Natural radioactivity in granite stones used as building materials in Iran
Natural radioactivity in granite stones used as building materials in Iran
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DOI：
10.1093/rpd/ncr233
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发表时间：
2012-04-01
影响因子：
1
通讯作者：
Gooya, E. S.
中科院分区：
文献类型：
--
作者：
Asgharizadeh, F.;Abbasi, A.;Gooya, E. S.
由于人们对环境辐射防护的日益关注，采用高分辨HPGe γ能谱系统测定了伊朗德黑兰市不同类型的常用花岗岩石样品中Ra-226、Th-232和K-40的比放射性浓度。所选花岗岩样品中Th-232、Ra-226和K-40的活度浓度分别为18 ~ 178、6 ~ 160和556 ~ 1539 Bq·kg（1）。镭当量放射性活度（Ra-eq）低于NEA-OECD [核能机构]规定的370 Bq kg（1）限值。建筑材料中天然放射性的辐射照射。NEA专家组的报告。经合组织（1979年）]，两个样本除外。在大多数样品中，发现内部危害指数远低于可接受的限度。五个被调查的商业花岗岩石材样品不符合UNSCEPTION（联合国原子辐射影响科学委员会）所说明的安全标准。暴露于自然辐射源。提交大会的报告（1993年）。应用欧盟委员会最近建议的剂量标准[欧洲委员会关于建筑材料天然放射性的辐射防护原则报告。辐射防护112（1999）]，所有研究样品均符合0.3 mSv y（1）的豁免剂量限值。
Due to increasing concern about environmental radiological protection, specific radioactivity concentrations of Ra-226, Th-232 and K-40 in different types of commonly used granite stone samples collected from the Tehran city of Iran have been determined by means of a high-resolution HPGe gamma-spectroscopy system. The activity concentrations of Th-232, Ra-226 and K-40 in the selected granite samples ranged from 18 to 178, 6 to 160 and 556 to 1539 Bq kg(1), respectively. The radium equivalent activities (Ra-eq) are lower than the limit of 370 Bq kg(1) set by NEA-OECD [Nuclear Energy Agency. Exposure to radiation from natural radioactivity in building materials. Report by NEA Group of Experts. OECD (1979)], except in two samples. The internal hazard indexes have been found well below the acceptable limit in most of the samples. Five samples of investigated commercial granite stones do not satisfy the safety criterion illustrated by UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation. Exposure from natural sources of radiation. Report to the General Assembly (1993). Applying dose criteria recently recommended by the EC [European Commission Report on Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials. Radiation Protection 112 (1999)] for superficial materials, all investigated samples meet the exemption dose limit of 0.3 mSv y(1).