Survey on candidate construction site for the demonstrator of High Temperature Gas-cooled Reactor in the UK

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).

Reduction and resource recycling of high-level radioactive wastes through nuclear transmutation; Isolation techniques of Pd, Zr, Se and Cs in simulated high level radioactive waste using solvent extraction

Sasaki, Yuji; Morita, Keisuke; Ito, Keisuke; Suzuki, Shinichi; Shiwaku, Hideaki; Takahashi, Yuya*; Kaneko, Masaaki*; Omori, Takashi*; Asano, Kazuhito*

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 4 Pages, 2017/09

no abstracts in English

Progress in thermohydraulic analysis of accident scenarios of a water-cooled fusion DEMO reactor

Nakamura, Makoto; Watanabe, Kazuhito; Tobita, Kenji; Someya, Yoji; Tanigawa, Hisashi; Uto, Hiroyasu; Sakamoto, Yoshiteru; Araki, Takao*; Asano, Shiro*; Asano, Kazuhito*; et al.

Proceedings of 26th IEEE Symposium on Fusion Engineering (SOFE 2015), 6 Pages, 2015/06

https://doi.org/10.1109/sofe.2015.7482295

We report recent progress in thermohydraulic analysis of several types of accidents of a water-cooled fusion DEMO reactor. We particularly studied (1) in-vessel (in-VV) loss-of-coolant accident (LOCA) of the first wall (FW) cooling pipes, (2) ex-vessel (ex-VV) LOCA of the primary cooling system, (3) LOCA in blanket modules (in-box LOCA) and (4) loss-of-vacuum accident (LOVA). The analysis identified transient responses of safety-class or safety-important reactor components and structures of the DEMO to these accidents. The pressure loads to the barriers confining radioactive materials were also evaluated. On a basis of these analysis results, strategies to confine the radioactive materials, i.e. tritium and activated tungsten dust, against these accidents were assessed.

Reduction and resource recycling of high-level radioactive wastes through nuclear transmutation; From viewpoint of reprocessing and recycling, 1; Separation and recovery of LLFP from high-level liquid wastes

Sasaki, Yuji; Morita, Keisuke; Suzuki, Shinichi; Shiwaku, Hideaki; Ito, Keisuke; Takahashi, Yuya*; Kaneko, Masaaki*; Asano, Kazuhito*

no journal, , 

no abstracts in English

The Strategy of HTGR fuel development

Yoshino, Masaki; Asano, Kazuhito; Fukaya, Yuji; Sato, Hiroyuki; Sakaba, Nariaki

no journal, , 

The strategy of HTGR fuel development is required for the HTGR demonstration reactor planned its operation in late 2030s for reliable and economic operations. In order to improve HTGR economic efficiency, higher burn-up fuel must be installed after confirming fuel integrity requirements by irradiation tests. Further, higher one compared with HTTR (High Temperature Engineering Test Reactor) is expected to perform economic improvement in HTGR demonstration reactor. These implementation items need to be planned in line with the HTGR demonstration reactor plan. So as to adapt these requirements, HTGR fuel research and development plan has been drawn up by Japan Atomic Energy Agency (JAEA). This plan aims to minimise development elements by maximising the utilisation of the proven fuel design of HTTR that can perform 60 GWd/t burn-up level without re-design of fuel. Higher burn-up fuel up to 160GWd/t is also planned to adapt commercial HTGR by applying ZrC coating and R&D such as SiC layer strength evaluation. Irradiation plans to perform fuel integrity at each burn-up are also identified. By framing HTGR fuel development plan that is consistent with the demonstration reactor schedule while improving fuel economy, JAEA has identified the action items necessary for the realisation of commercialising HTGR.

Recovery of LLFP from high-level liquid waste, 3; Properties of solvent for the replacement of n-dodecane

Sasaki, Yuji; Suzuki, Shinichi; Kobayashi, Toru; Ito, Keisuke*; Takahashi, Yuya*; Kaneko, Masaaki*; Asano, Kazuhito*

no journal, , 

At ImPACT project, we investigate more safety and effect disposal method by using separation of long-lived radioactive nuclides and their transmutation from high-level radioactive waste (HLW). High concentration of Zr in simulated HLW is extracted by HDEHP or TODGA, so we study on properties of diluents instead of n-dodecane. Especially we study on the radiolysis. After irradiation of TODGA dissolved in different 5 diluents, we use these extraction solvents as solvent extraction of Nd. It is found that distribution ratio of Nd decrease with irradiation time.