Sugita, Yutaka; Taniguchi, Naoki; Makino, Hitoshi; Kanamaru, Shinichiro*; Okumura, Taisei*
Nippon Genshiryoku Gakkai Wabun Rombunshi, 19(3), p.121 - 135, 2020/09
A series of structural analysis of disposal containers for direct disposal of spent fuel was carried out to provide preliminary estimates of the required pressure resistance thickness of the disposal container. Disposal containers were designed to contain either 2, 3 or 4 spent fuel assemblies in linear, triangular or square arrangements, respectively. The required pressure resistance thickness was evaluated using separation distance of the housing space for each spent fuel assembly as a key model parameter to obtain the required thickness of the body and then the lid of the disposal container. This work also provides additional analytical technical knowledge, such as the validity of the setting of the stress evaluation line and the effect of the model length on the analysis. These can then be referred to and used again in the future as a basis for conducting similar evaluations under different conditions or proceeding with more detailed evaluations.
Sugita, Yutaka; Kageyama, Takeshi*; Makino, Hitoshi; Shimbo, Hiroshi*; Hane, Koji*; Kobayashi, Yuichi*; Fujisawa, Yasuo*; Makanae, Koji*; Yabuki, Nobuyoshi*
Proceedings of 17th International Conference on Computing in Civil and Building Engineering (ICCCBE 2018) (Internet), 8 Pages, 2018/06
This paper presents status of development of the iSRE (integrated system for repository engineering) as a design supporting system that enables rational designing of a geological disposal repository. The complimentary technique of construction information modeling/management (CIM) has been employed for the development of iSRE. CIM uses a shared three dimensional (3D) model of associated data through common data models. In this paper, as a design support system that conforms to the characteristics of information management about engineering technology represented by repetition of design during the disposal project period, we examined and designed the function of the "iSRE", constructed a prototype, and confirmed the function through a trial simulating actual work in the disposal project. As a result, with respect to the functions of DB and IF of the iSRE, we got a prospect that these functions can be the foundation of information management on engineering technology, and development of the prototype of the iSRE and its test run extracted issues for practical use of such system.
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 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.
Osawa, Hideaki; Semba, Takeshi; Makino, Hitoshi
Kankyo Kyoiku, 24(3), p.74 - 90, 2015/03
This paper analyses change of questions on health effect by radiation during six months after Fukushima nuclear accident in terms of time based on an experience of risk communication in the call center of Fukushima prefecture for the accident of Fukushima Daiichi Nuclear Plane. The results show that main questions of the moment underwent a gradual transition from those for acquisition of information on situation of radiation contamination to those for way of acting to measure themselves for escape, decontamination and future health management. These changes may be caused due to progress risk perception, followed by awareness of risk, formation of risk image, estimation of risk and risk control on health effect of radiation in turn. The results also show that the function and method of risk communication required by the moment would undergo a gradual transition according to progress of risk perception.
Asami, Makoto; Watahiki, Hiromi; Oi, Takao; Makino, Hitoshi; Shibata, Atsuhiro; Kameo, Yutaka; Meguro, Yoshihiro; Ashida, Takashi
JAEA-Data/Code 2014-016, 37 Pages, 2014/09
A database on the analyses of samples obtained from contaminated water in the circulating system of Fukushima Daiichi Nuclear Power Station was built. This database contains the analyses of 25 samples of JAEA and 313 samples of TEPCO which have been published in FY 2011 to FY 2013. Also, as well as the analyses on contaminated water, the information on the stored and treated amount in accumulated water and the amount of produced waste, which has been published by TEPCO and which might be required in order to estimate the inventory of secondary waste (sludge, used vessels) generated by treatment of contaminated water are contained in this database. This technical report shows the function of this database and user manual with example and presents the FY2013 edition of database by appendix CD.
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
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.
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 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.
Makino, Hitoshi; Hioki, Kazumasa; Osawa, Hideaki; Semba, Takeshi; Umeki, Hiroyuki
New Research on Knowledge Management Technology, p.165 - 184, 2012/02
The paper will review progress to date of a challenge on development of an advanced Knowledge Management System (KMS) for radioactive waste disposal by JAEA, with emphasis on tailoring of existing knowledge engineering tools and methods to radioactive waste management requirements, and outline future developments and challenges.
Makino, Hitoshi; Umeki, Hiroyuki; Takase, Hiroyasu*; McKinley, I. G.*
Proceedings of 2011 International High-Level Radioactive Waste Management Conference (IHLRWMC 2011) (CD-ROM), p.25 - 31, 2011/04
In the Japanese deep geological disposal programme, the goals of applications of performance assessments (PA) have changed considerably from original generic feasibility demonstrations to site-specific comparison of options that may result from the current call for volunteer communities to host a repository. PA will play a key role to support highly sensitive decisions at main milestones, particular associated with ranking different site and design options. The paper will discuss requirements for next generation PA to play the role and associated R&D needs.
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
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.
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
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.
