Calculation of dpa rate in graphite box of Tehran Research Reactor(TRR)  

作　　者：Mohamad Amin Amirkhani Mohsen Asadi Asadabad Mostafa Hassanzadeh Seyed Mohammad Mirvakili Ali Mohammadi 

机构地区：[1]Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, Tehran, Iran [2]Department of Physics, Arak University, Arak, Iran

出　　处：《Nuclear Science and Techniques》2019年第6期44-56,共13页核技术（英文）

摘　　要：Radiation damage is an important factor that must be considered while designing nuclear facilities and nuclear materials. In this study, radiation damage is investigated in graphite, which is used as a neutron reflector in the Tehran Research Reactor (TRR) core. Radiation damage is shown by displacement per atom (dpa) unit. A cross section of the material was created by using the SPECOMP code. The concentration of impurities present in the non-irradiated graphite was measured by using the ICP-AES method. In the present study the MCNPX code had identified the most sensitive location for radiation damage inside the reactor core. Subsequently, the radiation damage (spectral-averaged dpa values) in the aforementioned location was calculated by using the SPECTER, SRIM Monte Carlo codes, and Norgett, Robinson and Torrens (NRT) model. The results of “Ion Distribution and Quick Calculation of Damage”(QD) method groups had a minor difference with the results of the SPECTER code and NRT model. The maximum radiation damage rate calculated for the graphite present in the TRR core was 1.567 9 10^-8 dpa/s. Finally, hydrogen retention was calculated as a function of the irradiation time.Radiation damage is an important factor that must be considered while designing nuclear facilities and nuclear materials. In this study, radiation damage is investigated in graphite, which is used as a neutron reflector in the Tehran Research Reactor（TRR） core.Radiation damage is shown by displacement per atom（dpa） unit. A cross section of the material was created by using the SPECOMP code. The concentration of impurities present in the non-irradiated graphite was measured by using the ICP-AES method. In the present study the MCNPX code had identified the most sensitive location for radiation damage inside the reactor core. Subsequently, the radiation damage（spectral-averaged dpa values） in the aforementioned location was calculated by using the SPECTER, SRIM Monte Carlo codes, and Norgett,Robinson and Torrens（NRT） model. The results of ‘‘Ion Distribution and Quick Calculation of Damage’’（QD）method groups had a minor difference with the results of the SPECTER code and NRT model. The maximum radiation damage rate calculated for the graphite present in the TRR core was 1.567 × 10-8 dpa/s. Finally, hydrogen retention was calculated as a function of the irradiation time.

关 键 词：Radiation damage GRAPHITE SPECTER SRIM MCNPX TEHRAN Research Reactor 

分 类 号：TL[核科学技术]