辐射防护 ›› 2019, Vol. 39 ›› Issue (4): 287-296.

• 辐射防护监测 • 上一篇    下一篇

秦山第二核电厂大修期间场所弱贯穿辐射调查

曾进忠1, 韦应靖2, 何俊男1, 赵鹏飞1, 刘立业2, 王川1, 张强1, 谷伟刚2, 湛昆1, 刘杰1   

  1. 1.中核核电运行管理有限公司,浙江 海盐 314300;
    2.中国辐射防护研究院,太原 030006
  • 收稿日期:2018-07-16 出版日期:2019-07-15 发布日期:2019-10-29
  • 通讯作者: 韦应靖。E-mail:weiyj531@sina.com
  • 作者简介:曾进忠(1972—),男,1993年毕业于南京工业学校电子技术应用专业,高级工程师。E-mail:zengjz@cnnp.com.cn

Investigation on weak penetration radiation in site during outagesin Qinshan phase II nuclear power plant

ZENG Jinzhong1, WEI Yingjing2, HE Junnan1, ZHAO Pengfei1, LIU Liye2, WANG Chuan1, ZHANG Qiang1, GU Weigang2, ZHAN Kun1, LIU Jie1   

  1. 1.CNNC Nuclear Power Operations Management Co., Ltd., Zhejiang Haiyan 314300;
    2.China Institute for Radiation Protection, Taiyuan 030006
  • Received:2018-07-16 Online:2019-07-15 Published:2019-10-29

摘要: 在秦山第二核电厂多次大修期间,对泵类设备、反应堆换料水池、蒸汽发生器、阀门类设备的辐射源项和弱贯穿辐射进行了监测。这些设备表面主要沉积的是58Co、60Co、54Mn、51Cr、95Nb、95Zr、124Sb、59Fe、57Co和110mAg等放射性核素,发射的β射线能量主要在100 keV~500 keV范围内。给出了所监测设备表面的$\dot{H}$·*(10)、$\dot{H}$·′(0.07)和$\dot{H}$·′(3)值,3种泵类设备的$\dot{H}$·′(3)/$\dot{H}$·*(10)平均值为1.31±0.09,$\dot{H}$·′(0.07)/$\dot{H}$·*(10)平均值为7.8±0.4;蒸汽发生器热端衬板和冷端衬板的$\dot{H}$·′(3)/$\dot{H}$·*(10)平均值为1.40±0.20,$\dot{H}$·′(0.07)/$\dot{H}$·*(10)平均值为15.1±3.2;4种阀门类设备的$\dot{H}$·′(3)/$\dot{H}$·*(10)平均值为1.32±0.17,$\dot{H}$·′(0.07)/$\dot{H}$·*(10)的平均值为14.6±3.5;堆芯水池和换料水池的$\dot{H}$·′(3)/$\dot{H}$·*(10)平均值为1.29±0.10,$\dot{H}$·′(0.07)/$\dot{H}$·*(10)平均值为8.5±1.1。所有弱贯穿调查设备的$\dot{H}$·′(3)/$\dot{H}$·*(10)总体平均值为1.32±0.12,$\dot{H}$·′(0.07)/$\dot{H}$·*(10)总体平均值为11.4±4.1。结合测量结果,建议主泵、余排泵、蒸汽发生器检修人员和换料水池去污人员,开展眼晶体剂量和皮肤剂量监测。

关键词: 核电厂, 泵类设备, 反应堆换料水池, 蒸汽发生器, 弱贯穿辐射

Abstract: Radiation source and weak penetrating radiation from pumps, reactor refueling pools, steam generators and valves were monitored during several outages in Qin Shan phase II nuclear power plant. Radionuclides such as58Co,60Co,54Mn,51Cr,95Nb,95Zr,124Sb,59Fe,57Co and 110mAg are mainly deposited on the surface of these devices. The emitted beta-ray energy is mainly in the range of 100 keV to 500 keV.$\dot{H}$·*(10),$\dot{H}$·′(0.07) and $\dot{H}$·′(3) values on the surface of monitored equipment are given. The average value of $\dot{H}$·′(3)/$\dot{H}$·*(10) of the three pumping equipment is 1.31±0.09,$\dot{H}$·′(0.07)/$\dot{H}$·*(10) average is 7.8±0.4. The average value of$\dot{H}$·′(3)/$\dot{H}$·*(10) of steam generator is 1.40±0.20,$\dot{H}$·′(0.07)/$\dot{H}$·*(10) average is 15.1±3.2. The average values of $\dot{H}$·′(3)/$\dot{H}$·*(10) of the four types of valve equipment is 1.32±0.17,$\dot{H}$·′(0.07)/$\dot{H}$·*(10) average is 14.6±3.5. The average value of $\dot{H}$·′(3)/$\dot{H}$·*(10) of the refueling cavity is 1.29±0.10,$\dot{H}$·′(0.07)/$\dot{H}$·*(10) average is 8.5±1.1. The overall average value of $\dot{H}$·′(3)/$\dot{H}$·*(10) of all weak penetrating radiation investigation equipment is 1.32±0.12,and the overall average value of $\dot{H}$·′(0.07)/$\dot{H}$·*(10) is 11.4±4.1. Combined with the measurement results,it is suggested that the maintenance personnel in reactor coolant pump,the residual heat removal pump,and the steam generator should carry out the monitoring of ocular lens dose and skin dose, so should the decontamination personnel in the changing pool.

Key words: pump equipment, reactor refueling pool, steam generator, weak penetrating radiation

中图分类号: 

  • TL75+1