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Featured researches published by Morimasa Naito.


Journal of Energy | 2018

Public Acceptance as a Driver for Repository Design

Ian G. McKinley; Sumio Masuda; Susie M.L. Hardie; Hiroyuki Umeki; Morimasa Naito; Hiroyasu Takase

The Japanese geological disposal programme for radioactive waste is based on a volunteering approach to siting, which places particular emphasis on the need for public acceptance. This, as established in law, emphasises the development of a repository project as a partnership with local communities and involves stakeholders in important decisions associated with key milestones in the selection of repository sites and subsequent construction, operation, and closure. To date, however, repository concept development has proceeded in a more traditional manner, focusing particularly on ease of developing a post-closure safety case. In the current project, we have attempted to go further by assessing what requirements stakeholders would place on a repository and assessing how these could be used to rethink repository designs so that they meet the desires of the public without compromising critical operational or long-term safety.


18th International Conference on Nuclear Engineering: Volume 1 | 2010

Development of Superfine Spherical Silica Grout as an Alternative Grouting Material for the Geological Disposal of Long-Lived Radioactive Waste

Morimasa Naito; Hirokazu Kishi; Naomi Fukuoka; Tsutomu Yamada; Hideaki Ishida

As an alternative grouting material for the geological repository of long-lived radioactive waste, the “S uperf ine S pherical silica G rout” (SFSG) material is developed using a fine spherical silica and a fine calcium hydroxide. The developed SFSG material takes an advantage of its smaller particle size distribution (max. ∼1 micron or less) than those of the cementitious materials, and also provides a low alkaline environment so as to reduce unfavorable effects on the long-term performance of geological disposal system. The SFSG is a mixture of the “super fine silica powder”, the superfine calcium hydroxide and additives such as superplasticizer. Presently, the mixture being investigated for grouting materials is focused on water/binder ratio (W/B) of 1.2. Some preliminary laboratory experiments were carried out to characterize its fundamental properties from the viewpoint of practical use for geological disposal, which is required to be equivalent with the conventional cementitious materials in terms of penetrability, strength, pH performance and workability. From a series of experiments, it was concluded that SFSG is expected to become an alternative grouting material for a geological repository.Copyright


ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 1 | 2009

Evaluation of Mechanical Effects of the Fault Movement on the Engineered Barrier System

Yuya Saito; Mayuka Nishimura; Takashi Hirai; Kenji Tanai; Morimasa Naito

Experiments and numerical analyses have been conducted to investigate the consequences of an active fault crosscutting the engineered barrier system (EBS) of a high-level radioactive waste (HLW) repository. Experiments were performed using laboratory simulation test equipment at a scale of 1:20, which can simulate the chosen shear displacements of 80% and 140% of the buffer thickness, and the chosen shear rates of 0.1 m/s, 0.05 m/s and 0.01 m/s. The experiments have so far demonstrated that the metal overpack will be rotated, but not breached, due to the plasticity of the surrounding bentonite buffer. The total pressure on the bentonite buffer increases with an increase in the shear rate. Numerical analyses were carried out using a finite element method assuming the constitutive model of modified Cam-clay, which was used to assess elasto-plastic behavior of the bentonite buffer.Copyright


Nuclear Engineering and Technology | 2006

KEY R&D ACTIVITIES SUPPORTING DISPOSAL OF RADIOACTIVE WASTE: RESPONDING TO THE CHALLENGES OF THE 21ST CENTURY

Yoichi Miyamoto; Hiroyuki Umeki; Hideaki Ohsawa; Morimasa Naito; Katsushi Nakano; Hitoshi Makino; Kazuhiko Shimizu; Toshihiro Seo


Archive | 2007

Concept and Design of the JAEA KMS for Geological Disposal of HLW

Hitoshi Makino; Hideaki Osawa; Katsushi Nakano; Morimasa Naito; Hiroyuki Umeki; Hiroyasu Takase; Ian G. McKinley


MRS Proceedings | 2002

An Overview of the H12 Performance Assessment in Perspective

Kaname Miyahara; Hitoshi Makino; Tomoko Kato; Keiichiro Wakasugi; Atsushi Sawada; Yuji Ijiri; Aki Takasu; Morimasa Naito; Hiroyuki Umeki


Journal of Nuclear Fuel Cycle and Environment | 2012

Characteristic evaluation of colloidal silica grout material developed for a high level radioactive waste geological repository

Hirokazu Kishi; Masanao Kawaguchi; Morimasa Naito; Koichiro Hatanaka; Jun Nobuto; Hirokazu Sugiyama


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2011

ICONE19-43532 MIX DESIGN OF LOW pH CEMENT SHOTCRETE IN HIGH LEVEL RADIOACTIVE WASTE REPOSITORIES

Akira Noguchi; Hirokazu Kishi; Koichiro Hatanaka; Morimasa Naito


Journal of Power and Energy Systems | 2009

Experimental Study on the Effects of Fault Movement on the Engineered Barrier System

Morimasa Naito; Yuya Saito; Kenji Tanai; Mikazu Yui


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2007

ICONE15-10204 ESTABLISHING PRIORITIES FOR HLW R&D IN THE 21^ CENTURY

Hiroyuki Umeki; Morimasa Naito; Hitoshi Makino; Hideaki Osawa; Katsushi Nakano; Yoichi Miyamoto; Ian G. McKinley

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Hiroyuki Umeki

Nuclear Waste Management Organization

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Hitoshi Makino

Japan Atomic Energy Agency

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Kazuhiko Shimizu

Japan Nuclear Cycle Development Institute

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Aki Takasu

Japan Nuclear Cycle Development Institute

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Hirokazu Kishi

Japan Atomic Energy Agency

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Hideaki Osawa

Japan Atomic Energy Agency

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Kenji Tanai

Japan Atomic Energy Agency

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Koichiro Hatanaka

Japan Atomic Energy Agency

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