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机构地区:[1]中国原子能科学研究院保健物理部
出 处:《原子能科学技术》1997年第1期35-43,共9页Atomic Energy Science and Technology
摘 要:用高气压电离室环境连续监测仪连续测量核设施气态流出物γ吸收剂量率的技术和方法,总结了1台连续监测仪在2座实验性核反应堆(15MW重水堆和3.5MW轻水游泳池式反应堆)附近环境中,连续测量3年(1990—1992)所获得的33450个数据资料。给出由于反应堆排放的惰性气体烟羽产生的外照射有效剂量。最高年份(1992年)值为53.8μSv,仅为天然本底值的9%。监测结果与用有限烟羽大气扩散模式计算结果进行了比较。The report describes techniques and methods on continuous monitoring in the environmental γ radiation dose rate due to the effluence from nuclear facilities with a high pressure argon ionization chamber.About 33450 individual record data for three years (1990—1992) were obtained by a continuous monitor in the environment near the two reactors (15 MW heavy water reactor and 3 5 MW light water swimming pool reactor).These data give the absorbed dose caused by noble gas plume from the reactors.The maximum value of annual effective dose is 53 8 μSv in 1992,which is only equal to 9% of natural background level.The monitoring results are compared with the computed results for the finite cloud atmospheric diffusion models,and they are in agreement within 62%.
分 类 号:TL751[核科学技术—辐射防护及环境保护]
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