamano, Hidemasa; Hayafune, Hiroki; Ohno, Shuji
no journal, ,
The application of thermal energy storage (TES) in power generation systems is an attractive option that can convert variable renewable energy, or stable heat sources, such as reactor heat from small modular reactors (SMRs), into flexible power output. A molten salt-based TES charging reactor heat from SMRs was considered as a case study of Power to Heat to Power system, and was feasibly investigated by annual simulation. A price-following model was developed to simulate heat charging and discharging operation, in which reactor heat is stably charged and its heat is discharged during periods of high electricity spot prices. Although the annual output is slightly lower than the SMR stand-alone operation due to the low-load operation of the steam turbine, the total revenue increases due to the improvement of the electricity spot price at the time of power selling.
