중대사고 시 보조건물 내 작업자 피폭선량 평가 방법론 개발
Development of a Methodology for Evaluating Radiation Dose to Workers in Auxiliary Building under Severe Accidents
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This study aims to evaluate the radiation dose received by workers within the auxiliary building ofthe Saeul Units 1 and 2 during a severe accident. To achieve this, representative accident scenarios were selected,and operator actions required by the severe accident management guidelines were derived to present a methodologyfor dose assessment. The study utilized MAAP5.06 to analyze severe accidents and employed MAAP DOSE toevaluate worker radiation exposure. Among the three operator actions considered, the direct spray action on thereactor building outer wall-side penetration resulted in the highest estimated radiation dose. This is likely becausethe workers are deployed near the reactor building penetration, exposing them to higher radiation levels. Future plansinclude the optimization of dose performance by comparing these findings with evaluations conducted using MCNP,and the development of a data-driven ALARA decision support system for predicting and diagnosing radiationexposure on nuclear sites to ensure worker safety during severe accidents
Abstract
This study aims to evaluate the radiation dose received by workers within the auxiliary building ofthe Saeul Units 1 and 2 during a severe accident. To achieve this, representative accident scenarios were selected,and operator actions required by the severe accident management guidelines were derived to present a methodologyfor dose assessment. The study utilized MAAP5.06 to analyze severe accidents and employed MAAP DOSE toevaluate worker radiation exposure. Among the three operator actions considered, the direct spray action on thereactor building outer wall-side penetration resulted in the highest estimated radiation dose. This is likely becausethe workers are deployed near the reactor building penetration, exposing them to higher radiation levels. Future plansinclude the optimization of dose performance by comparing these findings with evaluations conducted using MCNP,and the development of a data-driven ALARA decision support system for predicting and diagnosing radiationexposure on nuclear sites to ensure worker safety during severe accidents
참고문헌 (8)
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- Regulatory Guideline 16.4. Accident Consequence Assessment, "KINS", ~, pp.KINS (2016), RG-N16.04. Rev.0
- KHNP, "Shin-Kori Nuclear Power Plant Unit 3&4 Severe Accident Management Guidance", ~ (2019)
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- ICRP, "Application of the Commission’s Recommendations for the Protection of People in Emergency Exposure Situtaions, ICRP Publication 109", ~ (2009)