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Koito, Yuko
Kaku Naki Jidai O Dezainsuru; Kokusai Seiji, Kakufukakusan, Kokusaiho Kara Mita Genjitsuteki Purosesu, p.128 - 136, 2024/12
This paper is part of the research output of the JSPS KAKENHI project "Nuclear Disarmament without Undermining Security" (21H00688). The project comprehensively assessed nuclear weapons from multiple perspectives, including political, military, international humanitarian law, science and technology, and examined policies and institutions for an age without nuclear weapons, with the aim of following up on the proposal for substantial progress in nuclear disarmament made by the Council of Eminent Persons of the Ministry of Foreign Affairs (29 March 2018). This paper reviews the debates on the process of establishing the NPT, divided into the period before and after the decision to extend it indefinitely, and, while focusing on the consensus approach that has become the operational method, assesses the role it has played in shaping the order around nuclear weapons and tries to rethink the value of the NPT. In addition, the paper explores the possibility that Japan's advanced reactors could contribute to the WMD zone concept.
Uwaba, Tomoyuki
JNC TN9420 2000-005, 28 Pages, 2000/03
JNC-TN9420-2000-005.pdf:0.94MB
In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO
, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.
; Daidai, Misao; ; Obata, Shinichi; Seki, Masayuki; ;
PNC TN8410 97-045, 21 Pages, 1997/03
None
Tsuji, Hirokazu; ; Tsukada, Takashi; Nakajima, Hajime
JAERI-M 91-136, 42 Pages, 1991/09
no abstracts in English
; Ogawa, Yutaka; Nakajima, Hajime
Tetsu To Hagane, 74(2), p.380 - 387, 1988/02
no abstracts in English
Shindo, Masami; W.J.Quadakkers*; H.Schuster*
J. Nucl. Mater., 140, p.94 - 105, 1986/00
Times Cited Count：19 Percentile：85.39(Materials Science, Multidisciplinary)no abstracts in English
Shindo, Masami; ; Kondo, Tatsuo
JAERI-M 83-108, 17 Pages, 1983/07
no abstracts in English
;
JAERI-M 4438, 14 Pages, 1971/05
no abstracts in English
Noguchi, Hiroki; Ishii, Katsunori; Ono, Masato; Sato, Hiroyuki; Sakaba, Nariaki; Kato, Yukitaka*
no journal, ,
Achieving decarbonization of iron industry, large amount of hydrogen is required for a hydrogen reduction ironmaking as a reduction material. In addition, high temperature heat must be supplied from the outside in order to prevent a shaft furnace temperature from decreasing due to an endothermic reaction of hydrogen reduction. Therefore, hydrogen heated up to high temperature by electricity or burning hydrogen is supplied to the shaft furnace. High temperature gas-cooled reactor (HTGR) can produce a large amount of hydrogen due to high temperature heat supply capability. Additionally high temperature generated from HTGR can be used for heating hydrogen. This presentation will introduce the high temperature hydrogen supply system using HTGR for contributing to decarbonization of ironmaking.
Sakaba, Nariaki; Noguchi, Hiroki; Sato, Hiroyuki; Ohashi, Hirofumi
no journal, ,
The high-temperature gas-cooled reactors has inherent safety characteristics and a capability to produce high temperature heat. This large amount of heat is suitable for various heat applications such as production of hydrogen, steam as well as generation of electricity. HTGR will be located in close proximity to steelmaking and petrochemical complexes based on the inherent safety and will supply hydrogen, electricity, and steam to the complexes for contributing the carbon neutrality in hard-to-abate sector. Japanese government has formulated Basic Policy for GX Implementation which clearly shows a roadmap for development of HTGR demonstration reactor aiming to enter operation in the late 2030s. Based on the policy, JAEA has planned the world's first demonstration test of hydrogen production using the direct heat from the HTTR. This presentation will introduce the unique features of HTGR and the current status of hydrogen production technology development utilising the HTGR in Japan.
Kamide, Hideki
no journal, ,
no abstracts in English
