期刊文献+

田湾核电站弱贯穿辐射调查与个人剂量监测 被引量:2

Weakly penetrating radiation and personal dose monitoring in Tianwan Nuclear Power Station
下载PDF
导出
摘要 在田湾核电站两次大修换料期间,对1、2号机组开展了弱贯穿辐射调查,主要工作包括可能存在较高弱贯穿辐射风险场所的辐射剂量率监测、部分代表性工作人员受到的弱贯穿辐射剂量监测、防护用品的防护效果测试等。由弱贯穿辐射测量结果可知,田湾核电站各检修设备表面沉积的放射性核素基本一致,主要包含58Co、60Co、95Nb、95Zr、51Cr、124Sb、54Mn、110mAg、59Fe等,其伴随发射的β射线能量主要集中在600 keV以下。其中测得主泵剂量率比值H’(3)/H^*(10)最大值为2.08,H’(0.07)/H^*(10)最大值为34.9;蒸汽发生器H’(3)/H^*(10)最大值为2.58,H’(0.07)/H^*(10)最大值为10.7;堆本体H’(3)/H^*(10)最大值为1.25,H’(0.07)/H^*(10)最大值为26.4;主泵之外其他泵类设备H’(3)/H^*(10)最大值为3.80,H’(0.07)/H^*(10)最大值为55.6;阀门类设备H’(3)/H^*(10)最大值为1.15,H’(0.07)/H^*(10)最大值为4.18;其他物项H’(3)/H^*(10)最大值为1.53,H’(0.07)/H^*(10)最大值为2.16。检修人员弱贯穿剂量监测结果表明,Hp(0.07)/Hp(10)和Hp(3)/Hp(10)最大值分别为7.66和3.73,大修监测期间的个人剂量当量Hp(10)都在0.35 mSv以下,且这几次大修所有人员的个人剂量当量Hp(10)都小于2 mSv,由此可知Hp(0.07)和Hp(3)分别超过国家标准规定的个人剂量限值500 mSv/a及IAEA新限值20 mSv/a的可能性较小。根据弱贯穿测量结果,建议对主泵可抽取部件检修、反应堆水池清洁、KBA系统泵阀检修、放射性废物分拣等专项检修人员,开展眼晶体剂量和皮肤剂量监测。 During the two refueling outages of the Tianwan Nuclear Power Station,the investigation of weakly penetrating radiation of Units 1 and 2 was carried out,mainly including radiation dose rate monitoring at sites that may have a higher probability of weakly penetrating radiation,the weakly penetrating radiation dose monitoring received by some representative workers and the protective effect test of protective equipment. From the measurement results of weak penetrating radiation,the radionuclides deposited on the surface of the maintenance equipment of Tianwan nuclear power plant are basically the same,including 58Co,60Co,95Nb,95Zr,51Cr,124Sb,54Mn,110mAg,59Fe,etc. The β-ray energy is mainly concentrated below 600 keV. It is measured that the maximum value of H’(3)/H^*(10) is 2. 08 and H’(0. 07)/H^*(10) has a maximum value of 34. 9 for reactor coolant pump item;H’(3)/H^*(10) has a maximum value of 2. 58 and H’(0. 07)/H^*(10)has a maximum value of 10. 7 for the steam generator item;H’(3)/H^*(10) has a maximum value of 1. 25,’(0. 07)/H^*(10) has a maximum value of 26. 4 for the reactor item;The maximum value of H’(3)/H^*(10)is 3. 80 and H’(0. 07)/H^*(10) has a maximum value of 55. 6 for the other pumps item;H’(3)/H^*(10) has a maximum value of 1. 15 and the monitoring value of H’(0. 07)/H^*(10) is 4. 18 for the valves item. The maximum value of H’(3)/H^*(10) is 1. 53 and H’(0. 07)/H^*(10) has the maximum value of 2. 16 for the other items. The results of weakly penetration dose monitoring showed that the maximum values of Hp(0. 07)/Hp(10) and Hp(3)/Hp(10) are 7. 66 and 3. 73 respectively,and the personal dose equivalent Hp(10) during the overhaul monitoring period are all below 0. 35 mSv. In addition,the personal dose equivalent Hp(10) of the entire staff in these overhauls is less than 2 mSv. It indicates that Hp(0. 07) and Hp(3) are less likely to exceed the national standard personal dose limit of 500 mSv/a and the new IAEA limit of 20 mSv/a,respectively. It is suggested to carry out eye crystal dose and skin dose monitoring for special maintenance personnel such as reactor coolant pump maintenance, reactor pool cleaning, KBA system pumps and valves maintenance,radioactive waste sorting,etc.
作者 侯炳君 赵鸿翮 韦应靖 李中华 HOU Bingjun;ZHAO Honghe;WEI Yingjing;LI Zhonghua(Jiangsu Nuclear Power Co.Ltd.,Jiangsu Lianyungang 222000;China Institute for Radiation Protection,Taiyuan 030006)
出处 《辐射防护》 CAS CSCD 北大核心 2020年第1期1-9,共9页 Radiation Protection
关键词 田湾核电站 弱贯穿辐射 皮肤剂量 眼晶体剂量 Tianwan Nuclear Power Station weakly penetrating radiation skin dose monitoring eye lens dose monitoring
  • 相关文献

参考文献5

二级参考文献29

  • 1杨俊武,杨茂春,顾景智,张延生,毛永,陈慧莉,张钧,张志龙.大亚湾核电厂弱贯穿辐射监测评价[J].辐射防护,2006,26(3):137-142. 被引量:7
  • 2张延生.利用闪烁法测量定向剂量当量的实验研究[J].辐射防护,1988,8(4):339-339.
  • 3Heinzelmann M. Experiences and Problems of Skin Irradiation at Workplaces in Germany. Radiat. Prot.Dosim., 1991.39: 173
  • 4ICRU. Measurement of Dose Equivalents from External Photon and Electron Radiations. ICRU Report 47. 1992
  • 5Christensen P. Study of LiF: Mg, Cu, P TL Detectors for Individual Monitoring for Weakly Penetrating Radiation.Radiat. Prot. Dosim., 1993.47:425
  • 6Portal G. Implications of International Recommendations on Monitoring Procedure for Skin Dose Assessment.Radiat. Prot. Dosim., 1991. 39 : 79
  • 7ICRP. Statement tissue reactions [ Elsevier: International Commission Radiological Protection, 2011. R. on.
  • 8IAEA. Radiation protection and safety of radiation sources : international basic safety standards [ R ]. Safety Standards Series No. GSR Part 3 (Interim). Vienna: International Atomic Energy Agency, 2011.
  • 9IAEA. Implications for occupational radiation protection of the new dose limit for the lens of the eye (draft) [ R ]. Vienna: International Atomic Energy Agency, 2013.
  • 10ICRP. Conversion coefficients for in radiological protection against external radiation [ R ]. Elsevier: International Commission on Radiological Protection, 1996.

共引文献17

同被引文献8

引证文献2

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部