反应堆构件活化和剂量计算研究

Research on reactor component activation and dose calculation

  • 摘要: 放射性源项调查是反应堆退役制订方案、估算费用和进度及作好辐射防护和应急准备的重要依据。反应堆构件在中子辐照过程中由于中子活化反应会产生大量的放射性核素,其产生的衰变光子是反应堆退役过程中工作人员面临辐射剂量的主要来源。采用蒙特卡罗粒子输运程序(cosRMC、MCNP)和活化计算程序(DEPTH、ALARA)相结合的方法计算反应堆构件在运行一定时间后产生的放射性核素核子数密度、活度和几个主要构件的辐射剂量率。对比通过两个不同活化程序计算得到的计算结果,相对偏差在可接受范围内,表明了cosRMC的活化计算和剂量率计算功能应用于反应堆退役分析的可靠性和准确性。

     

    Abstract:
    Background
    The investigation of radioactive source terms serves as a critical basis for formulating reactor decommissioning plans, estimating costs and schedules, and ensuring adequate radiation protection and emergency preparedness.
    Purpose
    During neutron irradiation, reactor components undergo neutron activation reactions that generate significant quantities of radionuclides. The decay photons emitted by these nuclides constitute the primary source of radiation exposure for personnel during reactor decommissioning.
    Methods
    A combined approach using Monte Carlo particle transport programs (cosRMC, MCNP) and activation calculation programs (DEPTH, ALARA) was employed to calculate the nuclide atom density, activity, and radiation dose rates for key components after a specified operational period.
    Results
    Comparing results from the two activation programs shows relative deviations within acceptable limits.
    Conclusions
    The comparison demonstrates the reliability and accuracy of cosRMC’s activation calculations and dose rate assessment capabilities for reactor decommissioning analysis.

     

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