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Journal Articles

Tritium experience in JT-60 operation

Oikawa, Akira; Miya, Naoyuki

Purazuma, Kaku Yugo Gakkai-Shi, 78(12), p.1308 - 1312, 2002/12

Tritium experience over decade in DD operation of JT-60 is summarized.Effluent of tritium in vacuum exhaust through the stack to environment always remains a level below detectable levels. Tritium concentration of drain is also below the limit of regurations of the local agreement amd the law. For a scheduled maintenance work of the in-vessel components, following an annual deuterium plasma discharge campaign, a 4-week no-deuterium plasma discharge campaign and the succeeded ventilation by room air allow to reduce tritium concentration on the surface of in-vessel components. A cooperative endeavour is underway for analysis of tritium behavior in JT-60.

Journal Articles

Experience of clean-up activities and feedback to future D&D projects; Japan Power Demonstration Reactor decommissioning project

Yanagihara, Satoshi; Tachibana, Mitsuo; Shimada, Taro; Sukegawa, Takenori; Shiraishi, Kunio

8th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '01), Vol.2, p.1247 - 1251, 2001/10

In the Japan Power Demonstration Reactor (JPDR) decommissioning project, the procedure for clean-up activities was specially studied for harmonization with radioactive waste treatment policy in Japan; it consisted of several components such as survey of the facility operational history, radiological characterization of building surfaces, decontamination and final survey of radioactivities. After confirming that there was no significant radioactivity in the facilities in the final step of the procedure, buildings were demolished in consideration of treatment of wastes as non-radioactive materials. The JPDR decommissioning project was completed by March 1996 with no serious problems, which showed that the procedure was rational, and that the experiences are useful for planning of future decommissioning activities. The dismantling and clean-up activities were reviewed, and the experiences are excepted to contribute to establishing standard and regulatory systems on decommissioning nuclear facilities.

JAEA Reports

GARDEC; A Computer code for estimating dose-rate reduction by garden decontamination

Togawa, Orihiko

JAERI-Data/Code 98-038, 21 Pages, 1998/12

JAERI-Data-Code-98-038.pdf:1.13MB

no abstracts in English

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