首页> 外文期刊>Radiation Protection Dosimetry >RADIOLOGICAL HAZARDS DUE TO NATURALLY OCCURRING RADIONUCLIDES IN THE SELECTED BUILDING MATERIALS USED FOR THE CONSTRUCTION OF DWELLINGS IN FOUR DISTRICTS OF THE PUNJAB PROVINCE, PAKISTAN
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RADIOLOGICAL HAZARDS DUE TO NATURALLY OCCURRING RADIONUCLIDES IN THE SELECTED BUILDING MATERIALS USED FOR THE CONSTRUCTION OF DWELLINGS IN FOUR DISTRICTS OF THE PUNJAB PROVINCE, PAKISTAN

机译:巴基斯坦旁遮普省四个地区用于建造住宅的精选建筑材料中自然产生的放射性核素造成的辐射危害

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摘要

This paper presents the finding of a study undertaken to determine the naturally occurring radionuclides present in commonly used building materials for dwellings and workplaces in four districts of the Punjab Province, Pakistan. The concentrations of ~(226)RA, ~(232)TH and ~(40)K were measured by using gamma-ray spectroscopy. A total of 80 samples of building materials were collected from various manufacturers and suppliers of the studied area. The specific activities of ~(226)Ra, ~(232)TH and ~(40)K were measured in building samples, and results ranged from minimum values of 9+ 1, 9 + 2 and 27 + 8 Bq kg"' to maximum values of 106 ± 5, 133 ± 5 and 914±21 Bq kg~(-1) with mean values of 42 ± 3, 48 ± 3 and 376±16 Bq kg~(-1), respectively. From the measured activity concentrations, equivalent radium (Ra_(eq)), terrestrial absorbed dose rate, annual effective dose as well as external and internal hazard indices were calculated and found to range from 52 ±7 to 274± 15 Bq kg~(-1), 23 ± 3 to 130 6 nGy h~(-1), 0.15 ± 0.02 to 0.80 ± 0.03 mSv, 0.14 ± 0.02 to 0.75 ± 0.04 and 0.2 ± 0.02 to 0.98 ± 0.05, respectively. These results were comparable to the results of similar studies undertaken locally and in other countries. The samples considered were safe for use in construction of dwellings in the study area and do not pose any significant source of radiation hazard.
机译:本文介绍了一项研究的发现,该研究旨在确定巴基斯坦旁遮普省四个地区的住宅和工作场所常用建筑材料中存在的天然放射性核素。使用γ射线光谱法测量〜(226)RA,〜(232)TH和〜(40)K的浓度。从研究区域的各种制造商和供应商那里收集了总共80种建筑材料样品。在建筑样品中测量了〜(226)Ra,〜(232)TH和〜(40)K的比活,结果范围从最小值9 + 1、9 + 2和27 + 8 Bq kg“'至最大值分别为106±5、133±5和914±21 Bq kg〜(-1),平均值分别为42±3、48±3和376±16 Bq kg〜(-1)。计算浓度,当量镭(Ra_(eq)),陆地吸收剂量率,年有效剂量以及外部和内部危害指数,发现范围为52±7至274±15 Bq kg〜(-1),23 ±3至130 6 nGy h〜(-1),0.15±0.02至0.80±0.03 mSv,0.14±0.02至0.75±0.04和0.2±0.02至0.98±0.05,这些结果与类似研究的结果相当所考虑的样品可以安全地用于研究区域的住宅建设,并且不会造成任何明显的辐射危害。

著录项

  • 来源
    《Radiation Protection Dosimetry》 |2013年第3期|352-360|共9页
  • 作者单位

    Department of Medical Physics, Nuclear Medicine, Oncology and Radiotherapy Institute (NORI), Islamabad, Pakistan;

    Department of Physics, University of Azad Jammu and Kashmir, Muzaffarabad, Azad Kashmir 13100, Pakistan;

    PINSTECH, P.O. Nilore, Islamabad, Pakistan;

    PINSTECH, P.O. Nilore, Islamabad, Pakistan;

  • 收录信息 美国《科学引文索引》(SCI);美国《化学文摘》(CA);
  • 原文格式 PDF
  • 正文语种 eng
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