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; ; Yamazaki, Toshihiko; ; ; Kondo, Toshinari*; *
JNC TN8400 2001-030, 99 Pages, 2002/01
JNC-TN8400-2001-030.pdf:13.24MB
There is a great deal of that we build a Base-Isolated building with the quaternary deposit ground. In an atomic energy institution, a study request is strong. When we build a Base-Isolated building with the quaternary deposit ground, evaluation of earthquake vibration of a vertical direction is an important problem. In an atomic energy institution, we design it by big earthquake load, and therefore examination is necessary. And, in this study, we do examination to build a Base-Isolated building with the quaternary deposit ground, we report it about an evaluation method of a design. Furthermore, we report that we estimated pipe laying and machinery to put in a building of Base-lsolated.
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.
Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; Sudo, Toshiyuki; Hayashi, Shinichiro;
JNC TN8410 2000-006, 116 Pages, 2000/04
JNC-TN8410-2000-006.pdf:2.77MB
Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.
Kurihara, Ryoichi; Seki, Yasushi; Ueda, Shuzo; Aoki, Isao; Nishio, Satoshi; Ajima, Toshio*; Kunugi, Tomoaki; Takase, Kazuyuki; Yamauchi, Michinori*; *; et al.
Journal of Fusion Energy, 16(3), p.225 - 230, 1997/00
Times Cited Count：3 Percentile：30.37(Nuclear Science & Technology)no abstracts in English
; ; ; ; Kano, Yutaka
PNC TN8420 96-017, 50 Pages, 1996/08
The meteorological observation has been performed since 1955 in PNC Tokai-works. After 1974, this observation came to measure on the top of the meteorological tower (100m above sea level) for the environmental assessment of a radioactive waste with the atmospheric discharge from the reprocessing plant. This report presents an atmospheric phenomenon statistic result and an examination about a characteristic of the atmosphere diffusion based on the data from 1977 to 1995. Characteristics of the result are as follows; (1)It was confirmed that the maximum air concentration point that was calculated based on the discharge amount from reprocessing plant and atmospheric phenomenon statistic of each year appears at near point in the safety assessment of 1977. (2)In some case, a maximum concentration point has appeared at about 800m in the west-southwest direction owing to the deference of appearance frequency of the atmospheric stability, etc. Normally it appears at about 2,000m point in south-west direction. Still, as reference materials, atmospheric phenomenon statistics result and relative concentration were mentioned.
Toyohara, Masumitsu*; Hirayama, Fumio*; Tamura, Toshiyuki*; Fukazawa, Takuji*; Igarashi, Noboru*
PNC TJ8164 96-010, 213 Pages, 1996/03
no abstracts in English
Katakura, Junichi
Nihon Genshiryoku Gakkai-Shi, 38(7), p.609 - 615, 1996/00
Times Cited Count：1 Percentile：14.44(Nuclear Science & Technology)no abstracts in English
; Hino, Ryutaro; Inagaki, Yoshiyuki; Takase, Kazuyuki; Ioka, Ikuo; Takada, Shoji; Suzuki, Kunihiro; Kunitomi, Kazuhiko; Maruyama, So;
JAERI 1333, 196 Pages, 1995/03
no abstracts in English
Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shindo, Masami; Shiozawa, Shusaku; Mogi, Haruyoshi; Okubo, Minoru; Ito, Noboru; Shindo, Ryuichi; et al.
JAERI 1332, 247 Pages, 1994/09
no abstracts in English
Tsujino, Takeshi; Takeshita, Isao; Izawa, Naoki;
Topical meeting,Safety of the Nuclear Fuel Cycle, 0, p.124 - 137, 1994/00
no abstracts in English
Yanagisawa, Hiroshi; Takeshita, Isao
Robutsuri No Kenkyu, (41), p.53 - 56, 1992/03
no abstracts in English
; *
LA-9911-C,Vol.1, p.21 - 29, 1983/00
no abstracts in English
Shiba, Koreyuki; ; ; ; ; Tanifuji, Takaaki; ; *
JAERI-M 5511, 40 Pages, 1974/01
no abstracts in English
