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Journal Articles

Development of a design support system for geological disposal of radioactive waste using a CIM concept

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.

JAEA Reports

Investigation of the site selection examples adopted local participation; The Site selection processes in Belgium, UK and Switzerland

Kageyama, Hitoshi; Suzuki, Shinji; Hirose, Ikuro; Yoshioka, Tatsuji

JAEA-Review 2014-019, 79 Pages, 2014/06

JAEA-Review-2014-019.pdf:9.93MB

In late years, local participation policies are being adopted in foreign countries at site selection for the disposal of the radioactive waste. We performed documents investigation about the examples of the site selection processes of Belgium, the U.K., and Switzerland to establish the site selection policy in Japan. Reviewing the merits and demerits of each example through this investigation, we confirmed if we are to adopt local participation policy in our country in future, further prudent study would be necessary, considering current and future social conditions in Japan.

JAEA Reports

The Conceptual Design of Waste Repository for Radioactive Waste from Medical, Industrial and Research Facilities Containing Comparatively High Radioactivity III (Summary Report)

Kageyama, Hitoshi*; Akahori, Kuniaki*

JNC TJ8400 2003-085, 82 Pages, 2004/02

JNC-TJ8400-2003-085.pdf:0.72MB

Advisory Committee on Nuclear Fuel Cycle Backend Policy reported the basic approach to the RI and Institute etc. wastes on March 2002. According to it, radioactive waste form medical, industrial and research facilities should be classified by their radioactivity properties and physical and chemical properties, and should be disposed in the appropriate types of repository with that classification. For the radioactive waste containing comparatively high radioactivity generated from reactors, NSC has established the Concentration limit for disposal. NSC is now discussing about the limit for the radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity. Japan Nuclear Cycle Development Institute (JNC) has studied about the feasibility and the cost of the disposal for radioactive waste from medical, industrial and research facilities. This study was started to renew to latest data of the radioactive waste. And at the point of shielding from radiation, the waste was categorized by activity of nuclide in waste container. Th

JAEA Reports

The Conceptual Design of Waste Repository for Radioactive Waste from Medical, Industrial and Research Facilities Containing Comparatively High Radioactivity III

Kageyama, Hitoshi*; Akahori, Kuniaki*

JNC TJ8400 2003-084, 206 Pages, 2004/02

JNC-TJ8400-2003-084.pdf:3.38MB

Advisory Committee on Nuclear Fuel Cycle Backend Policy reported the basic approach to the RI and Institute etc. wastes on March 2002. According to it, radioactive waste form medical, industrial and research facilities should be classified by their radioactivity properties and physical and chemical properties, and should be disposed in the appropriate types of repository with that classification. For the radioactive waste containing comparatively high radioactivity generated from reactors, NSC has established the Concentration limit for disposal. NSC is now discussing about the limit for the radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity. Japan Nuclear Cycle Development Institute (JNC) has studied about the feasibility and the cost of the disposal for radioactive waste from medical, industrial and research facilities. This study was started to renew to latest data of the radioactive waste. And at the point of shielding from radiation, the waste was categorized by activity of nuclide in waste container. Then the safety assessment and the prediction of cost of the disposal performed.

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