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Journal Articles

Long-term alteration of bentonite; For safety evaluation of deep geological disposal

Tanaka, Tadao; Sakamoto, Yoshifumi; Yamaguchi, Tetsuji; Takazawa, Mayumi; Akai, Masanobu; Negishi, Kumi; Iida, Yoshihisa; Nakayama, Shinichi

JAERI-Conf 2005-007, p.105 - 110, 2005/08

Highly alkaline environments induced by cementitious materials in radioactive waste repositories are likely to dissolve and to alter montmorillonite, the main constituent of bentonite buffer materials. For the prediction of the long-term variations in permeability of compacted sand-bentonite mixtures, long-term alteration of bentonite should be quantified based on information accumulated by using the compacted or powdered bentonite materials, with batch experiments or column experiments. In this study, we summarize distinctive information obtained from various experimental systems, and propose functional and effective integration of experimental approaches to prediction of bentonite alteration.

JAEA Reports

Operation system concept for high-level radioactive wastes disposal facility

*; *; Tanai, Kenji

JNC-TN8400 99-050, 94 Pages, 1999/11

JNC-TN8400-99-050.pdf:3.86MB

This paper reports on the evaluations of operational activities for a High Level Radioactive Wastes Disposal Facility, from initial acceptance of vitrified waste at a surface facility to emplacement engineered barriers in underground facilities. The purpose of this analysis is to confirm the technical feasibility of geological disposal. First, the basic design and repository system requirements are identified. Second, operational activities in surface facilities, access facilities and underground facilities are described. The required procedures and equipment, suitable for specific emplacement concepts and configurations for engineered barrier systems are discussed for specific examples. Countermeasures for potential adverse events or conditions are based on extensive civil engineering and mining experiences in Japan and abroad. The time schedule is also evaluated on the basis of these concepts. In addition, the concept of stationary and mobile radiation control areas is studied based on experiences and practice in current nuclear facilities. Finally future research and development items are summarized.

JAEA Reports

None

; ; Shimizu, Kazuhiko; Miyahara, Kaname; ; Hasegawa, Hiroshi; Iwasa, Kengo

JNC-TN1400 99-008, 656 Pages, 1999/04

JNC-TN1400-99-008.pdf:34.68MB

None

JAEA Reports

None

Toyohara, Masumitsu*; Hirayama, Fumio*; Tamura, Toshiyuki*; Fukazawa, Takuji*; Igarashi, Noboru*

PNC-TJ8164 96-010, 213 Pages, 1996/03

PNC-TJ8164-96-010.pdf:7.67MB

no abstracts in English

Journal Articles

Environmental monitoring of tritium around radioactive waste disposal area; Analysis of tritium movement in a forest

Amano, Hikaru

Proc. of the 5th Int. Seminar for Liquid Scintillation Analysis, p.55 - 76, 1993/00

no abstracts in English

JAEA Reports

Thermal and Mechenical Effects of the High-Level Waste on the Deep Underground Rock Mass

; *; *; *; ; ;

JAERI-M 83-040, 55 Pages, 1983/03

JAERI-M-83-040.pdf:1.55MB

no abstracts in English

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