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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.8
- 수록면
- 2,652 - 2,660 (9page)
- DOI
- https://doi.org/10.1016/j.net.2021.01.035
이용수
초록· 키워드
오류제보하기
The gamma-ray exposure doses in decontamination operation after a nuclear accident were evaluatedwith a consideration of various geometrical conditions and specific gamma-ray energies. The calculationdomain is organized with three residence types and each form is divided into two kinds of geometricalarrangements. The position-wise air KERMA values were calculated with an assumption of evenlydistributed gamma-ray source based on Monte Carlo radiation transport analysis using the MCNP code.
The radioactivity is initially set to be unity to be multiplied by the deposition value measured in theactual accident condition. The workforce data set depending on the target object was determined bymodifying the Fukushima report. The external exposure doses for decontamination workers werederived from the calculated KERMA values and the workforce analysis. These results can be used toefficiently determine the workforce required by the characteristics of the area and the structure to bedecontaminated within the dose limits
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