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Takada, Tsuyoshi
Nihon Jishin Kogakkai-Shi, (44), p.6 - 11, 2021/10
This report describes the status of nuclear seismic safety assurance in Japan before 2007, followed by the background and main achievements of the activities of the three research committees in collaboration with the Japan Association for Earthquake Engineering (JAEE) and the Atomic Energy Society of Japan (AESJ), and finally a summary of the points that the author considers important as the end of these activities.
Minato, Kazuo
Hokeikyo Nyusu, (56), P. 1, 2015/10
The number of students who study nuclear engineering decreased after the accident at the Fukushima Dai-ichi Nuclear Power Station. Securing human resources and their development should be strongly promoted in cooperation with universities, industry, and research institutes since the universities hardly maintain and operate their nuclear facilities.
Nakajima, Norihiro; Miyamura, Hiroko; Kawakami, Yoshiaki; Kawamura, Takuma
Kashika Joho Gakkai-Shi, 35(Suppl.1), p.233 - 238, 2015/07
no abstracts in English
Hidaka, Akihide; Suzuki, Masahide
JAERI-Conf 2003-014, 178 Pages, 2003/09
JAERI-Conf-2003-014.pdf:19.17MB
The Workshop on Reactor Safety Research focusing on the integrity of aged components was held at the Tokai Research Establishment on March 17, 2003. The purpose of the Workshop was to obtain useful information to proceed with the reactor safety research in future and to resolve the issues on the integrity evaluation of aged components through the discussions followed by the presentations on the results of the research at JAERI on all the research subjects assigned to JAERI in the Five-Year Program of Safety Research for Nuclear Installations established by the Nuclear Safety Commission, and on those of the studies at JAERI on the integrity of core shrouds of BWR plants. Thirty-eight people from outside JAERI including the press such as Nihon Television Network Corporation and Shin-Ibaraki Shinbun and fifty-seven people from JAERI attended the Workshop. This proceeding compiles all the viewgraphs presented in the workshop, the opinions of participants for forum and the answers, and summary of questionnaire on workshop.
Sakurai, Kiyoshi; Yamamoto, Toshihiro
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.202 - 214, 2003/06
Monte Carlo Working Group of Special Committee on Nuclear Code Evaluation at JAERI investigated present status of application of Monte Carlo Calculation for large nuclear facilities in Japan. Application of Monte Carlo method has already been popular even to large facilities, but the calculated results are not compared with measured datain most of those applications. The authors believe that accuracy and precision of the method should be examined through comparisons with measured data, and that databases of measured data at experimental or commercial facilities should be developed for further comparison with the analysis results.
Shimada, Taro; Sukegawa, Takenori; Yanagihara, Satoshi; Sato, Tadamichi*; Sakai, Shinichi*
Proceedings of 9th Biennial International Conference on Nuclear and Hazardous Waste Management (Spectrum '02) (CD-ROM), 6 Pages, 2002/08
no abstracts in English
Kobayashi, Kaoru*; Kaminaga, Masanori; Haga, Katsuhiro; Kinoshita, Hidetaka; Aso, Tomokazu; Hino, Ryutaro
JAERI-Review 2002-010, 52 Pages, 2002/05
JAERI-Review-2002-010.pdf:3.38MB
no abstracts in English
Tanai, Kenji; Horita, M.*; Dewa, Katsuyuki*; Goke, Mitsuo*
JNC TN8410 2001-026, 116 Pages, 2002/03
JNC-TN8410-2001-026.pdf:9.19MB
Earthquake resistance for the underground structure is higher than the ground structure. Therefore, the case of examining the earthquake resistance of underground structure was little. However, it carries out the research on the aseismic designing method of underground structure, since the tunnel was struck by Hyogo-ken Nanbu Earthquake, and it has obtained a much knowledge. However, an object of the most study was behavior at earthquake of the comparatively shallow underground structure in the alluvial plain board, and it not carry out the examination on behavior at earthquake of underground structure in the deep rock mass. In the meantime, underground disposal facility of the high level radioactive waste constructs in the deep underground, and it carries out the operation in these tunnels. In addition, it has made almost the general process of including from the construction start to the backfilling to be about 60 years (Japan Nuclear Fuel Cycle Development Institute, 1999). During these periods, it is necessary to also consider the earthquake resistance as underground structure from the viewpoint of the safety of facilities. Then, it extracted future problem as one of the improvement of the basis information for the decision of the safety standard and guideline of the country on earthquake-resistant design of the underground disposal facility, while it carried out investigation and arrangement of earthquake-resistant design cases, guidelines and analysis method on existing underground structure, etc.. And, the research item for the earthquake resistance assessment of underground structure as case study of the underground research laboratory.
; ; 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.
