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Journal Articles

Challenge on development of the JAEA knowledge management system

Makino, Hitoshi; Semba, Takeshi; Shibata, Masahiro

NEA/RWM/R(2018)7 (Internet), p.315 - 322, 2022/11

This presentation summarize challenge on development of an advanced KMS by JAEA including the background to this initiative, the basic approach selected, a developed prototype of the JAEA KMS, and challenges and practical issues for introduction and also sustainable maintenance of the JAEA KMS.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage, 3; Progress report on NUMO-JAEA collaborative research in FY2013 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Kitamura, Akira; Yoshikawa, Hideki; Oda, Chie; Ishidera, Takamitsu; et al.

JAEA-Research 2014-030, 457 Pages, 2015/03

JAEA-Research-2014-030.pdf:199.23MB

JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and post-closure performance assessment in preliminary investigation stage. With regard to (1) study on rock suitability in terms of hydrology, based on some examples of developing method of hydro-geological structure model, acquired knowledge are arranged using the tree diagram, and model uncertainty and its influence on the evaluation items were discussed. With regard to (2) study on scenario development, the developed approach for "defining conditions" has been reevaluated and improved from practical viewpoints. In addition, the uncertainty evaluation for the effect of use of cementitious material, as well as glass dissolution model, was conducted with analytical evaluation. With regard to (3) study on setting radionuclide migration parameters, based on survey of precedent procedures, multiple-approach for distribution coefficient of rocks was established, and the adequacy of the approach was confirmed though its application to sedimentary rock and granitic rock. Besides, an approach for solubility setting was developed including the procedure of selection of solubility limiting solid phase. The adequacy of the approach was confirmed though its application to key radionuclides.

Journal Articles

Effect of local segregation of phosphorous on intergranular corrosion of type 310 stainless steel in boiling nitric acid

Komatsu, Atsushi; Motooka, Takafumi; Makino, Masashi; Nogiwa, Kimihiro; Ueno, Fumiyoshi; Yamamoto, Masahiro

Zairyo To Kankyo, 63(3), p.98 - 103, 2014/03

The effect of phosphorous on intergranular corrosion of type 310 stainless steel at transpassive potential was investigated using phosphorous added ultra high purity type 310 stainless steel. Intergranular corrosion depth was measured by scanning electron microscopic observation. Grain boundaries were observed using three dimensional atom probe. Intergranular corrosion was observed on phosphorous added stainless steel. The sample heat treated at 600$$^{circ}$$C showed severe integranular corrosion morphology. Observation by three dimensional atom probe revealed that grain boundary with high dissolution rate had segregated zone of chromium and phosphorous about 5nm in width, on the other hand, grain boundary with low dissolution rate had no segregated zone. From these results, it is suggested that intergranular corrosion of phosphorous added type 310 stainless steel at transpassive potential is affected by segregation of phosphorous and chromium along grain boundaries.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage, 2; Progress report on NUMO-JAEA collaborative research in FY2012 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Hayano, Akira; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; et al.

JAEA-Research 2013-037, 455 Pages, 2013/12

JAEA-Research-2013-037.pdf:42.0MB

Following FY2011, JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and performance assessment in preliminary investigation stage. With regard to (1) study on rock suitability in terms of hydrology, the tree diagram of methodology of groundwater travel time has been extended for crystalline rock, in addition, tree diagram for sedimentary rock newly has been organized. With regard to (2) study on scenario development, the existing approach has been improved in terms of a practical task, and applied and tested for near field focusing on the buffer. In addition, the uncertainty of some important processes and its impact on safety functions are discussed though analysis. With regard to (3) study on setting radionuclide migration parameters, the approaches for parameter setting have been developed for sorption for rocks and solubility, and applied and tested through parameter setting exercises for key radionuclides.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage; Progress report on NUMO-JAEA collaborative research in FY2011 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Hayano, Akira; Mitsui, Seiichiro; Taniguchi, Naoki; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; et al.

