Skip Navigation

Radiation Protection Dosimetry 2005 116(1-4):592-596; doi:10.1093/rpd/nci014
This Article
Right arrow Full Text
Right arrow Full Text (PDF)
Right arrow Alert me when this article is cited
Right arrow Alert me if a correction is posted
Services
Right arrow Email this article to a friend
Right arrow Similar articles in this journal
Right arrow Similar articles in PubMed
Right arrow Alert me to new issues of the journal
Right arrow Add to My Personal Archive
Right arrow Download to citation manager
Right arrow Search for citing articles in:
ISI Web of Science (1)
Right arrowRequest Permissions
Google Scholar
Right arrow Articles by Ohga, Y.
Right arrow Articles by Matsuzaki, T.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Ohga, Y.
Right arrow Articles by Matsuzaki, T.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

A system for the calculation and visualisation of radiation field for maintenance support in nuclear power plants

Yukiharu Ohga1,*, Mitsuko Fukuda1, Kiyotaka Shibata2, Takashi Kawakami3 and Tomokazu Matsuzaki3

1 Power & Industrial Systems R&D Laboratory, Hitachi, Ltd, 7-2-1 Omika-cho, Hitachi-shi, Ibaraki-ken, 319-1221 Japan
2 Hitachi Engineering & Services Co., Ltd, 38 Shinkou-cho, Hitachinaka-shi, Ibaraki-ken, 312-0005 Japan
3 Ibaraki Hitachi Information Service Co., Ltd, 1-22-1 Saiwai-cho, Hitachi-shi, Ibaraki-ken, 317-0073 Japan

* Corresponding author: ohga{at}erl.hitachi.co.jp

A system has been developed to improve the efficiency of maintenance work while decreasing the radiation exposure of maintenance personnel in nuclear power plants. The input data for dose rate calculation are automatically generated by using computer-aided design data. Changes for the input data corresponding to the progress of maintenance work, such as installation of a radiation shield and removal of a component, are easily input interactively on a graphical user interface (GUI). A new method was proposed which searches the sets of source and detector points between which gamma-ray attenuation is changed by the component movement. The calculation is performed only for the changed sets, so that the change of the three-dimensional dose rate distribution is calculated rapidly according to the work progress. The dose rate distribution and the radiation exposure of maintenance personnel are displayed three-dimensionally in colour with plant components and pipes on the GUI.


Add to CiteULike CiteULike   Add to Connotea Connotea   Add to Del.icio.us Del.icio.us    What's this?




Disclaimer: Please note that abstracts for content published before 1996 were created through digital scanning and may therefore not exactly replicate the text of the original print issues. All efforts have been made to ensure accuracy, but the Publisher will not be held responsible for any remaining inaccuracies. If you require any further clarification, please contact our Customer Services Department.