CAJ | 학술논문

西安脉冲反应堆辐照铀靶后，抽取Kr、Xe裂变气体，通过活性炭吸附于气体源盒内。HPGeγ谱仪测量源盒内混合气体活度，塑料闪烁探测器测量γ剂量率。将源盒、塑料闪烁探测器的几何结构、材料作为蒙特卡罗程序(MCNP)输入信息，模拟塑料闪烁探测器对源盒中核素活度与其γ剂量率对应关系，结合 HPGeγ谱仪所测活度得到剂量率模拟值，结果与实测值偏差小于6%。该工作说明在已知放射源空间结构、放射性核素种类和活度的情况下，采用 MCNP模拟计算复杂气体放射源γ剂量率的方法是可行的。
서안맥충반응퇴복조유파후，추취Kr、Xe렬변기체，통과활성탄흡부우기체원합내。HPGeγ보의측량원합내혼합기체활도，소료섬삭탐측기측량γ제량솔。장원합、소료섬삭탐측기적궤하결구、재료작위몽특잡라정서(MCNP)수입신식，모의소료섬삭탐측기대원합중핵소활도여기γ제량솔대응관계，결합 HPGeγ보의소측활도득도제량솔모의치，결과여실측치편차소우6%。해공작설명재이지방사원공간결구、방사성핵소충류화활도적정황하，채용 MCNP모의계산복잡기체방사원γ제량솔적방법시가행적。
Gamma dose rate of fission gas is calculated by MCNP method and compared with the data measured by plastic scintillation.The fission gas absorbed by active carbon in source vessel was produced by neutron irradiation of uranium in Xi’an Pulsed Reactor.The simula-tion model is composed of geometry and material of source and plastic scintillation detector as well as the gamma-ray energies and probabilities of 85 Krm ,87 Kr,88 Kr,135 Xem ,135 Xe,138 Xe and 138 Cs whose activities were measured by an HPGeγdetector.The presented calculation shows agreement with experiments less than 6% which consequently confirms the reliability of the simulation for gamma dose rate of complicated radioactive gas.