JAEA-Research 2012-032, 298 Pages, 2012/09

JAEA-Research-2012-032.pdf:33.68MB

JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and performance assessment in preliminary investigation phase. The topics and the conducted research are follows; (1) Study on selection of host rock: in terms of hydraulic properties, items for assessing rock property, and assessment methodology of groundwater travel time has been organized with interaction from site investigation. (2) Study on development of scenario: the existing approach has been embodied, in addition, the phenomenological understanding regarding dissolution of and nuclide release from vitrified waste, corrosion of the overpack, long-term performance of the buffer are summarized. (3) Study on setting nuclide migration parameters: the approach for parameter setting has been improved for sorption and diffusion coefficient of buffer/rock, and applied and tested for parameter setting of key radionuclides. (4) Study on ensuring quality of knowledge: framework for ensuring quality of knowledge has been studied and examined aimed at the likely disposal facility condition.

JAEA Reports

Horonobe Underground Research Laboratory Project; Synthesis of phase I investigation 2001 - 2005, Volume "Geological disposal research"

Fujita, Tomoo; Taniguchi, Naoki; Matsui, Hiroya; Tanai, Kenji; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; et al.

JAEA-Research 2011-001, 193 Pages, 2011/03

JAEA-Research-2011-001.pdf:5.23MB

This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project, of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the surface-based investigations in the Horonobe Underground Research Laboratory project as an example of actual geological environment.

JAEA Reports

CoolRep H22; Synthesis report on R&D results on geological disposal up to 2009

Umeki, Hiroyuki; Hioki, Kazumasa; Osawa, Hideaki; Fujita, Tomoo; Shibata, Masahiro; Makino, Hitoshi; Iwatsuki, Teruki; Takeuchi, Shinji; Ishimaru, Tsuneari

JAEA-Review 2010-073, 255 Pages, 2011/02

JAEA-Review-2010-073.pdf:4.19MB

The Japan Atomic Energy Agency (JAEA) has been performing research and development on geological disposal technology of high level radioactive waste. At the end of fiscal year 2009, the Geological Isolation Research and Development Directorate of JAEA made publicly available the "CoolRep H22", which is a web-based report that summarizes the R&D results, on its website. This document reports the contents of CoolRep H22.

JAEA Reports

Study on potential impacts of natural phenomena on a HLW geological disposal system

Kawamura, Makoto; Makino, Hitoshi; Sasao, Eiji; Niizato, Tadafumi; Yasue, Kenichi; Asamori, Koichi; Umeda, Koji; Ishimaru, Tsuneari; Osawa, Hideaki; Ebashi, Takeshi; et al.

JAEA-Research 2010-027, 85 Pages, 2010/09

JAEA-Research-2010-027.pdf:9.37MB

Japan Atomic Energy Agency (JAEA) have developed a formal evaluation method to assess the potential impacts of natural phenomena (earthquakes and faulting; volcanism; uplift, subsidence, denudation and sedimentation; climatic and sea-level changes) on a high level radioactive waste (HLW) disposal system for the purpose of maintenance of evaluation method for potential impacts of natural phenomena within more realistic view. In this report, we developed a framework as a part of the total system performance assessment for two purposes: the first one is quantification of relationship of characteristic of natural phenomena between geological environmental conditions (T-H-M-C-G), and the other one is quantification of relationship of T-H-M-C-G condition between parameters of performance assessment. We tried to apply the framework to all natural phenomena to confirm the effectiveness of the framework. On the other hand, we applied an argument-diagram that was developed one of the methods of the knowledge management to elicit future tasks. As a result, to apply the framework, we could show that information integration could carry out efficiently, and information integration was attained by the common framework by combining information on geohistory and existing information of natural phenomena and geological environmental conditions as modern-analogue. We could show that suitable scenarios might be chosen by information integration. Furthermore, we were able to elicit future tasks to this study by applying the argument-diagram.

JAEA Reports

Information basis for developing comprehensive waste management system; US-Japan Joint Nuclear Energy Action Plan Waste Management Working Group Phase I report (Joint research)

Yui, Mikazu; Ishikawa, Hirohisa; Watanabe, Atsuo*; Yoshino, Kyoji*; Umeki, Hiroyuki; Hioki, Kazumasa; Naito, Morimasa; Seo, Toshihiro; Makino, Hitoshi; Oda, Chie; et al.

JAEA-Research 2010-015, 106 Pages, 2010/05

JAEA-Research-2010-015.pdf:13.58MB

This report summarizes the activity of Phase I of Waste Management Working Group of the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The working group focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios in both countries were surveyed and summarized. Secondly, the waste management/disposal system optimization was discussed. Repository system concepts for the various classifications of nuclear waste were reviewed and summarized, then disposal system optimization processes and techniques were reviewed, and factors to consider in future repository design optimization activities were also discussed. Finally the potential collaboration areas and activities related to the optimization problem were extracted.

