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JAEA Reports

Assessment report research and development activities; Activity "Research and development on high-temperature gas-cooled reactor and hydrogen manufacturing technology" (Interim report)

Nuclear Hydrogen and Heat Application Research Center

JAEA-Evaluation 2014-001, 41 Pages, 2014/05

JAEA-Evaluation-2014-001.pdf:4.51MB

Japan Atomic Energy Agency (hereinafter referred to as "JAEA") consults an assessment committee, "Evaluation Committee of Research Activities for High-Temperature Gas-Cooled Reactor and Hydrogen Manufacturing Technology" (hereinafter referred to as "Evaluation Committee") for interim assessment of "High-Temperature Gas Reactor and Hydrogen Manufacturing Technology" in accordance with "General Guideline for the Evaluation of Government Research and Development (R&D) Activities" by Cabinet Office, Government of Japan, "Guideline for Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and "Regulation on Conduct for Evaluation of R&D Activities" by JAEA. An interim assessment of R&D activities in accordance with the second midterm plan "R&D on High-Temperature Gas Reactor and Hydrogen Manufacturing Technology Incorporating Them" by JAEA during the period of three years from April 2010 was carried out by "Evaluation Committee of Research Activities for High-Temperature Gas-Cooled Reactor and Hydrogen Manufacturing Technology" (hereinafter referred to as "Evaluation Committee"). The assessment was carried out based on the explanatory documents submitted by Nuclear Hydrogen and Heat Application Center, JAEA. As a result, the interim assessment to R&D activities from FY2008 to FY2012 was estimated as A about a High-Temperature Gas-Cooled Reactor and Hydrogen Manufacturing Technology. An interim assessment report "R&D on High-Temperature Gas Reactor and Hydrogen Manufacturing Technology" was finalized by the Evaluation Committee.

JAEA Reports

Assessment report of research and development on "The Abolition measures of nuclear facilities and associated technology development" and "Radioactive waste treatment and disposal and associated technology development" (Interim report)

Nuclear Cycle Backend Directorate

JAEA-Evaluation 2014-002, 182 Pages, 2014/07

JAEA-Evaluation-2014-002.pdf:101.85MB

Japan Atomic Energy Agency (JAEA) consulted the "Evaluation Committee for Nuclear Cycle Backend Program Promotion" to performed the interim evaluation of "The abolition measures of nuclear facilities and associated technology development" project and "radioactive waste treatment and disposal and associated technology development" project in accordance with the "Guideline for evaluation of government R&D activities", the "Guideline for evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology (MEXT)" and the "Operational rule for evaluation of R&D activities" by JAEA. In response to JAEA's request, the Committee decided the evaluation method and performed the interim evaluation of both projects from the viewpoints of purposes, plans, results and soon. As a result of review, the Committee concluded that both projects were proceeded adequately.

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

Assessment report of research and development activities; Activity "Quantum Beam Science Research" (Interim report)

Quantum Beam Science Center

JAEA-Evaluation 2014-004, 113 Pages, 2014/09

JAEA-Evaluation-2014-004.pdf:29.31MB

Japan Atomic Energy Agency (hereafter referred to as "JAEA") consults an assessment committee, "Evaluation Committee of Research Activities for Quantum Beam Science" (hereafter referred to as "Committee") for interim assessment of "Quantum Beam Science", in accordance with "General Guideline for the Evaluation of Government Research and Development (R&D) Activities" by Cabinet Office, Government of Japan, "Guideline for Evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology" and "Regulation on Conduct for Evaluation of R&D Activities" by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Quantum Beam Science Directorate (hereafter referred to as "QuBS") during the period from April 2010 to September 2012. The Committee evaluated the management and research activities of QuBS based on the explanatory documents and oral presentations by QuBS.

JAEA Reports

Safety requirements expected to the prototype fast breeder reactor "Monju"

Advisory Committee on Monju Safety Requirements

JAEA-Evaluation 2014-005, 275 Pages, 2014/11

JAEA-Evaluation-2014-005.pdf:134.4MB

In July 2013, Nuclear Regulation Authority (NRA) has enforced new regulatory requirements in consideration of severe accidents for the commercial light water reactors (LWR) and also prototype power generation reactors such as the sodium-cooled fast reactors (SFR) of "Monju" based on TEPCO Fukushima Daiichi Nuclear Power Plant accident occurred in March 2011. Although the regulatory requirements for SFR will be revised by NRA with consideration for public comments, Japan Atomic Energy Agency (JAEA) set up "Advisory Committee on Monju Safety Concept" consists of fast breeder reactor (FBR) and safety assessment experts in order to establish original safety requirements expected to prototype FBR "Monju" considering severe accidents with knowledge from JAEA as well as scientific and technical insights from the experts. This report summarizes the safety requirements expected to Monju discussed by the committee.

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