EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR

A. Hamzah, H. Adrial, Subiharto Subiharto
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Abstract

EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR. The RSG-GAS reactor has been operated for 30 years. Since the nuclear reactor has been operated for a long time, aging process on its components may occur. One important parameter for maintaining the safety level of the RSG-GAS reactor is to maintain radiation exposure as low as possible, especially in the working area. The evaluation results should be able to demonstrate that the radiation exposure of the RSG-GAS is still safe for workers, communities and the surrounding environments. The purpose of this study is to evaluate radiation exposure in the working area to ensure that the operation of RSG-GAS is still safe for the next 10 years. The scope of this work is confirming the calculation results with the measured radiation dose in the RSG-GAS reactor working area. Measurement of radiation exposure is done by using the installed equipments at some points in the RSG-GAS working area and a portable radiation exposure measurement equipment. The calculations include performance of a modeling and analysis of dose rate distribution based on the composition and geometry data of RSG-GAS by using MCNP.  The analysis results show that the maximum dose rate at Level 0 m working area of RSG-GAS reactor is 3.0 mSv/h with a deviation of 6%, which is relatively close to the measurement value. The evaluation results show that the dose rate in RSG-GAS working area is below the limit value established by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) of 10 mSv/h (for the average effective dose of 20 mSv/year). Therefore, it is concluded that the dose rate in RSG-GAS working area is safe for personnel..Kata kunci: dose rates, RSG-GAS, radiation safety, MCNP.
rsg -气体反应器辐射剂量率评价
rsg -气体反应器辐射剂量率评价。RSG-GAS反应堆已经运行了30年。由于核反应堆长期运行,其部件可能发生老化过程。维持RSG-GAS反应堆安全水平的一个重要参数是保持尽可能低的辐射暴露,特别是在工作区域。评价结果应能够证明RSG-GAS的辐射暴露对工人、社区和周围环境仍然是安全的。本研究的目的是评估工作区域的辐射暴露,以确保未来10年RSG-GAS的运行仍然是安全的。本工作的范围是将计算结果与RSG-GAS反应堆工作区域的实测辐射剂量进行验证。辐射照射量的测量是利用在RSG-GAS工作区域的某些点安装的设备和便携式辐射照射测量设备进行的。计算包括基于RSG-GAS的组成和几何数据,用MCNP对剂量率分布进行建模和分析。分析结果表明,RSG-GAS反应器0 m级工作区域的最大剂量率为3.0 mSv/h,偏差为6%,与实测值较为接近。评价结果表明,RSG-GAS工作区域的剂量率低于印度尼西亚核能监管机构(BAPETEN)规定的10 mSv/h(平均有效剂量为20 mSv/年)的限值。因此,RSG-GAS工作区的剂量率对人员是安全的。Kata kunci:剂量率,RSG-GAS,辐射安全,MCNP。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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