摘要
通过对10 MW高温气冷堆从装料前到满功率运行期间工艺流、工艺间、流出物、厂区环境的放射性核素含量、个人剂量水平进行的系统监测,了解了反应堆在不同功率下运行时对环境和工作人员的辐射影响,为反应堆安全运行和验收评价提供依据。监测结果显示,除反应堆堆顶距堆芯最近处中子剂量率最高为3.1μSv/h外,其余点和工艺间均小于2.5μSv/h(贮留因子T>1/4)的剂量率控制值,厂区环境γ剂量率处于本底水平,烟囱流出物中没有检测到放射性核素(低于方法探测限)。
In order to assess the impact of radiation on environment and human from 10 MW High Temperature Gas-Cooled Reactor （HTR-10） at various power, some radiation monitoring items such as neutron dose rate on the top of reactor shell,γ absorbed dose rate of the technic plume and technic areas and noble gas plume released from reactor chimney were carried out. Monitoring results revealed that total absorbed dose rate including γ and neutron dose rate were far below the control limit 2.5 μSv/h specified by GB 18871. Environmental air absorbed dose rates around reactors were found at background radiation levels and no nuclides were detectable by HPGe gamma-my spectrometer （ 〈 LLD）.
出处
《辐射防护》
CAS
CSCD
北大核心
2007年第2期72-78,共7页
Radiation Protection
基金
863项目资助(项目编号863-614-02)
