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Fujiwara, Yusuke; Nakajima, Kunihiro; Urabe, Kohei; Nagatsuka, Kentaro; Asano, Kazuhito; Shimizu, Atsushi; Noguchi, Hiroki; Sato, Hiroyuki; Ohashi, Hirofumi; Sumita, Junya; et al.
JAEA-Technology 2026-001, 43 Pages, 2026/05
JAEA-Technology-2026-001.pdf:2.93MB
High Temperature Gas-cooled Reactors (HTGRs) have excellent safety features and can supply high-temperature heat without emitting carbon dioxide, and therefore are expected to stably produce large amounts of hydrogen to contribute carbon neutrality by 2050. The pertinent material for the "Basic Policy for GX Realization" shows the development process for the HTGR demonstrator with the goal of starting operation in the 2030s. Meanwhile, to achieve net-zero, the UK government has started the Advanced Module Reactor (AMR) Research, development and demonstration (RD&D) programme with the aim of starting operations of the HTGR demonstrator in the early 2030s. Against this background, with the aim of early deployment of HTGR technology, Japan Atomic Energy Agency (JAEA), in collaboration with the United Kingdom National Nuclear Laboratory (UKNNL), aims to demonstrate Japanese HTGR technology outside Japan and reflect the development of HTGR demonstrator in the UK to Japan. This document summarizes the results of a market survey of HTGR products and surveys of industrial infrastructure in the UK, the environment and social conditions of Hartlepool, a candidate construction site, with the aim of contributing to the design study of the HTGR demonstrator in the UK (UKJ-HTR).
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：25 Percentile：97.89(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
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*; 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.
Fujiwara, Yusuke; Matsui, Yutaka; Nagatsuka, Kentaro; Hasegawa, Takeshi; Morita, Keisuke; Aoki, Takeshi; Takahashi, Hideo; Kondo, Makoto; Sawahata, Hiroaki; Homma, Fumitaka; et al.
no journal, ,
This paper reports the results of elemental tests of aerodynamic parts, magnetic bearings, and high-speed motors as the development results of a helium gas circulator with magnetic bearings, which circulates helium gas in pipes connecting the HTGR and heat application facilities such as hydrogen production.
Matsui, Yutaka; Fujiwara, Yusuke; Morita, Keisuke; Nagatsuka, Kentaro; Hasegawa, Takeshi; Aoki, Takeshi; Kondo, Makoto; Sawahata, Hiroaki; Homma, Fumitaka; Takahashi, Hideo; et al.
no journal, ,
JAEA has initiated the HTTR heat application test project to demonstrate hydrogen production utilizing heat from a high-temperature gas-cooled reactor (HTGR) by coupling HTTR with a hydrogen production facility. A high-temperature isolation valve installed on the secondary helium piping is one of the key components of the heat application system. This valve isolates the nuclear facility from the heat application facility during abnormal events. This report describes the confirmation of design feasibility through simulation and the current status of welding technology development.
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
