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Nagatsuka, Kentaro; Noguchi, Hiroki; Nagasumi, Satoru; Nomoto, Yasunobu; Shimizu, Atsushi; Sato, Hiroyuki; Nishihara, Tetsuo; Sakaba, Nariaki
Nuclear Engineering and Design, 425, p.113338_1 - 113338_11, 2024/08
Times Cited Count：4 Percentile：91.70(Nuclear Science & Technology)HTGR has a potential to contribute to decarbonization of hard-to-abate industries by supplying a large amount of hydrogen and high temperature heat or steam without carbon dioxide emission. JAEA has been conducting R&Ds for HTGR technologies with High Temperature Engineering Test Reactor (HTTR). This paper shows that HTTR's tests including the loss of core cooing test as a joint the OECD/NEA international research project and a HTTR heat application test plan which demonstrate hydrogen production by coupling the HTTR with a hydrogen production test facility. Additionally, aiming for operation start from the latter half of 2030s, the basic design of the HTGR demonstration reactor has been shown. The Japan's HTGR technology capabilities established by the HTTR project will be fully utilized for the construction of HTGR demonstration reactor.
Ishii, Katsunori; Morita, Keisuke; Noguchi, Hiroki; Aoki, Takeshi; Mizuta, Naoki; Hasegawa, Takeshi; Nagatsuka, Kentaro; Nomoto, Yasunobu; Shimizu, Atsushi; Iigaki, Kazuhiko; et al.
Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 4 Pages, 2023/09
Nagatsuka, Kentaro*; Sato, Hiroyuki; Imai, Yoshiyuki; Yan, X.
no journal, ,
In order to improve economics of High Temperature gas cooled reactors (HTGR) by means of increasing core power density, HTGR's fuel assembly in which converged coolant flow is adapted is proposed to achieve reduction of fuel temperature during normal operation and heat transfer flow characteristics is estimated with numerical simulation. As a result of estimation, a perspective of fuel temperature reduction is obtained without numbers of fuel enrichment which are required in the conventional method.
Noguchi, Hiroki; Ishii, Katsunori; Morita, Keisuke; Mizuta, Naoki; Nagatsuka, Kentaro; Hasegawa, Takeshi; Aoki, Takeshi; Takahashi, Hideo; Kurahayashi, Kaoru; Yasuda, Takanori; et al.
no journal, ,
High temperature gas-cooled reactor (HTGR) can produce a large amount of hydrogen due to high temperature heat supply capability. JAEA has started an HTTR heat application test project, which aims world's first hydrogen production demonstration utilizing direct nuclear heat. A hydrogen production facility will be newly constructed and will be connected to the HTTR. The objective of the test is to establish a safety design for coupling HTGR and hydrogen production facility through the licensing by the Nuclear Regulation Authority in Japan and demonstrate performance of components required for coupling between HTGR and hydrogen production facility. JAEA is currently conducting hydrogen production facility design as well as safety design and analysis of the HTTR. This presentation will show the overview and current status of the HTTR heat application test.
Nagatsuka, Kentaro; Mizuta, Naoki; Morita, Keisuke; Yoshino, Masaki; Hasegawa, Takeshi; Ishii, Katsunori; Aoki, Takeshi; Ono, Masato; Takahashi, Hideo; Kurahayashi, Kaoru; et al.
no journal, ,
no abstracts in English
