辐射防护 ›› 2020, Vol. 40 ›› Issue (6): 510-515.

• 辐射传输与屏蔽 • 上一篇    下一篇

上海硬X射线自由电子激光装置调试用束流收集桶的设计

徐玉海1, 王光宏1, 李哲夫1, 许文贞1, 张斌团1, 吕炯军1, 杨夫彬1, 夏晓彬2   

  1. 1.中国科学院上海高等研究院张江实验室 上海 201204;
    2.中国科学院上海应用物理研究所,上海 201800
  • 出版日期:2020-11-20 发布日期:2021-01-27
  • 作者简介:徐玉海(1985—),男,2008年7月毕业于泰山学院物理学专业,2012年3月毕业于哈尔滨工程大学核技术及应用专业,获硕士学位,助理研究员。E-mial:xuyuhai@zjlab.org.cn

Design of beam dump for the commissioning at SHINE facility

XU Yuhai1, WANG Guanghong1, LI Zhefu1, XU Wenzhen1, ZHANG Bintuan1, LV Jiongjun1, YANG Fubin1, XIA Xiaobin2   

  1. 1. Shanghai Advanced Research Institute,Chinese Academy of Sciences,Shanghai 201204;
    2. Shanghai Institute of Applied physics,Chinese Academy of Sciences,Shanghai 201800
  • Online:2020-11-20 Published:2021-01-27

摘要: 在建上海硬X射线自由电子激光装置(Shanghai high repetition rate XFEL and extreme light facility,SHINE)包含一台8 GeV的超导直线加速器,100 PW的激光系统,三条波荡线和10条实验线站。主加速器的第三磁压缩段(BC3段)有一调试用的束流收集桶,BC3段的调试电子流强为0.3 μA、能量为7.7 GeV,束流功率为2.31 kW。本文从材料对7.7 GeV电子的能量吸收方面考虑,对束流收集桶的结构进行了确定。用ANSYS 17.0对束流收集桶的温度场进行了分析,结果证明在有表面空气自然对流换热的情况下,铝芯的最高温度为193.14 ℃,在束流收集桶坑道无外界换气的情况下,束流收集桶需要外围冷却水;用蒙特卡罗程序FLUKA对束流收集桶的活化进行了分析,保守假设束流收集桶连续注束2 000 h。结果证明要保证停机1 h后,束流收集桶周围30 cm处的剩余辐射剂量小于25 μSv/h,束流收集桶外围需要55~85 cm的混凝土屏蔽体;结果显示束流收集桶的剩余辐射剂量在30 min内衰减的非常快,这是由于刚停机时束流收集桶内产生的50%左右的放射性核素半衰期都小于10 min。

关键词: 上海硬X射线自由电子激光装置, 束流收集桶, ANSYS17.0, 热分析, FLUKA, 活化分析

Abstract: SHINE facility,Shanghai hard Xray free electron laser (XFEL) facility,and jointly built by Shanghai Institute of advanced research and Shanghai Institute of Applied physics,Chinese Academy of Sciences (SINAP,CAS).It is currently under construction in Zhangjiang Science Park,Shanghai.The SHINE facility consists of an 8 GeV continuous-wave (CW) superconducting linear accelerator,a 100 PW laser system,three undulator lines,and ten experimental end-stations at phase-I.A beam dump set at BC3 accelerator section is designed for beam commissioning with beam energy of 7.7 GeV and beam current 0.3 μA based on the preliminary conceptual design.This paper presents the heat analysis of the dump using ANSYS 17.0 and the activation analysis of the beam dump for radiation safety evaluation by using Monte Carlo simulation code FLUKA.It is assumed conservatively that the beam is continuously injected into the dump for 2 000 h during normal operation.The activation analysis showed that the surrounding concrete shielding with the thickness of 55-85 cm for the dump is required,in order to keep the residual dose rate outside the dump below 25 μSv/h at 1 hour after stopping the beam injection.

Key words: activation analysis, beam dump, radiation safety, FLUKA, FEL facility