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JAEA Reports

Assessment report on research and development activities in FY2017; Activity "Research and development on high temperature gas-cooled reactor and related heat application technology" (Annual report)

Tatematsu, Kenji; Nishihara, Tetsuo

JAEA-Evaluation 2018-001, 71 Pages, 2018/06

JAEA-Evaluation-2018-001.pdf:6.84MB

Executive Director of Sector of Nuclear Science Research in Japan Atomic Energy Agency consulted with the "Evaluation Committee of Research Activities for High Temperature Gas-cooled Reactor and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee"), which consists of specialists in the fields of the evaluation subjects of high temperature gas-cooled reactor and related heat application technology, about the relevance of the management and research activities of the HTGR Hydrogen and Heat Application Research Center in FY2017.Research activity for FY2017, The Evaluation Committee concluded with a score of S for "Conformity confirmation conformity to HTTR's new regulatory standards", "Cooperation with industry" and "Promotion of international cooperation". Therefore, the Evaluation Committee concluded with a score of A for the overall activity by evaluating that more results than originally required were acquired. Also, regarding the research plan for FY2018, it was judged appropriate. This report summarizes the members of the Evaluation Committee, outlines the method, the review process for procedure of the assessment and that result.

JAEA Reports

Assessment report on research and development activities in FY2016; Activity "Research and development on high temperature gas-cooled reactor and related heat application technology" (Interim report)

Tatematsu, Kenji; Nishihara, Tetsuo

JAEA-Evaluation 2017-001, 107 Pages, 2017/09

JAEA-Evaluation-2017-001.pdf:13.46MB

President of Japan Atomic Energy Agency consulted with the "Evaluation Committee of Research Activities for High Temperature Gas-cooled Reactor and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee"), which consists of specialists in the fields of the evaluation subjects of high temperature gas-cooled reactor and related heat application technology, about the relevance of the management and research activities of the HTGR Hydrogen and Heat Application Research Center during the period from April 2015 to March 2017. The assessment of the Evaluation Committee concluded with a score of B for the confirmation of adjustability to the new regulation standard for restarting HTTR and for the development of hydrogen production technology, a score of A for the design of HTTR-GT/H$$_{2}$$ test plant completing all equipment design specification and for the development exceeding the original scope of an oxidation resistant fuel element containing SiC. The Evaluation Committee concluded with a score of A for the overall activity. In addition, the Evaluation Committee recommended that the judgement to move to the construction phase of the HTTR-GT/H$$_{2}$$ test plant be made after 3-4 years, after the HTTR will be restarted and the thermal load fluctuation tests using HTTR will be carried out. This report lists the members of the Evaluation Committee and outlines the method and procedure of the assessment. The assessment report by the Evaluation Committee is attached.

JAEA Reports

Assessment report of research and development activities in FY2014; Activity "Research and development on high-temperature gas-cooled reactor and related hydrogen production technology"

Tatematsu, Kenji; Matsumoto, Hiroyuki

JAEA-Evaluation 2015-001, 91 Pages, 2015/06

JAEA-Evaluation-2015-001.pdf:14.25MB

President of Japan Atomic Energy Agency consulted with the "Evaluation Committee of Research Activities for High-Temperature Gas-Cooled Reactor and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee"), which consists of specialists in the fields of the evaluation subjects of high-temperature gas-cooled reactor and related hydrogen production technology. The evaluation concludes that an overall judgment is A, because the outcome of the 2nd midterm plan has been obtained as planed in terms of advancing the safety and the practical use in each of the high-temperature gas-cooled reactor technology and the hydrogen production technology. As a result the technological goal has been achieved. Another key outcome obtained is that the achievement for a part of the next midterm plan has been accelerated with the construction of a continuous hydrogen production test facility. In addition, the contents of the 3rd period mid- to long- term plan (draft) are acceptable because they sufficiently reflect the interim report of the high-temperature gas-cooled reactor technical research and development working group organized by the MEXT. This report lists the members of the Evaluation Committee and outlines the method and procedure of the assessment. The results of the assessment by the Evaluation Committee are attached from Page 7.

JAEA Reports

Assessment report of research and development activities; Activity "Research and development on high-temperature gas-cooled reactor and related hydrogen production technology"

Tatematsu, Kenji; Matsumoto, Hiroyuki

JAEA-Evaluation 2014-003, 131 Pages, 2014/09

JAEA-Evaluation-2014-003.pdf:26.08MB

Japan Atomic Energy Agency consulted with "Evaluation Committee of Research Activities for High-Temperature Gas-Cooled Reactor and Related Hydrogen Production Technology" (hereinafter referred to as "Evaluation Committee") which consists of specialists in the fields of the evaluation subjects of high-temperature gas-cooled reactor and related hydrogen production technology. The evaluation concludes that Japan needs to have the high-temperature gas-cooled reactor and hydrogen production technology because it is important that the nuclear energy be utilized to meet heat demand in order to contribute to the emission reduction of carbon dioxide in industry and transportation sectors. Therefore, the research and development should continue with the use of the High Temperature Engineering Test Reactor and the aim of establishing the basic technology. This report lists the members of the Evaluation Committee and the Expert Committee and outlines the method and procedure of the assessment. The result of the assessment by the Committees are attached from page 7.

