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Journal Articles

Nuclear facilities and human resource development

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.

Journal Articles

Analyses for designing objects in mechanical design

Nakajima, Norihiro; Miyamura, Hiroko; Kawakami, Yoshiaki; Kawamura, Takuma

Kashika Joho Gakkai-Shi, 35(Suppl.1), p.233 - 238, 2015/07

no abstracts in English

JAEA Reports

Proceedings of the Workshop on Reactor Safety Research, Focusing on the Integrity of Aged Components; March 17, 2003, Tokai Research Establishment, Tokai-mura

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.

Journal Articles

Present status of application of Monte Carlo calculation for large nuclear facilities in Japan

Sakurai, Kiyoshi; Yamamoto, Toshihiro

Nippon 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.

Journal Articles

Development of computer programs for occupational doses estimation in dismantling of nuclear facilities

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

JAEA Reports

Investigation of safety concept of spallation neutron source

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

JAEA Reports

The Arrangement of the seismic design method of the underground facility

Tanai, Kenji; Horita, M.*; *; 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.

JAEA Reports

A Study of structure of base-isolated

; ; ; ; ; 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.

Journal Articles

Measurement, monitoring and prevention of environmental contamination with radioactive substances

Matsuzuru, Hideo

Nippon 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

JAEA Reports

None

JNC-TN1400 2001-015, 509 Pages, 2001/10

JNC-TN1400-2001-015.pdf:25.67MB

no abstracts in English

JAEA Reports

Behavior of carbon-14 in the Tokai reprocessing plant

; ; ;

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$$sim$$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$$sim$$ 9.6GBq every ton of uranium reprocessed. (3)The total amount of carbon-14 input to TRP was summed up to about 11.9$$sim$$15.5 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 15$$sim$$22ppm 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 ...

JAEA Reports

Study of aerosol diffusion behaviors in dismantling nuclear facilities (Contract research)

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.

Journal Articles

Development of robots for nuclear accident in Japan Atomic Energy Reserch Institute, 1; Development of remote surveillance squad

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Nippon Robotto Gakkai-Shi, 19(6), p.706 - 709, 2001/09

no abstracts in English

JAEA Reports

None

; *

JNC-TN8200 2001-005, 54 Pages, 2001/08

JNC-TN8200-2001-005.pdf:5.85MB

None

Journal Articles

Development of remote surveillance squad

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Gekkan Shobo, 23(6), p.22 - 26, 2001/06

no abstracts in English

Journal Articles

Sensitivity analysis on the deposition of inhaled radioactive iodine and the effectiveness of iodine prophylaxis

Matsunaga, Takeshi; Kobayashi, Kensuke

Hoken Butsuri, 36(1), p.31 - 44, 2001/03

no abstracts in English

JAEA Reports

None

; *; *

JNC-TN8200 2001-001, 42 Pages, 2001/01

JNC-TN8200-2001-001.pdf:3.16MB

None

JAEA Reports

Some experiences of radiation protection activities in nuclear emergency

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.

JAEA Reports

Detailed investigation on the environmental effects from the liquid effluent of JNC reprocessing plant (IV); (April, 1996$$sim$$March, 2000)

; Shinohara, Kunihiko; ; ; ; Isozaki, Tokuju; ; *

JNC-TN8440 2000-003, 93 Pages, 2000/08

JNC-TN8440-2000-003.pdf:2.2MB

The investigation on the radioactivity concentration for gross beta, $$^{3}$$H and $$^{137}$$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.

Journal Articles

Sensitivity analysis on the effectiveness of iodine prophylaxis to reduce thyroid gland exposure in nuclear emergency

Matsunaga, Takeshi; Kobayashi, Kensuke

Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 10 Pages, 2000/05

no abstracts in English

154 (Records 1-20 displayed on this page)