Radiation shielding analysis of the Fugen nuclear power station

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安藤 康正*; 中村 孝久*; 渋谷 進; 他2名*

not registered; not registered; not registered; 2 of others*

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The radiation shielding analysis of pressure tube type heavy water reactors was performed using the discrete ordinate transport code, dot 3.5. The present paper describes the analytical methods developed to calculate the dose rates after shutdown in various regions such as pressure tubes, outside the primary shield and penetrations through the primary shield and calandria tank. The calculation methods were applied to analyze the dose rates in Fugen measured by neutron and -ray detectors. These calculated results are in good agreement with the measured values within a factor of approximately 3.