Matsuzuru, Hideo
Nihon Gakujutsu Kaigi Kohaishita Seikatsu Kankyo No Sentan Gijutsu Ni Yoru Kaifuku Kenkyu Renrakukai Iinkai Shimpojiumu "Hoshasei Busshitsu Ni Yoru Kankyo Osen No Yobo Ni Mukete", p.53 - 62, 2002/00
no abstracts in English
JNC TN1400 2001-015, 509 Pages, 2001/10
JNC-TN1400-2001-015.pdf:25.67MB
no abstracts in English
; ; ; Omori, Eiichi
JNC TN8410 2001-021, 33 Pages, 2001/09
JNC-TN8410-2001-021.pdf:4.37MB
Carbon-14 released from the nuclear facilities is an important radionuclide for the safety assessment, because it tends to accumulate in environment through food chain and has as a significant impact to personal dose. Carbon-14 has been monitored routinely as one of the main gaseous radionuclides exhausted from the Tokai Reprocessing Plant (TRP) since OCtober of 1991. Furthermore, behavior of carbon-14 in TRP has been investigated through the reprocessing operation and the literature survey. This report describes the result of investigation about the behavior of carbon-14 in TRP as followings. (1)Only a very small amount of carbon-14 in the fuel was liberated into the shear off-gas and most of it was liberated into the dissolver of-gass. Part of the carbon-14 was trapped at the caustic scrubber installed in the of-gas treatment process, and untrapped carbon-14 was released into the environment from the main stack. Amount of carbon-14 released from the main stack was about 4.1
6.5GBq every ton of uranium reprocessed. (2)Carbon-14 trapped at the caustic scrubbers installed in the dissolver off-gas and in the vessel off-gas treatment process is transferred to the low active waste vessel. Amount of carbon-14 transferred to the low active waste vessel was about 5.4 9.6GBq every ton of uranium reprocessed. (3)The total amount of carbon-14 input to TRP was summed up to about 11.915.5 GBq every ton of uranium reprocessed considering the released amount from the main stack and the trapped amount in the off-gas treatment devices. The amount of nitrogen impurity in the initial fuel was calculated about 1522ppm of uranium metal based on the measured carbon-14. (4)The solution in the low active waste vesselis concentrated at the evaporator.Most of the carbon-14 in the solution was transferred into concentrated solution. (5)Tokai vitrification Demonstration Facility (TVF) started to operate in 1994. Since then, carbon-14 has been measured in the ...
Shimada, Taro; Tachibana, Mitsuo; Yanagihara, Satoshi
JAERI-Tech 2001-060, 44 Pages, 2001/09
JAERI-Tech-2001-060.pdf:5.11MB
To evaluate aerosol diffusion behaviors under dismantling of nuclear facilities, plasma arc cuttings were conducted in the enclosure. The flow of air and high temperature gas in the enclosure were visualized, and the temperature distributions in the enclosure and the aerosol number and weight density in air of outlet flow were measured in the experiments. As a result, it was confirmed that ascending high temperature gas flow produced by the plasma arc is corresponded with aerosol diffusion behavior during cutting. It was also confirmed that after completing the cuttings the aerosol tends to fall due to decreasing of flow velocity of high temperature gas and the aerosol which reaches near the floor is resuspended by relatively high velocity exhaust flow.
Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi
Nihon Robotto Gakkai-Shi, 19(6), p.706 - 709, 2001/09
no abstracts in English
Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi
Gekkan Shobo, 23(6), p.22 - 26, 2001/06
no abstracts in English
Matsunaga, Takeshi; Kobayashi, Kensuke
Hoken Butsuri, 36(1), p.31 - 44, 2001/03
no abstracts in English
Noda, Kimio; Shinohara, Kunihiko; Kanamori, Masashi
JNC TN8410 2001-010, 35 Pages, 2000/10
JNC-TN8410-2001-010.pdf:3.85MB
We, the radiation control section of JNC have had two important experiences on the JCO critical accident and the JNC fire-explosion accident. Especially, at the critical accident in JCO, it was essential to take an action on the radiation protection activities for the evacuated neighboring inhabitants to the safety area. During the accident, we carried out the radiation protection activities, at the beginning of the accident, environmental monitoring of the surrounding area. Especially for the JCO accident, we took an action to terminate criticality, radiation shielding and monitoring, environmental monitoring, radiation survey of the residents, radiation monitoring of exhaust air.
March, 2000); Shinohara, Kunihiko; ; ; ; Isozaki, Tokuju; ; *
JNC TN8440 2000-003, 93 Pages, 2000/08
The investigation on the radioactivity concentration for gross beta, 
H and 
Cs in seawater collected around the discharge point had been performed in order to grasp the change of the activity level of the coastal seawater offshore the JNC Tokai Works from the low level liquid effluent of the reprocessing plant. After the investigation on the radioactivity in seawater during the hot examination, the detailed investigation on the environmental effects from the liquid effluent of JNC reprocessing plant has been performed since July 1978 on the basis of the request from Ibaraki prefecture as the full-scale operation of the reprocessing plant. Consequently, no increase of the radioactive concentration due to the discharged effluent has been observed. And also, as the result of the consideration to the investigation on the environmental effect from the liquid effluent throughout 22 years since 1978, no change of the radioactive concentration level in seawater was recognized.
