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首页> 外文期刊>World Journal of Nuclear Science and Technology >Experimental and Simulated Effective Dose for Some Building Materials in France
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Experimental and Simulated Effective Dose for Some Building Materials in France

机译：法国某些建筑材料的实验和模拟有效剂量

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摘要

The specific radioactivity of several building materials used in France, which is considered a direct exposure to radiation, has been assessed by γ-ray spectrometry. Corrected for coincidence summing and self-absorption effects, the values for 226Ra, 232Th and 40K were in the ranges 4 - 56, 3 - 72 and 9 - 1136 Bq·kg-1, respectively. The samples were found to have radium-equivalent activities between 5 and 245 Bq·kg-1. Values of 0.02 - 0.67 for the external and 0.03 - 0.82 for the internal hazard indexes were estimated. The calculated absorbed dose in air agrees closely with MCNPX simulations. The conversion of absorbed dose to annual effective dose gave values between 0.03 - 1.09 mSv·y-1. All these values are below action limits recommended by the International Commission on Radiological Protection. The materials examined would not contribute a significant radiation exposure for an occupant and thus are acceptable for construction.
机译：已通过γ射线光谱法评估了法国使用的几种建筑材料的特定放射性，这些放射性被认为直接暴露于辐射。经过校正的巧合和自我吸收效应，226Ra，232Th和40K的值分别在4-56、3-72和9-1136 Bq·kg-1范围内。发现样品的镭当量活度介于5和245 Bq·kg-1之间。外部危险指数的估计值为0.02-0.67，内部危险指数的估计值为0.03- 0.82。计算得出的空气中吸收剂量与MCNPX模拟非常吻合。吸收剂量到年有效剂量的转换值介于0.03-1.09 mSv·y-1之间。所有这些值均低于国际放射防护委员会建议的行动限值。检查的材料不会对乘员造成明显的辐射暴露，因此可以用于建筑。

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