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Hama, Katsuhiro
Proceedings of 6th East Asia Forum on Radwaste Management Conference (EAFORM 2017) (Internet), 6 Pages, 2017/12
The Mizunami Underground Research Laboratory project is being pursued by the JAEA in the crystalline host rock at Mizunami City in Gifu Prefecture. The project proceeds in three overlapping phases, Surface-based investigation Phase (Phase I), Construction Phase (Phase II) and Operation Phase (III). During Phase I, a step-wise investigation was conducted by iterating investigation, interpretation, and assessment, thereby understanding of geologic environment was progressively and effectively improved with progress of investigation. During Phase II, we have evaluated adequacy of techniques for investigation, analysis and assessment of the deep geological environment established in the Phase I. For Phase III, three important issues were identified based on the latest results. Development of countermeasure technologies for reducing groundwater inflow, Development of modeling technologies for mass transport, Development of drift backfilling technologies.
Wada, Ryutaro*; Yoshinaka, Kazuyuki
Gijutsushi, 28(11), p.4 - 7, 2016/11
It is one of the important subjects for decommissioning to establish the safe and effective waste management. Research and Development programs on the waste management for Fukushima-Daiichi as it differs from normal practices are conducted by IRID. We show the outline of the lecture presented by Mr.Miyamoto, Deputy Director of IRID.
Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Kaji, Yoshiyuki
Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.21 - 30, 2016/09
Fuel rod, channel box, and control rod designed with new materials and concepts have been developed in Japan for increasing accident tolerance of LWRs. In order to efficiently and properly implement the accident tolerant fuels (ATFs) and the other components, it is necessary not only to accumulate fundamental and practical data but also to consider technology readiness, recognize knowledge gaps, and establish strategy for design and fabrication. The Japan Atomic Energy Agency (JAEA) has established the above "technical basis" and drafted a research plan towards implementation of the ATFs and components as a program sponsored and organized by the Ministry of Economy, Trade and Industry (METI). It is useful to take advantage of the experiences in commercial uses of zirconium-base alloys in LWRs and, therefore, JAEA has conducted this METI project in cooperation with power plant providers, fuel venders, research institutes and universities who have been involved in the development of the ATF materials. The present paper describes the main results of the project conducted to establish the technical basis of the ATFs and components.
Hama, Katsuhiro; Iwatsuki, Teruki; Matsui, Hiroya; Mikake, Shinichiro; Sasao, Eiji; Osawa, Hideaki
JAEA-Review 2016-004, 38 Pages, 2016/06
JAEA-Review-2016-004.pdf:7.07MB
The Mizunami Underground Research Laboratory project is being pursued by the Japan Atomic Energy Agency to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the host crystalline rock at Mizunami City in Gifu Prefecture, central Japan. The present report summarizes the research and development activities planned mainly in the -500m gallery.
Radioactive Waste Processing and Disposal Research Department
JAEA-Research 2015-016, 327 Pages, 2015/12
JAEA-Research-2015-016.pdf:41.98MB
The Japan Atomic Energy Agency has prepared the technical progress report on preliminary assessment of geological disposal for spent fuel (hereinafter referred to as "First Progress Report on Direct Disposal"). This report is aiming to examine the technical feasibility of the direct disposal of spent fuel in Japan, based on the results of research and development (R&D) on SF direct disposal carried out during FY 2013. In the First Progress Report on Direct Disposal, the available technology for the direct disposal of spent fuel in Japan was discussed through the preliminary design and safety assessment for the geological disposal system which were made under the limited conditions of representative characteristics of geological environment and spent fuel. Through R&D, the challenges and concerns on the engineering technology and the safety assessment, to be resolved for the Second Progress Report on Direct Disposal, were identified and classified.
Tokai Reprocessing Technology Development Center
JAEA-Evaluation 2015-012, 83 Pages, 2015/12
JAEA-Evaluation-2015-012.pdf:6.67MB
Japan Atomic Energy Agency (hereafter referred as "JAEA") consulted the "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" to assess the issue on "Research and Development on Reprocessing of Nuclear Fuel Materials" conducted by JAEA during the period from FY2010 to FY2014. In response to the JAEA's request, the committee assessed the R&D programs and the activities of JAEA related to the issue and concluded the mission was accomplished. This evaluation was performed based on the "General guideline for the 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.
Nuclear Science and Engineering Center; Center for Computational Science & e-Systems
JAEA-Evaluation 2015-003, 58 Pages, 2015/07
JAEA-Evaluation-2015-003.pdf:1.39MB
JAEA-Evaluation-2015-003-appendix(CD-ROM)..zip:9.94MB
Japan Atomic Energy Agency (hereinafter referred to as "JAEA") consults an assessment committee, "Evaluation Committee of Research Activities for Nuclear Science and Engineering" (hereinafter referred to as "Committee") for result and in-advance evaluation of "Nuclear Science and Engineering", 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 the JAEA. In response to the JAEA's request, the Committee assessed the research program of the Nuclear Science and Engineering Center (hereinafter referred to as "NSEC") and Center for Computational Science and e-Systems (hereinafter referred to as "CCSE"). The Committee evaluated the management and research activities of the NSEC and the CCSE based on explanatory documents prepared by the NSEC and the CCSE, and oral presentations with questions-and-answers.
