Development of coupling technology for high temperature gas-cooled reactors and hydrogen production facility; HTTR heat application test project plan

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

https://doi.org/10.1299/jsmepes.2023.27.A242

Development plan for coupling technology between high temperature gas-cooled reactor HTTR and hydrogen production facility, 1; Overview of the HTTR heat application test plan to establish high safety coupling technology

Nomoto, Yasunobu; Mizuta, Naoki; Morita, Keisuke; Aoki, Takeshi; Okita, Shoichiro; Ishii, Katsunori; Kurahayashi, Kaoru; Yasuda, Takanori; Tanaka, Masato; Isaka, Kazuyoshi; et al.

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 7 Pages, 2023/05

High temperature gas-cooled reactors

Takeda, Tetsuaki*; Inagaki, Yoshiyuki; Aihara, Jun; Aoki, Takeshi; Fujiwara, Yusuke; Fukaya, Yuji; Goto, Minoru; Ho, H. Q.; Iigaki, Kazuhiko; Imai, Yoshiyuki; et al.

High Temperature Gas-Cooled Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.5, 464 Pages, 2021/02

https://doi.org/10.1016/C2018-0-05383-9

As a general overview of the research and development of a High Temperature Gas-cooled Reactor (HTGR) in JAEA, this book describes the achievements by the High Temperature Engineering Test Reactor (HTTR) on the designs, key component technologies such as fuel, reactor internals, high temperature components, etc., and operational experience such as rise-to-power tests, high temperature operation at 950C, safety demonstration tests, etc. In addition, based on the knowledge of the HTTR, the development of designs and component technologies such as high performance fuel, helium gas turbine and hydrogen production by IS process for commercial HTGRs are described. These results are very useful for the future development of HTGRs. This book is published as one of a series of technical books on fossil fuel and nuclear energy systems by the Power Energy Systems Division of the Japan Society of Mechanical Engineers.

Study of an incrementally loaded multistage flash desalination system for optimum use of sensible waste heat from nuclear power plant

Yan, X.; Noguchi, Hiroki; Sato, Hiroyuki; Tachibana, Yukio; Kunitomi, Kazuhiko; Hino, Ryutaro

International Journal of Energy Research, 37(14), p.1811 - 1820, 2013/11

https://doi.org/10.1002/er.2995

Existing nuclear desalination cogeneration incurs loss of nuclear plant power generation. Such loss is avoided with the plant design GTHTR300 proposed in the present study. The plant is based on a HTGR. Gas turbine is used to replace steam turbine as power generator. The gas turbine converts about a half of the reactor thermal power to electricity while rejecting the balance as sensible waste heat to be utilized in a MSF plant for desalination. A new MSF is proposed to efficiently match the sensible waste heat source. Although operating with a similar number of stages to traditional process, the new process is shown to produce 45% more water over the same temperature range.

For discussions with the public for the safety of nuclear power; Risks for judgments

Noguchi, Kazuhiko*; Miyano, Hiroshi*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*; Sugiyama, Kenichiro*

no journal, , 

The risk is used for an index to judge. The risk to be considered varies according to the purpose of the judgment. The analysis of the risk needs the knowledge of the nuclear energy system and society.

For discussions with the public for the safety of nuclear power; Social risk and nuclear risk

Matsumoto, Masaaki*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsunaga, Yoko*; Sugiyama, Kenichiro*

no journal, , 

In society, understanding of risk is various. We will show how to understand risk and describe how to face risks in the society. Individual risks are accepted by individuals, but it is necessary for society to construct a structure in society that allows risks to be tolerated by society. For that purpose, we also describe what social risk is and how society and individuals face social risks and how to choose risks to accept. We consider not only the concept of nuclear risk but also how nuclear risk should be accepted from the viewpoint of disaster prevention for the public.

For discussions with the public for the safety of nuclear power; Risk assessment for nuclear safety and application to external event

Takata, Takashi; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Narumiya, Yoshiyuki*; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*

no journal, , 

A considering nuclear safety, it is an important task to clarify the relationship with "peace of mind" that is the heart of people. In this paper, a fundamental methodology of risk assessment for nuclear safety is introduced based on a probabilistic risk assessment (PRA) method. Furthermore, an application of the methodology for an external event is also discussed.

For discussions with the public for the safety of nuclear power; Various patterns of risk application method and examples

Narumiya, Yoshiyuki*; Miyano, Hiroshi*; Noguchi, Kazuhiko*; Muramatsu, Ken*; Takata, Takashi; Muta, Hitoshi*; Itoi, Tatsuya*; Matsumoto, Masaaki*; Matsunaga, Yoko*

no journal, , 

Target of PRA is not calculating PRA to get CDF/CFF, but providing significant and useful information from PRA results for risk-informed activities. Lot of risk applications have been implemented these about 20 years in US. After Fukushima Dai-ichi accidents, Japanese Nuclear Regulation Authority provided new regulatory requirements about external events and beyond design events. And Risk Application faces full-scale implementation. In this report, several methods of risk application are showed with adequate risk indexes. Two examples of risk application, risk-informed shutdown management and RI-ISI, are provided. The explanation about Risk Informed Decision-Making Process is made.

Development of large-scale hydrogen production technology utilizing very high temperature, 1-1; Overview of large-scale hydrogen production demonstration project utilizing very high temperature

Sato, Hiroyuki; Iigaki, Kazuhiko; Shimizu, Atsushi; Noguchi, Hiroki; Sakaba, Nariaki; Asano, Koji*; Oyama, Sunao*; Onishi, Hiroyuki*; Suyama, Kazumasa*; Usui, Yukinori*

no journal, , 

no abstracts in English

Muonic X-ray analysis for Ryugu samples

Osawa, Takahito; Ninomiya, Kazuhiko*; Nakamura, Tomoki*; Takahashi, Tadayuki*; Terada, Kentaro*; Yurimoto, Hisayoshi*; Noguchi, Takaaki*; Okazaki, Ryuji*; Yabuta, Hikaru*; Naraoka, Hiroshi*; et al.

no journal, , 

I report on the muonic X-ray analysis experiment conducted at J-PARC from 2020 to 2021, in which the analytical method was significantly developed through four preliminary experiments and successfully analyzed samples from the asteroid Ryugyu in July 2021. The experimental process is described from a radiochemical point of view.

多段フラッシュ型海水淡水化装置及び方法

野口 弘喜; Yan, X.; 日野 竜太郎; 佐藤 博之; 橘 幸男; 國富 一彦

not registered

JP, 2013-025416  Patent licensing information  Patent publication (In Japanese)

【課題】高温ガス炉からの大量の廃熱を回収して、淡水製造量を大幅に向上させることができる多段フラッシュ型海水淡水化装置を提供する。 【解決手段】発電システムからの廃熱との熱交換により原料海水を加熱する加熱部10と、加熱部10において加熱された海水をフラッシュ蒸発させて淡水を得、蒸発潜熱を原料海水により熱回収する熱回収部20と、熱回収部20からの残余の加熱された海水をフラッシュ蒸発させて淡水を得、蒸発潜熱を外部に放出する熱放出部30と、を具備し、加熱部10は、段階的に温度が低下するように直列に連結されている複数の加熱セクション11A、11B、11C・・・を有し、熱回収部20は、各加熱セクションにて加熱された海水を受け入れてフラッシュ蒸発させる1以上のフラッシュ蒸発室を有する熱回収セクション21A、21B、21C・・・を有し、各加熱セクションと各熱回収セクションとが熱交換関係に連結されている、海水淡水化装置。