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ISSN : 1738-1894(Print)
ISSN : 2288-5471(Online)
ISSN : 2288-5471(Online)
핫셀시설의 방사선 안전성 평가
Evaluation on the Radiological Shielding Design of a Hot Cell Facility
Abstract
The hot cell facility for research activities related to the lithium reduction of spent fuel, which is designed to permit safe handling of source materials with radioactivity levels up to 1,385 TBq, is planned to be built. To meet this goal, the facility is designed to keep gamma and neutron radiation lower than the recommended dose-rate in normally occupied areas. The calculations peformed with QAD-CGGP and MCNP-4C are used to evaluate the proposed engineering design concepts that would provide acceptable dose-rates during a normal operation in hot cell facility. The maximum effective gamma dose-rates on the surfaces of the facility at operation area and at service area calculated by QAD-CGGP are estimated to be mSv/h, respectively. And those calculated by MCNP-4C are mSv/h, respectively, The dose-rates contributed by neutrons are one order of magnitude less than that of gamma sources. Therefore, it is confirmed that the radiological design for hot cell facility satisfies the Korean criterion of 0.01 mSv/h for the operation area and 0.15 mSv/h for the service (maintenance) area.
Shielding, Shielding Design, Hot Cell, QAD-CGGP, MCNP, Effective Dose, 차폐, 차폐 설계, 핫셀, QAD-CGGP, MCNP, 유효선량
Reference
JNFCWT
Online Submission
Korean Radioactive
Waste Society (KRS)
Editorial Office
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