JAEA Reports

Construction, management and operation on advanced volume reduction facilities

Higuchi, Hidekazu; Osugi, Takeshi; Nakashio, Nobuyuki; Momma, Toshiyuki; Tohei, Toshio; Ishikawa, Joji; Iseda, Hirokatsu; Mitsuda, Motoyuki; Ishihara, Keisuke; Sudo, Tomoyuki; et al.

JAEA-Technology 2007-038, 189 Pages, 2007/07

JAEA-Technology-2007-038-01.pdf:15.13MB
JAEA-Technology-2007-038-02.pdf:38.95MB
JAEA-Technology-2007-038-03.pdf:48.42MB
JAEA-Technology-2007-038-04.pdf:20.53MB
JAEA-Technology-2007-038-05.pdf:10.44MB

The Advanced Volume Reduction Facilities (AVRF) is constructed to manufacture the waste packages of radioactive waste for disposal in the Nuclear Science Research Institute of the Japan Atomic Energy Agency. The AVRF is constituted from two facilities. The one is the Waste Size Reduction and Storage Facility (WSRSF) which is for reducing waste size, sorting into each material and storing the waste package. The other is the Waste Volume Reduction Facility (WVRF) which is for manufacturing the waste package by volume reducing treatment and stabilizing treatment. WVRF has an induction melting furnace, a plasma melting furnace, an incinerator, and a super compactor for treatment. In this report, we summarized about the basic concept of constructing AVRF, the constitution of facilities, the specifications of machineries and the state of trial operation until March of 2006.

JAEA Reports

Horonobe Underground Research Laboratory project synthesis of phase I investigation 2001-2005 volume "Geological Disposal Research"

Fujita, Tomoo; Taniguchi, Naoki; Matsui, Hiroya; Tanai, Kenji; Nishimura, Mayuka; Kobayashi, Yasushi; Hiramoto, Masayuki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; et al.

JAEA-Research 2007-045, 140 Pages, 2007/03

JAEA-Research-2007-045-1.pdf:38.33MB
JAEA-Research-2007-045-2.pdf:44.62MB

This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project (HOR), of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological environments and derive future subjects based on the results. The design methods of geological disposal were reviewed based on the recent knowledge and the advertences were identified. Then the parameters for virtual design of engineered barrier system, backfill deposition hole and tunnel were set up based on actual geological conditions obtained from the surface-based investigations in HOR as an example of actual geological environment. The conceptual structure from site investigation and evaluation to mass transport analysis was represented as a work flow at first. Then following this work flow a series of procedures for mass transport analysis were carried out based on actual geological conditions obtained from the surface-based investigations in HOR to illustrate the functioning of the work flow and the applicability of this methodology. Consequently, knowledge that will help follow-up or future execution and planning activities was obtained.

JAEA Reports

None

Makino, Hitoshi; Sawada, Atsushi; Maekawa, Keisuke; Shibata, Masahiro; Sasamoto, Hiroshi; Yoshikawa, Hideki; Wakasugi, Keiichiro; Koo, Shigeru*; Hama, Katsuhiro; Kurikami, Hiroshi; et al.

JNC TN1400 2005-021, 148 Pages, 2005/09

JNC-TN1400-2005-021.pdf:32.85MB

None

JAEA Reports

Study on Methodology for Biosphere Assessment Data

Kato, Tomoko; Suzuki, Yuji*; Makino, Hitoshi; Uchida, Masahiro; Naito, Morimasa; Wakasugi, Keiichiro*; Takahashi, Yoshiaki*

JNC TN1400 2005-024, 14 Pages, 2005/08

JNC-TN1400-2005-024.pdf:0.67MB

Biosphere assessment is positioned as part of an important factor in safety assessment to convert nuclide release rates into surface environment to measures of effect for human, such as radiation dose. In general, a lot of data are handled in the biosphere assessment, and they are based on the feature of specific site. Therefore, it is reasonable to screen parameters in order to manage the limited resource and develop the biosphere assessment effectively. JNC and NUMO established

Journal Articles

Development of the JNC Geological Disposal Technical Information Integration System(JGIS)