JAEA Reports

Choice evaluation of power supply composition using the mapping method of the long-term energy demand-and-supply scenario

Tatematsu, Kenji

JAEA-Research 2012-042, 45 Pages, 2013/03

JAEA-Research-2012-042.pdf:2.47MB

Long-term energy demand-and-supply were analyzed for our country using the MARKAL model, supposing six kinds of energy demand-and-supply scenarios where different installed capacity of nuclear power generation and the emission standard of carbon-dioxide were employed. It was shown that even when nuclear power generation was not used, the carbon-dioxide emissions in the whole country and a power generation sector are reducible by 37% and 47% in 2050 from the 1990 level, respectively. However, when nuclear power generation was phase-out and renewable energy and natural gas were substituted, it was found that an average power generating cost was higher than the case where use of nuclear or coal was continued, 3.7 yen/kWh or more. Moreover, in the case where immediate cessation of the nuclear power generation was carried out, it was also shown that a current average power generating cost rose by 4.4 yen/kWh. In order to evaluate and visualize the influence of power supply composition change on both the average power generating cost and the carbon-dioxide emissions, a new mapping method was proposed where diversity of an energy source, the carbon-dioxide emissions, and the average power generating cost were used as indexes. Based on the result of model analysis, when nuclear power generation was substituted with renewable energy, natural gas, or coal, oligopoly of an energy source was shown to increase sharply by abolition of nuclear power generation. These results showed that by continuing use of the nuclear power generation with a fixed scale, less carbon-dioxide emissions, avoiding oligopolization of an energy source and suppressing the steep rise of an average power generating cost were possible.

JAEA Reports

Long-term outlook of energy demand and supply in Japan; Estimation of energy demand and supply for "Nuclear Energy Vision 2100" of JAEA

Tatematsu, Kenji; Kawasaki, Hirotsugu; Nemoto, Masahiro; Murakami, Masakazu

JAEA-Research 2009-007, 46 Pages, 2009/06

JAEA-Research-2009-007.pdf:3.96MB

In this study, we showed an energy demand and supply scenario toward the year 2100 in Japan, which underlies JAEA's "Nuclear Energy Vision 2100" published in October 2008. This energy demand and supply scenario aims at the coexistence of the reduction of the carbon dioxide emission and the energy security through reduction of the fossil fuel usage, positive electrification and the nuclear energy usage. We reduce the ratio of the fossil fuel in the primary energy supply to about 1/3 and extend the share of renewable and nuclear energy to 70% from current 15%. As a result, the carbon dioxide emission is reduced to current 10%, and it developed that the half was the contribution of the nuclear energy.

Journal Articles

Revolution scenario of energy demand-supply structure for 100 years

Tatematsu, Kenji; Kawasaki, Hirotsugu; Nemoto, Masahiro

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 51(6), p.463 - 467, 2009/06

no abstracts in English

JAEA Reports

The Possible role of reduced-moderation water reactors and its sensitivity to fuel recycling conditions

Tatematsu, Kenji; Sato, Osamu

JAERI-Research 2004-024, 35 Pages, 2005/01

JAERI-Research-2004-024.pdf:9.97MB

Many scenarios were defined for future development of nuclear power generation and fuel cycle systems in Japan. These scenarios were quantitatively analyzed from the viewpoint of plutonium recycling, natural uranium consumption, stock of spent fuel, etc. Following findings were obtained from the analysis. RMWRs will contribute to control the uranium consumption at certain finite levels if net conversion ratio (CR) is kept higher than 1.0. However, since RMWRs do not have an excellent breeding performance in comparison with FBRs, their effect is very sensitive to the conditions on fuel recycling processes. Judging from the results of analysis using a RMWR design with gross CR 1.06, it would be necessary for RMWRs to have net CR 1.04 in order to replace enriched uranium fuelled LWRs by around the year 2200, and thereby to keep ultimate natural uranium consumption at rather low levels. This can be achieved by controlling fuel duration time outside reactors to shorter than 4 years or 6 years, when total loss of plutonium during the processes of recycling is 1.0% or 0.2%, respectively.

Journal Articles

Toward very long-term utilization of nuclear energy; Prospects and problems of water-cooled breeder "reduced moderation water reactor"

Sato, Osamu; Tatematsu, Kenji; Tanaka, Yoji*

Genshiryoku eye, 47(7), p.60 - 64, 2001/07

no abstracts in English

JAEA Reports

An Analysis on the economics of plutonium recycle

Tatematsu, Kenji; Tanaka, Yoji*; Sato, Osamu

JAERI-Research 2001-014, 25 Pages, 2001/03

JAERI-Research-2001-014.pdf:2.23MB

no abstracts in English

JAEA Reports

An Analysis on the roles of reduced-moderation water reactors

Tatematsu, Kenji; Sato, Osamu; Tanaka, Yoji*

JAERI-Research 2000-025, 74 Pages, 2000/05

JAERI-Research-2000-025.pdf:2.4MB

no abstracts in English

Oral presentation

Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 8; Conceptual design of breeder type FLWR core using recovered uranium as blanket fuel

Uchikawa, Sadao; Nakano, Yoshihiro; Tatematsu, Kenji; Okubo, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 11; An Analysis on roles of breeder type FLWRs using enriched recovered uranium

Tatematsu, Kenji; Ishikawa, Nobuyuki; Uchikawa, Sadao; Okubo, Tsutomu

no journal, , 

In this study, the roles of breeder type FLWRs using enriched recovered uranium were quantitatively analyzed from the viewpoint of installed capacity of FLWRs, reprocessing plant capacity and the natural uranium consumption in Japanese future nuclear power generation systems. It became clear that the newly-designed breeder type FLWRs could shorten realization of the complete closed cycles to about 150 years.

Oral presentation

Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 10; Conceptual design of breeder type FLWR core with a breeding ratio of 1.1 for transitioning to long term sustainable fuel cycles

Uchikawa, Sadao; Okubo, Tsutomu; Nakano, Yoshihiro; Kobayashi, Noboru; Tatematsu, Kenji; Ishikawa, Nobuyuki

no journal, , 

no abstracts in English

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