Asgharizadeh F, Abbasi A, Hochaghani O, Gooya E S
Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran.
Radiat Prot Dosimetry. 2012 Apr;149(3):321-6. doi: 10.1093/rpd/ncr233. Epub 2011 Jun 17.
Due to increasing concern about environmental radiological protection, specific radioactivity concentrations of (226)Ra, (232)Th and (40)K 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 (232)Th, (226)Ra and (40)K 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).
由于对环境辐射防护的关注日益增加,利用高分辨率HPGeγ能谱系统测定了从伊朗德黑兰市采集的不同类型常用花岗岩样品中(226)镭、(232)钍和(40)钾的比活度浓度。所选花岗岩样品中(232)钍、(226)镭和(40)钾的活度浓度分别为18至178、6至160和556至1539 Bq kg-1。镭当量活度(Ra(eq))低于经济合作与发展组织核能机构(NEA - OECD)设定的370 Bq kg-1限值[核能机构。建筑材料中天然放射性的辐射暴露。NEA专家组报告。经合组织(1979年)],但有两个样品除外。在大多数样品中发现内照射危害指数远低于可接受限值。所调查的五块商用花岗岩样品不符合联合国原子辐射影响科学委员会(UNSCEAR)[联合国原子辐射影响科学委员会。天然辐射源的辐射暴露。提交大会的报告(1993年)]所说明的安全标准。应用欧洲委员会[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年)]最近推荐的表层材料剂量标准,所有调查样品均符合0.3 mSv y-1的豁免剂量限值。