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Journal Articles

Visualization of distribution of shear stress due to water vortex flow with SSLCC

Okazaki, Soichiro*; Ezure, Toshiki; Ohshima, Hiroyuki; Kawara, Zensaku*; Yokomine, Takehiko*; Kunugi, Tomoaki*

Proceedings of 10th Pacific Symposium on Flow Visualization and Image Processing (PSFVIP-10), 8 Pages, 2015/06

A visualization study is performed under suction vortex geometry in water. In the experiment, the shear-sensitive liquid crystal coating (SSLCC) is applied to grasp the distribution of wall shear stress under the suction votex flow. As the result, it was found that the peak value of wall shear stress is appeared at the center and edge of the projected area of suction pipe. The non-dimensional profile of wall shear stress obtained by suction vortex flow experiment agrees well with that of numerical simulation.

Journal Articles

Development of safety assessment code for decommissioning of nuclear facilities (DecDose)

Shimada, Taro; Oshima, Soichiro*; Sukegawa, Takenori

Journal of Power and Energy Systems (Internet), 4(1), p.40 - 53, 2010/02

A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR) at Japan Atomic Energy Research Institute DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning, and also evaluates the public dose at accidental situations including fire and explosion. As for the public, both the internal and the external doses are calculated by considering inhalation, ingestion, direct radiation from radioactive aerosols and radioactive depositions, and skyshine radiation from waste containers. For external dose for workers, the dose rate from contaminated components and structures to be dismantled is calculated. Internal dose for workers is calculated by considering dismantling conditions, e.g. cutting speed, cutting length of the components and exhaust velocity. DecDose was partially verified by comparison with the actual external dose of workers which were acquired during JPDR Decommissioning Project.

Journal Articles

Development of safety assessment code for decommissioning of nuclear facilities (DecDose)

Shimada, Taro; Oshima, Soichiro; Sukegawa, Takenori

Proceedings of 17th International Conference on Nuclear Engineering (ICONE-17) (CD-ROM), 8 Pages, 2009/07

A safety assessment code, DecDose, for decommissioning of nuclear facilities has been developed, based on the experiences of the decommissioning project of Japan Power Demonstration Reactor (JPDR). DecDose evaluates the annual exposure dose of the public and workers according to the progress of decommissioning of the plant, and also evaluates the public dose at accidental situations including fire and explosion. The DecDose is expected to contribute to utilities in formulating rational dismantling plans and to the safety authority in estimating conservativeness in safety assessment of licensing application or risk-based regulatory criteria.

JAEA Reports

Study of decommissioning cost evaluation technique for nuclear reactor dismantlement; Calculation of decommissioning cost by COSMARD

Oshima, Soichiro; Shiraishi, Kunio; Shimada, Taro; Sukegawa, Takenori; Yanagihara, Satoshi

JAERI-Tech 2005-046, 46 Pages, 2005/09

JAERI-Tech-2005-046.pdf:3.43MB

A model for estimating decommissioning costs consisting of labor cost, device cost and expense, was developed for items which OECD/NEA had standardized, and was installed into the computer system for planning and management of reactor decommissioning (COSMARD). Input data files and databases for the decommissioning of JPDR were prepared, and the decommissioning cost was calculated with COSMARD. In addition, the decommissioning cost for a large scale BWR power plant was also calculated on the assumption of the advantage of scale. The calculations have shown that it is useful and efficient for studying the decommissioning costs for nuclear reactors to apply the COSMARD with database for cost estimation to the decommissioning cost calculation.

Journal Articles

Development of public dose assessment code for decommissioning of nuclear reactors (DecDose)

Shimada, Taro; Oshima, Soichiro; Ishigami, Tsutomu; Yanagihara, Satoshi

Proceedings of 10th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '05) (CD-ROM), 8 Pages, 2005/09

In order to review an operator's "Decommissioning Plan" applied to the regulatory body for approval accurately and quickly, Public Dose Assessment Code for Decommissioning of Nuclear Reactors (DecDose) was developed. It evaluates public exposure doses for each year during dismantling activities in accordance with the "Decommissioning Plan". DecDose takes account of various exposure pathways such as cloudshine, surface ground deposition, ingestion of seafood, and direct and skyshine radiation based on the quantity of radionuclides discharged to the environment, and containers stored in the facility in consideration of cutting and storage of components and structures. Example evaluations with DecDose have shown that it is a useful tool for assessing public dose during decommissioning of nuclear reactors.