Sakurai, Kiyoshi; Nakazawa, Masaharu*
Shimyureshon, 22(4), p.248 - 253, 2003/12
no abstracts in English
Sakurai, Kiyoshi
Nihon Genshiryoku Gakkai Monte Karuro Ho Ni Yoru Ryushi Shimyureshon No Genjo To Kadai, p.61 - 64, 2002/01
no abstracts in English
Research Evaluation Committee
JAERI-Review 2000-023, 37 Pages, 2000/10
JAERI-Review-2000-023.pdf:3.6MB
no abstracts in English
Research Evaluation Committee
JAERI-Review 2000-022, 53 Pages, 2000/10
JAERI-Review-2000-022.pdf:4.69MB
no abstracts in English
Sakurai, Kiyoshi; Ueki, Kotaro*; Naito, Yoshitaka*
Nihon Genshiryoku Gakkai-Shi, 42(10), p.1048 - 1049, 2000/10
no abstracts in English
Research Evaluation Committee
JAERI-Review 2000-012, 22 Pages, 2000/07
JAERI-Review-2000-012.pdf:2.58MB
no abstracts in English
Research Evaluation Committee
JAERI-Review 2000-011, 25 Pages, 2000/07
JAERI-Review-2000-011.pdf:2.74MB
no abstracts in English
Nomura, Masahiro; Toyama, Shinichi; ; ; Yamazaki, Yoshio; Hirano, Koichiro; Omura, Akiko
JNC TN9410 2000-007, 376 Pages, 2000/03
JNC-TN9410-2000-007.pdf:15.51MB
According to the Long-Term Program for Partitioning and Transmutation which was published by the Atomic Energy Commission in 1988, study on the transmutation using an electron accelerator, which was a part of the program, has been carried out in the O-arai Engineering Center. It is the study on converting radioactive fission products for example Strontium and Cesium to stable nuclides by photonuclear reaction caused by high energy gamma-ray made by an electron accelerator. It was thought that a 100mA-100MeV (10MW output power) accelerator would be needed in order to carry out the transmutation study in engineering phase. Therefore, development of the High-Current Electron Accelerator whose target had been 20mA-10MeV (200 kW output power) accelerator was carried out as development of elemental technologies on beam stabilization. The conceptual design of the accelerator was started in 1989. In March 1997, the main facility of this accelerator was completed. The test operation was carried out to confiim the performance of the accelerator from January, 1999 to December. As the result, an output of about 14 kW was achieved. In addition, the electron beam of 40 kW could be to accelerate in short time. In this report, the design, fabrication and evalution of performance of the facilities are presented.
; ; Toyama, Shinichi; Hasegawa, Makoto
JNC TN9410 2000-005, 182 Pages, 2000/03
JNC-TN9410-2000-005.pdf:5.73MB
According to the Long-term Program for Partitioning and Transmutation which was published by the Atomic Energy Commission in 1988, study on the transmutation using an electron accelerator, which was a part of the program, has been carried out in the O-arai Engineering Center. It is the study on converting radioactive fission products for example Strontium and Cesium to stable nuclides by photonuclear reaction caused by high energy gamma-ray made by an electron accelerator. It was thought that a 100mA-100Mev (10MW output power) accelerator would be needed in order to carry out the transmutation study in engineering phase. Therefore, development of the High-Current Electron Accelerator whose target had been 20mA-10Mev (200kW output power) accelerator was carried out as development of elemental technologies on beam stabilization. Construction of the accelerator was completed in March, 1997, afler development of the elemental devices. After the facility assessment, the full-scale experiment of the accelerator was started in January, 1999. However, the reform of the Power Reactor and Nuclear Fuel Development Corporation caused by the fire and explosion accident in the Asphalt Bitumenizing Facility was hardly discussed between the completion and the starting the experiment. It was decided that development of the accelerator would be terminated until the fiscal year 1999, results of the development would be summarized, and the developed accelerator would be planed to utilize as a beam utilization facility, in the Medium-Long-term Project Program of the Japan Nuclear Fuel Cycle Development Institute which was in March, 1999. It showed the direction that research and development for transmutation would be terminated. According to the Medium-Long-Term Project Program, the utilization of the accelerator was discussed, and research themes of the utilization of the accelerator in the various fields as well as nuclear field were investigated.
*; *; *; *
JNC TJ9440 2000-007, 43 Pages, 2000/03
JNC-TJ9440-2000-007.pdf:1.73MB
Planning of the plutonium utihzation in the Light water thermal reactor has been investigated to evaluate scenario for FBR development. Plans for MOX fuel utilization in the ABWR including Ooma plant are studied, and information of high burnup fuels for a future BWR is summarized based on public documents. Nuclear compositions of the present burnup fuel (45,000MWd/t) and a high burnup fue (60,000MWd/t) have been evaluated using an open code: SRAC. Results of the study are follows; (1)Surveying the status of MOX fuel utilization. The status of MOX and UO
fuel utilization in the present BWR and future BWR have been summarized based on public documents. (2)Evaluation of spent MOX and UO fuel composition. Nuclear compositions of spent MOX and UO fuels at 45,000MWd/t and 60,000MWd/t burnup have been evaluated and summarized for recycle scenarios by FBR.
*; *; *
JNC TJ8420 2000-003, 99 Pages, 2000/03
JNC-TJ8420-2000-003.pdf:5.47MB
no abstracts in English
