Summary results of subsidy program for the "Project of Decommissioning and Contaminated Water Management (Development of Analysis and Estimation Technology for Characterization of Fuel Debris (Development of Technologies for Enhanced Analysis Accuracy and Thermal Behavior Estimation of Fuel Debris))"

Koyama, Shinichi; Nakagiri, Toshio; Osaka, Masahiko; Yoshida, Hiroyuki; Kurata, Masaki; Ikeuchi, Hirotomo; Maeda, Koji; Sasaki, Shinji; Onishi, Takashi; Takano, Masahide; et al.

Hairo, Osensui Taisaku jigyo jimukyoku Homu Peji (Internet), 144 Pages, 2021/08

https://dccc-program.jp/3797

JAEA performed the subsidy program for the "Project of Decommissioning and Contaminated Water Management (Development of Analysis and Estimation Technology for Characterization of Fuel Debris (Development of Technologies for Enhanced Analysis Accuracy and Thermal Behavior Estimation of Fuel Debris))" in 2020JFY. This presentation summarized briefly the results of the project, which will be available shortly on the website of Management Office for the Project of Decommissioning and Contaminated Water Management.

Detaching test on an irradiated mock-up contaminated with tritium from the core of JMTR

Tomita, Kenji; Tsuchiya, Kunihiko; Onuma, Yuichi; Inoue, Shuichi; Watanabe, Hiroyuki; Saito, Takashi; Kikuchi, Taiji; Hayashi, Kimio; Kitajima, Toshio

JAEA-Technology 2008-036, 61 Pages, 2008/06

JAEA-Technology-2008-036.pdf:7.47MB

The second in-situ irradiation experiment using a mock-up (ORIENT-II, JMTR capsule Number: 99M-54J) with a tritium breeder (LiTiO) pebble bed in the Japan Materials Testing Reactor (JMTR) was finished on Aug. 1, 2006. Consideration on the detaching procedure of the irradiated mock-up contaminated with tritium with pebble bed and a detaching test of this mock-up was carried out. The tritium removal properties were examined in the irradiated mock-up, the sweep gas tube, the protective tube and the junction box, for the decreasing of the tritium release to the area of detaching test. Melting/enclosed tests of sealing plug were also carried out for the prevention of tritium leakage from sweep gas lines of pebble bed. Then, the detaching test of the pebble bed was carried out. This report describes the results of tritium removal tests, examination of the detaching procedure, and the detaching test, as well as knowledge obtained from these tests and works.

Investigation of the long term corrosion resistance of the overpack (Contract research)

Tachikawa, Hirokazu*; Kawakubo, Fumie*; Shimizu, Akihiko*; Shibata, Toshio*; Sugimoto, Katsuhisa*; Seo, Masahiro*; Tsuru, Toru*; Fujimoto, Shinji*; Inoue, Hiroyuki*

JAEA-Research 2006-058, 80 Pages, 2006/10

JAEA-Research-2006-058.pdf:10.86MB

The Japan Nuclear Cycle Development Institute submitted "Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan" to the Japanese government. This report contains investigations of the corrosion life time of the overpack on the basis of experimental data and past research, assuming the ranging geological environment of Japan. However some subjects, such as the behavior of the overpack under high pH conditions and the behavior of the engineering barrier with change of near-field environmental condition with time for promoting reliability have still been left. To take into account these conditions, expert committee composed of metal corrosion science experts were established in the Nuclear Safety Research Association and past research outcomes and the theory of safety assessment were investigated from the view points of long term stability and corrosion resistance of engineering barrier.

Development of the corrosion models for the analysis of candidate materials for overpacks

Shibata, Toshio*; *; *; Tsuru, Toru*; Inoue, Hiroyuki*; *

JNC TJ8400 2002-059, 139 Pages, 2003/02

JNC-TJ8400-2002-059.pdf:7.07MB

A technical committee was organized in Japan Society of Corrosion Engineering (JSCE) to review and assess the study of overpack in JNC. The corrosion models for candidate materials for overpacks were developed in terms of corrosion science to contribute the selection of material, establishment of experimental methods and lifetime prediction of overpacks. It is expected that this report is used for the study of overpacks in the process of the research and development of high-level radioactive waste disposal.

Development of the corrosion models for the analysis of candidate materials for overpacks

Shibata, Toshio*; *; *; Tsuru, Toru*; Inoue, Hiroyuki*

JNC TJ8400 2001-008, 94 Pages, 2001/02

JNC-TJ8400-2001-008.pdf:2.05MB

A technical committee was organized in Japan Society of Corrosion Engineering to review and assess the study of overpacks in JNC. The corrosion models for candidate materials for overpaks were developed in terms of corrosion science to contribute the selection of material, establishment of experimental methods and life prediction of overpacks. It is expected that this report is used for the study of overpacks in the process of the research and development of high-level radioactive waste disposal.

Development of superconducting linac for the KEK/JAERI joint project

Ouchi, Nobuo; Mizumoto, Motoharu; Kusano, Joichi; Chishiro, Etsuji; Hasegawa, Kazuo; Akaoka, Nobuo*; Saito, Kenji*; Noguchi, Shuichi*; Kako, Eiji*; Inoue, Hitoshi*; et al.

Proceedings of 20th International Linac Conference (CD-ROM), 1 Pages, 2000/00

no abstracts in English

Study of the management of hull wastes (VI)

Sawada, Yoshihisa*; Komatsu, Fumiaki*; Takagi, Yuji*; Mizoguchi, Takao*; Kobayashi, Masato*; Inoue, Takao*; Iwata, Toshio*; Wada, Ryutaro*

PNC TJ4058 88-004, 259 Pages, 1988/07

PNC-TJ4058-88-004.pdf:16.99MB

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