연소도 이득효과를 적용한 사용후핵연료 수송용기의 방사선원별 차폐영향 분석

A Study on the Radiation Source Effect to the Radiation Shielding Analysis for a Spent-Fuel Cask Design with Burnup-Credit

Kyung-O KIM, Sooo Youog KIM, Jaehoon Ko, Gangug Lee, Taeman Kim, Jeonghyun Yoon

Abstract

The radiation shielding analysis for a Burnup-credit (BUC) cask designed under the management of Korea Radioactive Waste Management Corporation (KRMC) was performed to examine the contribution of each radiation source affecting dose rate distribution around the cask. Various radiation sources, which contain neutron and gamma-ray sources placed in active fuel region and the activation source, and imaginary nuclear fuel were all considered in the MCNP calculation model to realistically simulate the actual situations. It was found that the maximum external and surface dose rates of the spent fuel cask were satisfied with the domestic standards both in normal and accident conditions. In normal condition, the radiation dose rate distribution around the cask was mainly influenced by activation source (60Co radioisotope); in another case, the neutron emitted in active fuel region contributed about 90% to external dose rate at 1m distance from side surface of the cask. Besides, the contribution level of activation source was dramatically increased to the dose rates in top and bottom regions of the cask. From this study, it was recognized that the detailed investigation on the radiation sources should be performed conservatively and accurately in the process of radiation shielding analysis for a BUC cask.

Key Words : 사용후핵연료, 수송/저장시스템, 연소도이득효과, 방사선 차폐, Spent Nuclear Fuel, Transportation/Storage System, Burnup Credit, Radiation Shielding

Reference

JNFCWT

Online Submission

Korean Radioactive
Waste Society (KRS)

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