Study on induced radioactivity of China Spallation Neutron Source

China Spallation Neutron Source (CSNS) is the first High Energy Intense Proton Accelerator planned to be constructed in China during the State Eleventh Five-Year Plan period, whose induced radioactivity is very important for occupational disease hazard assessment and environmental impact assessment. Adopting the FLUKA code, the authors have constructed a cylinder-tunnel geometric model and a line-source sampling physical model, deduced proper formulas to calculate air activation, and analyzed various issues with regard to the activation of different tunnel parts. The results show that the environmental impact resulting from induced activation is negligible, whereas the residual radiation in the tunnels has a great influence on maintenance personnel, so strict measures should be adopted.     

北京正负电子对撞机重大改造工程储存环调试运行期间辐射剂量监测与分析

介绍北京正负电子对撞机重大改造工程储存环加速器调试运行期间周围环境、工作区域各监测点的平均辐射剂量率水平. 给出了电子环调试、正电子环调试、正负电子双环对撞调试、同步辐射光用户实验及不同束流频率下的典型剂量率水平曲线图, 并提出了防护建议. 总体监测数据表明, 储存环调试运行期间, 主体屏蔽及局部防护措施满足了储存环加速器调试运行需要, 达到了设计指标.     

Analysis of radiation environmental safety for China＇s Spallation Neutron Source （CSNS）

The China Spallation Neutron Source（CSNS） is going to be located in Dalang Town,Dongguan City in the Guangdong Province.In this paper we report the results of the parameters related with environment safety based on experiential calculations and Monte Carlo simulations.The main project of the accelerator is an under ground construction.On top there is a 0.5 m concrete and 5.0 m soil covering for shielding,which can reduce the dose out of the tunnel＇s top down to 0.2 μSv/h.For the residents on the boundary of the CSNS,the dose produced by skyshine,which is caused by the penetrated radiation leaking from the top of the accelerator,is no more than 0.68 μSv/a.When CSNS is operating normally,the maximal annual effective dose due to the emission of gas from the tunnel is 2.40×10-3 mSv/a to the public adult,and 2.29×10-3 mSv/a to a child,both values are two orders of magnitude less than the limiting value for control and management.CSNS may give rise to an activation of the soil and groundwater in the nearest tunnels,where the main productions are 3H,7Be,22Na,54Mn,etc.But the specific activity is less than the exempt specific activity in the national standard GB13376-92.So it is safe to say that the environmental impact caused by the activation of soil and groundwater is insignificant.To sum up,for CSNS,as a powerful neutron source device,driven by a highenergy high-current proton accelerator,a lot of potential factors affecting the environment exist.However,as long as effective shieldings for protection are adopted and strict rules are drafted,the environmental impact can be kept under control within the limits of the national standard.     

反照中子剂量计的现场标定

反照中子个人剂量计的体积小, 使用方便, 易于测量, 越来越为人们所乐于采用. 使用反照中子剂量计一般要用标定源进行标定. 但是现场能谱的差异要影响现场测量的精度, 因此必须解决现场标定问题. 本文介绍了现场标定的方法以及利用Bonner柱进行加速器现场的标定技术.     

Measurement of radiation dose at the north interaction point of BEPCⅡ

The technique details for measuring radiation dose are expounded. The results of gamma and neutron radiation levels are presented and the corresponding radiation shielding is discussed based on the simplified estimation. In addition, the photon radiation level move as background for future experiments is measured by a NaI（T1） detector.     

应用MORSE程序计算中子的天空反散射

用中子源模拟粒子加速器，以MORSE程序分析计算由于天空反散射引起的中子剂量当量的变化规律，揭示了天空反散射的实质，计算结果可供加速器或核设施环境评价和防护设计使用．计算模型采用将中子源置于空心圆柱体中，圆柱体分为有顶盖屏蔽和无顶盖屏蔽两种情况．中子源能量分别为2.38MeV、14Mev和巨共振中子．中子源为各向同性．此外，还分析计算了不同的发射立体角和不同散射介质的影响．     

北京正负电子对撞机重大改造工程储存环调试运行期间辐射剂量监测与分析

介绍北京正负电子对撞机重大改造工程储存环加速器调试运行期间周围环境、工作区域各监测点的平均辐射剂量率水平.给出了电子环调试、正电子环调试、正负电子双环对撞调试、同步辐射光用户实验及不同束流频率下的典型剂量率水平曲线图,并提出了防护建议.总体监测数据表明,储存环调试运行期间,主体屏蔽及局部防护措施满足了储存环加速器调试运行需要,达到了设计指标.     

80MeV电子打靶次级中子产额和角分布的测量

本实验采用包有慢化体的铟活化探测器测量80MeV电子打铅厚靶后次级中子的产额和角分布. 测得次级中子按各向同性分布, 中子产额为(2.20±0.13)×10¹²n/s∙kW, 与理论计算结果相符.     

30MeV电子直线加速器脉冲中子注量率及剂量当量率的测定

电子直线加速器的辐射场特点, 要求探测器在窄脉冲辐射场中有正确的剂量响应, 较高的n、γ分辨能力和抗电磁干扰能力. 本文中采用In活化探测器测量脉冲中子, 它能满足上述三点要求, 是一种可靠的方法. 此外, 该探测器结构简单, 造价低廉, 便于大量使用. 我们用它测定了30MeV电子直线加速器屏蔽墙内外中子注量率及剂量当量率的分布. 同时与TLD测量结果进行了比较. 最后, 讨论了轫致辐射的高能光子对In发生的光核反应生成的活性对探测器的n、γ分辨能力的影响.