Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of Decommissioning Engineering Support System(DEXUS) of the Fugen Nuclear Power Station

Iguchi, Yukihiro*; Kanehira, Yoshiki*; Tachibana, Mitsuo*; Johnsen, T.*

Journal of Nuclear Science and Technology, 41(3), p.367 - 375, 2004/03

The Fugen Nuclear Power Station (NPS) was shut down permanently in March 2003, and preparatory activities are underway to decommission the Fugen NPS. An engineering system to support the decommissioning is being developed to create a dismantling plan using state-of-the-art software such as 3-dimentional computer aided design (3D-CAD) and virtual reality (VR). In particular, an exposure dose evaluation system using VR has been developed and tested. The total system can be used to quantify radioactive waste, to visualize radioactive inventory, to simulate the dismantling plan, to evaluate workload in radiation environments and to optimize the decommissioning plan. The system will also be useful for educating and training workers and for gaining public acceptance.

JAEA Reports

Data analysis on worker dose in dismantling of Japan Power Demonstration Reactor (JPDR) (Contract research)

Shiraishi, Kunio; Sukegawa, Takenori; Yanagihara, Satoshi

JAERI-Data/Code 2001-028, 86 Pages, 2001/11

JAERI-Data-Code-2001-028.pdf:6.31MB

The data on worker dose in dismantling of the Japan Power Demonstration Reactor (JPDR) was analyzed to characterize its features. It was appeared from the study that the collective dose to the workers was 306 man-mSv, in which maximum individual dose was 8.5 mSv, almost all doses were received in the activities for dismantling of reactor internals, the reactor pressure vessel and the biological shield, and that the worker dose distribution was similar to that in the maintenanee of the facilities which was characterized by the hybrid log normal distribution model. Farthermore, it was found that the dismantling activities were categorized into three groups depending on dose rates in workplaces, then contribution factors for radiation exposure in terms of dose rates in different groups were derived based on the analysis. The study would be useful for estimation of worker dose in future decommissioning of commercial nuclear power plants in Japan.

JAEA Reports

Data analysis on waste arising in dismantling of Japan Power Demonstration Reactor (JPDR) (Contract research)

Shiraishi, Kunio; Sukegawa, Takenori; Yanagihara, Satoshi

JAERI-Data/Code 99-050, p.113 - 0, 2000/01

JAERI-Data-Code-99-050.pdf:5.95MB

no abstracts in English

JAEA Reports

Data analysis on work activities in dismantling of Japan Powor Demonstration Reactor, JPDR (Contract research)

; Sukegawa, Takenori; Yanagihara, Satoshi

JAERI-Data/Code 98-010, 186 Pages, 1998/03

JAERI-Data-Code-98-010.pdf:7.12MB

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report; April 1, 1995-March 31, 1996

JAERI-Review 96-012, 292 Pages, 1996/09

JAERI-Review-96-012.pdf:9.91MB

no abstracts in English

JAEA Reports

Reactor Engineering Department annual report; April 1, 1993$$sim$$March 31, 1994

JAERI-Review 94-009, 333 Pages, 1994/11

JAERI-Review-94-009.pdf:10.37MB

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

JAEA Reports

JAEA Reports

JAEA Reports

Reactor Engineering Department Annual Report,April 1,1984-March 31,1985

JAERI-M 85-116, 259 Pages, 1985/08

JAERI-M-85-116.pdf:6.67MB

no abstracts in English

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop,PhaseIIA,Part 2 Chapter IX:Engineering

; Seki, Masahiro; *; *; *; *; *; *; *; *; et al.

JAERI-M 85-081, 231 Pages, 1985/07

JAERI-M-85-081.pdf:3.67MB

no abstracts in English

JAEA Reports

Conceptual Design Nuclear Power Plant Database System

*; ;

JAERI-M 84-051, 40 Pages, 1984/03

JAERI-M-84-051.pdf:1.09MB

no abstracts in English

JAEA Reports

JAEA Reports

Engineering Data of SEAMATE-II,I; Rapid Heating Test

; ; ; ; ; Yoshida, Kenzo

JAERI-M 9361, 63 Pages, 1981/03

JAERI-M-9361.pdf:2.04MB

no abstracts in English

16 (Records 1-16 displayed on this page)
  • 1