用蒙特卡罗模拟和γ能谱分析中国NSRL直线加速器的感生放射性
Induced radioactivity analysis for the NSRL Linac in China using Monte Carlo simulations and gamma-spectroscopy
摘要：
合肥国家同步辐射实验室的200 MeV电子直线加速器是我国最早建成的高能电子直线加速器之一。电子由五个加速管加速到200 MeV，并由刮刀准直。刮刀的孔径比加速管的孔径小，所以一些电子在穿过材料时会撞击到材料上。这些丢失的电子主要通过韧致辐射和光核反应引起感生放射性。本文介绍了使用FLUKA模拟和伽玛能谱研究NSRL直线加速器的感生放射性。测量结果表明，电子主要在刮刀处损失。所以NSRL直线加速器的感生放射性主要产生于此。使用FLUKA Monte Carlo代码模拟放射性核素类型，并将结果与用高纯锗（HPGe）γ谱仪进行的测量进行比较。NSRL直线加速器由于去年升级而退役。取出的组分用于研究诱导放射性。通过测量确认的放射性核素为：$^{57}$ Ni、$^{52}$ Mn、$^{51}$ Cr、$^{58}$ Co、$^{56}$ Co、$^{57}$ Co、$^{54}$ Mn、$^{60}$ Co和$^{22}$ Na，其中前8种核素通过FLUKA模拟预测。该研究将为类似加速器退役方案提供理论依据，对加速器结构设计、材料选择和辐射防护设计具有重要意义。
英文摘要：
The 200-MeV electron linac of the National Synchrotron Radiation Laboratory (NSRL) located in Hefei is one of the earliest high-energy electron linear accelerators in China. The electrons are accelerated to 200 MeV by five acceleration tubes and are collimated by scrapers. The scraper aperture is smaller than the acceleration tube one, so some electrons hit the materials when passing through them. These lost electrons cause induced radioactivity mainly due to bremsstrahlung and photonuclear reaction. This paper describes a study of induced radioactivity for the NSRL Linac using FLUKA simulations and gamma-spectroscopy. The measurements showed that electrons were lost mainly at the scraper. So the induced radioactivity of the NSRL Linac is mainly produced here. The radionuclide types were simulated using the FLUKA Monte Carlo code and the results were compared against measurements made with a High Purity Germanium (HPGe) gamma spectrometer. The NSRL linac had been retired because of upgrading last year. The removed components were used to study induced radioactivity. The radionuclides confirmed by the measurement are: $^{57}$Ni, $^{52}$Mn, $^{51}$Cr, $^{58}$Co, $^{56}$Co, $^{57}$Co, $^{54}$Mn, $^{60}$Co and $^{22}$Na, the first eight nuclides of which are predicted by FLUKA simulation. The research will provide the theoretical basis for the similar accelerator decommissioning plan, and is significant for accelerator structure design, material selection and radiation protection design.
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