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Development of an Evaluation Tool of Radiation Dose Rate in Primary Containment Vessel for Hamaoka BWR Plants

[+] Author Affiliations
Hiromitsu Inagaki

Chubu Electric Power Company, Inc., Nagoya, Japan

Paper No. ICONE16-48688, pp. 241-244; 4 pages
doi:10.1115/ICONE16-48688
From:
  • 16th International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues
  • Orlando, Florida, USA, May 11–15, 2008
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4814-0 | eISBN: 0-7918-3820-X
  • Copyright © 2008 by ASME

abstract

We are developing a radiation dose rate evaluation tool for work areas in the primary containment vessel (PCV) of the Hamaoka BWR plant in order to reduce radiation exposure to workers. The evaluation tool is composed of two calculation codes; a water chemistry code and a radiation dose rate code. The radiation dose rate calculates radiation maps of the work areas in the PCV of Hamaoka plant. We compared measured values with calculated values in order to improve the accuracy of the tool.

Copyright © 2008 by ASME

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