Shibata, Katsushi; Makino, Hitoshi; Wakasugi, Keiichiro; Uchida, Masahiro

Saikuru Kiko Giho, (21), p.79 - 88, 2003/12

R&D of geological disposal of high-level radioactive waste consists of three fields (site investigation, repository design and safety assessment). It is necessary to deal with an increase in quantity of , and growing diversity and complexity of technical information caused by progress of R&D at each field and accelerated iteration within these three fields. To deal with this problem, it is necessary to prepare the computational environment that can catalogue and share the technical information efficiently and effectively. This report introduces concept and approach for developing a "JNC Geological Disposal Technical Information Integration System (JGIS)"

Journal Articles

Biosphere Assessment for High-level Radioactive Waste Disposal: Modelling Experinces and Discussion on Key Parameters by Sensitivity Analysis in JNC

Kato, Tomoko; Suzuki, Yuji*; Makino, Hitoshi; Uchida, Masahiro

Proceedings of International Symposium on Radioecology and Environmental Dosimetry, p.465 - 472, 2003/10

Considering a wide range of Japanese geological environments in generic context, some biosphere models were developed using an approach consistent with the BIOMASS Methodology. Moreover, sensitivity analysis for the biosphere models was performed to evaluate and understand the relative importance of parameters.

Journal Articles

Biosphere Assessment for High-level Radioactive Waste Disposal: Modelling Experiences and Discussion on Key Parameters by Sensitivity Analysis in JNC

Kato, Tomoko; Suzuki, Yuji*; Makino, Hitoshi; Uchida, Masahiro

Heisei-15-Nendo Kankyoken Kokusai Kento Iinkai "Hoshasei Seitaigaku To Kankyo No Hoshasen Hibaku Ni Kansuru Kokusai Shimpojiumu", 35 Pages, 2003/00

JNC has an on-going programme of research and development relating to the safety assessment of the deep geological system of high-level radioactive waste. This paper summarises the approach used for the deriviation of "flux to dose conversion factors" for the range of geosphere-biosphere interfaces and potential exposure groups and discussion on key parameters in JNC' biosphere assessment.

Journal Articles

Development of JNC Geologic Disposal Technical Information Integration System -An Approach to Integrate and Share Technical Information among Safety Assessment, Repository Design and Site Investigation

Uchida, Masahiro; Makino, Hitoshi; Wakasugi, Keiichiro; Shibata, Katsushi

OECD/NEA Amigo Project Dai-1-Kai Wakushoppu, 0 Pages, 2003/00

None

JAEA Reports

Results from synthesis of calculation cases illustrating overall system performance in the safety assessment in H12 report

Makino, Hitoshi; ; Kato, Tomoko; ; Uchida, Masahiro

JNC TN8450 2001-012, 11 Pages, 2002/02

JNC-TN8450-2001-012.pdf:0.49MB

JNC (Japan Nuclear Cycle Development Institute) had proceeded R&D activities to provide a scientific and technical basis for geological disposal of HLW in Japan. The second progress report (H12) documented the progress of R&D and the Japanese version was submitted to the AEC (the Atomic Energy Commission) in November 1999. This report summarizes the calculation results for nuclide migration in "Synthesis of Calculation Cases Illustrating Overall System Performance", which are performed to examine the safety of the geological disposal concept in Japan in the Safety Assessment in H12 Report. In addition, a set of calculation result for nuclide migration through each pathway in one-dimensional multiple pathway model (a set of 48 segments) are summarized for the Reference Case in H12 Report, and calculated dose conversion factors are also summarized against the combinations of potential Geosphere-Biosphere Interfaces (GBI) and potential exposure groups. Digital data of the calculation results are summarized in Appendix CD-ROM as Microsoft EXCEL files.

JAEA Reports

None

Yui, Mikazu; Shibata, Masahiro; Makino, Hitoshi; ; ; Ishiguro, Katsuhiko; Ishikawa, Hirohisa

PNC TN8410 92-162, 140 Pages, 1992/09

PNC-TN8410-92-162.pdf:3.14MB

None

Oral presentation

Development of simplified pellet fuel production technology, 2; Processing technology for de-nitration conversion based on microwave heating

Kato, Yoshiyuki; Kimura, Yuichi; Isomae, Hidemi; Kurita, Tsutomu; Yoshimoto, Katsunobu; Makino, Takayoshi; Suzuki, Masahiro; Kihara, Yoshiyuki

no journal, , 

no abstracts in English

33 (Records 1-20 displayed on this page)