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Konishi, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 78(11), p.1157 - 1164, 2002/11
Based on the fundamental approach for safety of ITER, possible extension to assure safety of fusion power plant was considered. Although the entire analysis and licensing preparation are specific for ITER, its methodology that take full advantage of inherent feature of fusion is expected to be applied to fundamental logic of fusion power plant. Both energy and radioactive source terms that could be potential hazards are typically of order of days of operation rather than a year in the case of fission. Major difference from the test reactor ITER identified was power blanket, coolant loop and generator train that will hold high temperature and considerable amount of tritium. It is anticipated that tritium inventory and most of the tritium safety plant would essentially be same as ITER, tritium recovery and removal from blanket loop will dominate the fusion power plant tritium systems. Such a tritium system will actively remove tritium at the daily throughput comparable with the order of plant inventory. This feature suggest no dedicated off-normal systems are needed to assure safety of fusion plant from the aspect of environmental tritium release.
Kakehi, Isao; Nakabayashi, Hiroki
JNC TN9400 2000-051, 237 Pages, 2000/04
JNC-TN9400-2000-051.pdf:8.14MB
In this study, we have proposed the concept of safety systems (solutions of safety problems) in pyrochemical reprocessing systems (lt consists of pyrochemical reprocessing methods and the injection casting process for the metal fuel fabrication, or vibro-packing process for the oxide fuel fabrication.) which has different concept from the existing PUREX reprocessing method and pellet fuel fabrication process. And we performed its safety evaluations. FoIlowing the present Japanese safety regulations for reprocessing facilities, we pointed out functions, design requirements and equipments relating to its safety systems and picked up subjects. For the survey of safety evaluations, we first selected anticipated events and accident events, and second by evaluated 6the correspondence of the limitation of the public exposure to the accidents above, by using two parameters, the safety design parameter (the filter performance to confine radioactive matelials) and the leak inventory of radioactivities, and last by picked up its problems. ln addition to the above evaluations we performed basic criticality analyses for its systems to utilize these results for the design and evaluation of the criticality safety management system. Thus this study specified the concept of safety systems for pyrochemical reprocessing processes and then issues in order to establish safety design policies (matters which must consider for the safety design) and guides and to advance more definite safety design.
JNC TN1400 2000-001, 371 Pages, 2000/01
JNC-TN1400-2000-001.pdf:12.26MB
no abstracts in English
Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime
Nihon Kikai Gakkai Kansai Shibu Dai-75-ki Teiji Soukai Koenkai Koen Rombunshu, p.13_11 - 13_12, 2000/00
no abstracts in English
Matsumoto, Kiyoshi; *; Tanabe, Fumiya
JAERI-M 90-210, 222 Pages, 1990/11
no abstracts in English