JAEA Reports

Characterization of the nuclear power plants in decommissioning program and influence evaluation on decommissioning costs

Mizukoshi, Seiji; Oshima, Soichiro; Shimada, Taro

JAERI-Tech 2005-011, 122 Pages, 2005/03

JAERI-Tech-2005-011.pdf:13.25MB

The radiological and physical characteristic on decommissioning, such as component and structure weights and radioactivity of the 1.1 MWe class reference nuclear power plants summarized in the NUREG reports of the US NRC were classified,arranged and compared with the domestic commercial nuclear power plants and JPDR from a view point of dismantling plan and waste management for decommissioning. As the results, it was found that the radioactive component and structure weights was about 28,000ton、and non-radioactive structure weights was about 124,000ton less than the domestic commercial BWR. And it was found that this differences has mainly influenced dismantling costs for decommissioning. Farther, it was found that the concrete element composition rates of B, Ni, Nb and so were differerence of one or more figures btween the reference nuclear power plants and the domestic commercial PWR or JPDR.Also,it was found that the this difference became about two or three times by radioactivity concentration and has mainly influenced transport and disposal costs for decommissioning.

JAEA Reports

Development of computer systems for planning and management of reactor decommissioning; A Study on influence of work difficulty factors on project management data and simplification of work breakdown structures (Contract research)

Oshima, Soichiro; Sukegawa, Takenori; Shiraishi, Kunio; Yanagihara, Satoshi

JAERI-Tech 2001-086, 83 Pages, 2001/12

JAERI-Tech-2001-086.pdf:5.23MB

Project management data on dismantling the Japan Power Demonstration Reactor (JPDR) was calculated using the Code System for Planning and Management of Reactor Decommissioning (COSMARD), and then its validity was studied by comparing the calculation results with actual data. In addition, work breakdown structure models and database were modified to meet an evaluation with changing work difficulty of preparation and cleanup activities, and calculations were further conducted to analyze feasibility by changing various conditions on cutting and conditioning activities. As the results, COSMARD was verified to be useful by confirming calculation capability on reflection of actual work conditions and relatively good agreement between actual data and calculations. Moreover, it was cleared that main parameters such as work difficulty of preparation and cleanup activities and the cutting speed in demolition work could affect to manpower within 30% in each calculations.

Journal Articles

Development of computer systems for planing and management of reactor decommissioning; Estimation of project management data on Dismantling Tokai Power Station

Yanagihara, Satoshi; Oshima, Soichiro; Sukegawa, Takenori; Tanabe, Norio*; Takaya, Junichi*; Kiuchi, Yoshio*; Yokota, Shuichi*

Nihon Genshiryoku Gakkai-Shi, 43(5), p.493 - 502, 2001/05

 Times Cited Count:1 Percentile:12.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of project management data calculation models relating to dismantling of nuclear facilities (Contract research)

Sukegawa, Takenori; Oshima, Soichiro; ; Yanagihara, Satoshi

JAERI-Data/Code 99-005, 65 Pages, 1999/02

JAERI-Data-Code-99-005.pdf:3.5MB

no abstracts in English

Oral presentation

Development of computer programs for evaluation of public exposure dose in decommissioning of nuclear reactor facilities, 4

Shimada, Taro; Oshima, Soichiro; Ishigami, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Development of computer programs for evaluation of occupational exposure dose in decommissioning of nuclear reactor facilities

Shimada, Taro; Oshima, Soichiro; Sukegawa, Takenori; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Radioactive dust scattering rate evaluation at the time of the cutting work for the JPDR dismantling waste

Takamura, Atsushi; Shimada, Taro; Oshima, Soichiro; Uno, Yuichi; Gunji, Soichi; Ito, Takeshi; Sukegawa, Takenori; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Develpoment of computer code for exposure doses during decommissioning of nuclear reactor facilities

Shimada, Taro; Oshima, Soichiro; Sukegawa, Takenori

no journal, , 

no abstracts in English

Oral presentation

Plasma arc cutting test using the JPDR dismantling waste, 2; Particle size distribution and dispersion mechanism of the radioactive aerosols

Takamura, Atsushi; Shimada, Taro; Oshima, Soichiro; Uno, Yuichi; Gunji, Soichi*; Ito, Takeshi; Sukegawa, Takenori; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Plasma arc cutting test using the JPDR dismantling waste, 1; Evaluation of dispersion rate of the radioactive aerosols

Shimada, Taro; Takamura, Atsushi; Oshima, Soichiro; Uno, Yuichi; Gunji, Soichi*; Ito, Takeshi; Sukegawa, Takenori; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

no abstracts in English

Oral presentation

Study on effectivity of the environmental monitoring data for judging final site status after decommissioning

Sukegawa, Takenori; Shimada, Taro; Uno, Yuichi; Oshima, Soichiro; Ito, Takeshi; Takamura, Atsushi; Tanaka, Tadao; Nakayama, Shinichi

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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