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Takano, Kazuya; Oki, Shigeo; Ozawa, Takayuki; Yamano, Hidemasa; Kubo, Shigenobu; Ogura, Masashi*; Yamada, Yumi*; Koyama, Kazuya*; Kurita, Koichi*; Costes, L.*; et al.
EPJ Nuclear Sciences & Technologies (Internet), 8, p.35_1 - 35_9, 2022/12
The France and Japan teams have carried out collaborative works to have common technical views regarding a sodium-cooled fast reactor concept. Japan has studied the feasibility of an enhanced high burnup low-void effect (CFV) core and fuel using oxide dispersion-strengthened steel cladding in ASTRID 600. Regarding passive shutdown capabilities, Japan team has performed a preliminary numerical analysis for ASTRID 600 using a complementary safety device, called a self-actuated shutdown system (SASS), one of the safety approaches of Japan. The mitigation measures of ASTRID 600 against a severe accident, such as a core catcher, molten corium discharge assembly, and the sodium void reactivity features of the CFV core, are promising to achieve in-vessel retention for both countries. The common design concept based on ASTRID 600 is feasible to demonstrate the SFR core and safety technologies for both countries.
Kan, Taro*; Ogura, Masashi*; Hibi, Koki*; Oki, Shigeo; Maeda, Seiichiro; Maruyama, Shuhei; Ohgama, Kazuya
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04
C and 
O nuclei by low-energy proton beamsAkagi, Takashi*; Yagi, Masashi*; Yamashita, Tomohiro*; Murakami, Masao*; Yamakawa, Yoshiyuki*; Kitamura, Keiji*; Ogura, Koichi; Kondo, Kiminori; Kawanishi, Shunichi*
Radiation Measurements, 59, p.262 - 269, 2013/12
Times Cited Count：16 Percentile：76.68(Nuclear Science & Technology)In proton therapy, positron emitters are induced from C andO nuclei by protons on the beam path in the patient. Many studies for monitoring positron emitters with beam-induced PET technique have been performed by various groups to verify the proton beam range and the dose in the patient for quality assurance. The aim of this study was to develop a method for measuring the production cross sections of positron emitters using standard equipment for proton therapy. The time-activity curve was then obtained with a high-sensitivity PET scanner to extract the number of positron emitters produced in the target. The production cross sections for four reaction channels: O(p,pn)
O, O(p,3p3n)
C, O(p,2p2n)
N, and C(p,pn)C were then measured. The cross sections for the O(p,pn)O reaction channel were consistent with data of previous experiments within the uncertainties, while those of C(p,pn)C were generally lower than data of previous experiments.
Okubo, Tsutomu; Oki, Shigeo; Ogura, Masashi*; Okubo, Yoshiyuki*; Kotake, Shoji*
Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), p.479 - 486, 2011/05
A conceptual design study and related R&D on a commercial-base large-scale Japan Sodium-cooled Fast Reactor (JSFR) have been carried out in the framework of the Fast Reactor Cycle Technology development (FaCT) project. As a next generation plant, JSFR adopts a number of innovative technologies in order to achieve economic competitiveness, enhanced reliability and safety. This paper describes the current results of the ongoing conceptual design study on the JSFR core. The most important point in the core design is to achieve a high core average burn-up around 150 GWd/t, assuming the ODS steel utilization as the cladding material. Another design target for the breeding ratio is intended to have some flexibility and is set at from around 1.0 to 1.2 under the design philosophy of the compatible fuel assembly among them. Also, the fuel composition is considered to have some variation range based on the wide variety of the spent fuel composition expected to be treated during the LWR to FBR transition period. The core design study performed in the FaCT project has clarified the feasibility of the JSFR core concept, which is based on the high internal conversion ratio type core using a large fuel rod diameter around 10 mm and satisfies a number of design targets and requirements including ones mentioned above.
Okubo, Tsutomu; Oki, Shigeo; Ogura, Masashi*; Okubo, Yoshiyuki*
no journal, ,
Aiming at realization of the demonstration reactor for the Japan Sodium-cooled Fast Reactor (JSFR) around 2025, the conceptual design study has been performed on 750 or 500 MWe core. This presentation gives the present status. In the conceptual design of the demonstration reactor, design targets, requirements and conditions are set as the same as those of the 1500 MWe commercial reactor. The design of the fuel assembly and fuel pin are also the same as in the commercial reactor, based on the consideration to demonstrate them. Fuel composition covers MA bearing fuel supposed in the commercial reactor and the highly decontaminated U-Pu fuel considering the fuel cycle circumstances around 2025. The study has shown that the core concept satisfying given design condition will be possible, as well as the range of core performance change based on the fuel composition range.
Ogura, Masashi*; Moriwaki, Hiroyuki*; Okubo, Yoshiyuki*; Oki, Shigeo; Okubo, Tsutomu
no journal, ,
no abstracts in English
Koga, Yasuhiko*; Kaira, Kyoichi*; Yamada, Masanobu*; Dobashi, Kunio*; Matsuzaki, Shinichi*; Hisada, Takeshi*; Koka, Masashi; Yamada, Naoto; Sato, Takahiro; Yokoyama, Akihito; et al.
no journal, ,
Tsuboi, Toru*; Moriwaki, Hiroyuki*; Ogura, Masashi*; Hibi, Koki*; Maeda, Seiichiro; Ohgama, Kazuya; Chikazawa, Yoshitaka; Oki, Shigeo
no journal, ,
no abstracts in English
Moriwaki, Hiroyuki*; Ogura, Masashi*; Kan, Taro*; Oki, Shigeo
no journal, ,
no abstracts in English
Soga, Akira*; Oki, Shigeo; Naganuma, Masayuki; Ogura, Masashi*
no journal, ,
no abstracts in English