Kawamura, Makoto; Ebashi, Takeshi; Makino, Hitoshi; Niizato, Tadafumi; Yasue, Kenichi; Inagaki, Manabu; Oi, Takao
Oyo Chishitsu, 51(5), p.229 - 240, 2010/12
Uplift, subsidence, denudation, and sedimentation are phenomena over long-term in a regional scale. It is difficult to ignore the impacts of those phenomena on a disposal system completely in long-term. Therefore, type and extent of the impacts on geological and disposal environmental conditions, and disposal systems need to be evaluated quantitatively in order to develop perturbation scenarios. We have been developing a systematic methodology to develop perturbation scenarios based on the appropriate understanding of those phenomena. The variety of the change of geological environment and evolution pattern of the environment, which are caused by the variation of the uplift, subsidence, denudation, sedimentation phenomena and those rates, are understood by arranging the information in the framework of the thermal-hydrological-mechanical-chemical-geometrical (T-H-M-C-G) system, and the impacts of those environmental change to the performance of the repository system are also examined by using the T-H-M-C-G system. In this study, firstly, the potential changes of the geological environment were identified by examination of possible combinations of the uplift/denudation and subsidence/ sedimentation. The effects of the initial environmental condition are also considered. Geohistorical information and View of Modern analogue theory should be used in this stage. This procedure is essential to set up the scenarios regarding uplift/denudation and subsidence/sedimentation, to clarify the trend and/or range of the change of the geological environmental conditions. Then, the phenomena which give the large impacts to a disposal system were extracted based on the T-H-M-C-G system. By applying the developed framework which deals with the impacts on the HLW disposal system realistic view and builds evaluation scenarios and models based on step wise manner, we acquired the prospect that realistic uplift and denudation scenario could be built to this examination procedure.
Osawa, Hideaki; Hioki, Kazumasa; Makino, Hitoshi; Semba, Takeshi; Umeki, Hiroyuki; Takase, Hiroyasu*
Kenkyu, Gijutsu Keikaku Gakkai Dai-25-Kai Nenji Gakujutsu Taikai Oyobi Sokai Koen Yoshishu (CD-ROM), p.55 - 60, 2010/10
This paper describes new concept of common platform for communication among stakeholders using argumentation model for safety on geological disposal.
Maekawa, Keisuke; Makino, Hitoshi; Kurikami, Hiroshi; Niizato, Tadafumi; Inagaki, Manabu; Kawamura, Makoto*
Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.71 - 80, 2010/10
It is important for establishing safety assessment techniques of HLW geological disposal to understand groundwater flow and solute transport. We have carried out groundwater flow and solute transport analysis using geological and hydrological information from surface-based investigations in the Horonobe area. From this study, a methodology to integrate activities from site investigations and evaluation to solute transport analysis was tested. We have been also carrying out a simulation of groundwater flow and salinity concentration distribution using information on geological evolution considering the impacts of natural events and processes. From the result, we could outline the impacts of natural events and processes on geological environments. We plan to apply a methodology of groundwater flow and solute transport analysis to the shallow part, the Horonobe coastal area. It must be important techniques in support of generic safety assessment for future geologic disposal in Japan.
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
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.
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
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.
Genankyo Dayori, (234), p.11 - 12, 2010/02
This report summarize the contents and outcomes of the QA Workshop that had been hold by JAEA and NSRA to discuss QA in the viewpoint of safety case.
Makino, Hitoshi; Hioki, Kazumasa; Umeki, Hiroyuki; Yang, H.*; Takase, Hiroyasu*; McKinley, I. G.*
Proceedings of 12th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '09/DECOM '09) (CD-ROM), 8 Pages, 2009/10
This paper will outline the reformulation of PA as a Knowledge Management (KM) task, discuss application of knowledge management technologies to PA tasks, and illustrate how these can be handled electronically in a "Performance assessment All-In-one Report System (PAIRS)" utilising hyperlinks and embedded tools to minimise duplication of material, ease Quality Assurance (QA) and facilitate the regular updating required in the Japanese programme.
Makino, Hitoshi; Hioki, Kazumasa; Umeki, Hiroyuki; Tachibana, Shoko*; Takase, Hiroyasu*; McKinley, I. G.*
Proceedings of 12th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '09/DECOM '09) (CD-ROM), 9 Pages, 2009/10
The JAEA Knowledge Management System (KMS) is being developed to be flexible and able to respond to potential changes of boundary conditions. On a shorter timescale, the KMS must encourage flexibility in the methodology used for carrying out and presenting performance assessments. This is closely linked to development of advanced repository concepts; considering the requirements for a safe and practical repository tailored to specific site conditions, which reflects evolving technology. These coupled development tasks were, in the past, carried out by expert teams in a rather informal manner. As the technical challenges increase - and the need for transparency is accepted - a more formal method of developing innovative design solutions is needed. A knowledge engineering approach (TRIZ) that is used in other financial and industrial applications has thus been tested for its usefulness for such tasks.
Mitsui, Seiichiro; Makino, Hitoshi; Inagaki, Manabu; Ebina, Takanori*
Materials Research Society Symposium Proceedings, Vol.1193, p.397 - 404, 2009/05
The results of a sensitivity analysis for long-term glass dissolution taking into account Si release from the glass and its migration through the buffer material are presented to illustrate the impact of this near-field process on the lifetime of the vitrified waste. The lifetime of the glass estimated by the analysis showed a strong dependence on Si diffusion and distribution coefficients in the buffer material and groundwater flow rate in the EDZ. This indicates the significance of these parameters for the long-term evolution of vitrified waste. We also discuss the impact of glass hydration, which proceeds simultaneously with matrix dissolution considering Si release, on the lifetime of the vitrified waste. The results show that glass hydration is less important for the long-term evolution than matrix dissolution in an open system and it can be concluded that Si migration through the buffer material will be an important process for estimating the lifetime of the vitrified waste.