Shielding design of container for radioactive waste of CFETR helium cooling blanket

doi:10.16568/j.0254-6086.202202001

Abstract

Abstract: The shielding design of container of radioactive waste decommissioned from Helium Coolant Ceramic Breeder-Tritium Breeding Blanket (HCCB-TBB) for China Fusion Engineering Testing Reactor (CFETR) is studied. The characteristics of radioactive source term for CFETR HCCB are analyzed, the calculation model of container shielding thickness is focused on, and dose rate of container surface is calculated using MCNP5. It is found that there is an exponential attenuation relationship between the container surface dose rate and the thickness of container. According to the relevant requirements of the current standard of container, two design schemes of container with steel material and steel-lead-steel sandwich material are proposed, respectively.

Key words: CEFTR, Radioactive waste, Container, γ Dose rate; Shielding design

摘要： 对中国聚变工程实验堆(CFETR)氦冷陶瓷产氚包层放射性废物包装容器进行了屏蔽设计。分析了CFETR氦冷陶瓷包层放射源项特点，阐述了容器屏蔽厚度的计算模型，使用蒙特卡罗程序MCNP5计算容器表面剂量率。结果表明包装容器表面剂量率与容器厚度之间呈现指数衰减关系。再根据中国现行标准，给出普通碳钢材料和普通碳钢-铅夹层材料两种方案。

关键词: 中国聚变工程实验堆, 放射性废物, 包装容器, γ剂量率, 屏蔽设计

CLC Number:

TL62+1

ZHAO Zi-qiang, LI Zai-xin, CAO Qi-xiang. Shielding design of container for radioactive waste of CFETR helium cooling blanket[J]. Nuclear Fusion and Plasma Physics, 2022, 42(2): 175-181.

赵自强, 栗再新, 曹启祥. CFETR氦冷包层放射性废物包装容器的屏蔽设计[J]. 核聚变与等离子体物理, 2022, 42(2): 175-181.

[1]	LUAN Zhen-bo, ZHOU Zhan-ru, HUANG Sheng-hong, YE Min-you. Investigation on the effect of buoyancy on the subcooled flow boiling heat transfer characteristics of in tube waters [J]. Nuclear Fusion and Plasma Physics, 2022, 42(2): 236-243.
[2]	ZHAO Yao, ZHANG Xiu-jie, PAN Chuan-jie, XU Zeng-yu, WANG Lei, WANG Fan. Investigation of magnetic field distribution in ferritic steel rectangular duct under external strong magnetic fields [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2021, 41(2): 178-182.
[3]	HU Wan-peng, CAI Lai-zhong. Particle simulation of heat deposition on the ITER-like divertor tile surface [J]. Nuclear Fusion and Plasma Physics, 2021, 41(1): 16-20.
[4]	WANG Kai-song, YANG Hao, XU Kun. Electromagnetic-structural coupling analysis of CFETR water cooled blanket [J]. Nuclear Fusion and Plasma Physics, 2021, 41(1): 45-50.
[5]	ZHOU Yi-fu1, MAO Shi-feng1, ZHAO Deng2, YE Min-you1, 3. Simulation study of the radiative divertor under different gas puffing locations for CFETR [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2020, 40(4): 336-343.
[6]	QIAN Wei, ZHENG Peng-fei, WANG Lian, XU Li-sha,LIU Xing, WEI Ran, BAI Quan, CHE Tong. Study of early stage surface evolution of molybdenum coated tungsten bombarded by helium plasma [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2020, 40(2): 142-147.
[7]	WANG Wei-hua1, 2, CHENG De-sheng2, DENG Hai-fei2,WANG Xiao-yu3, CHU De-lin1, LIU Sheng1. Coupled heat transfer characteristics study of multi-flow field between lead lithium and helium gas for liquid blanket breeder zone of fusion reactor [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(4): 309-316.
[8]	ZHANG Long, LU Yong, CAI Li-jun, LIU Yu-xiang,YUAN Ying-long, LIU Jian, LAI Chun-lin. Research on flow-induced-vibration of the cooling system in HL-2M divertor [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(4): 317-323.
[9]	YAO Wei-zhi, WANG Jin-chuan, DENG Li, CHEN Chang-an, GAO Bo. Progress of dust research in plasma devices [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(4): 362-372.
[10]	WANG Zhen-zhong, CAI Lai-zhong, LIU Ping, LIU Min-Jia, Imran Muhammad, DING Hong-bin. Analyzing the deposition layer on the carbon tiles of HL-2A with laser-induced breakdown spectroscopy [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2018, 2(2): 170-176.
[11]	LU Yong, CAI Li-jun, HUANG Yun-cong, LIU Jian, LIU Yu-xiang, ZHENG Guo-yao. Studies on structural parameters influencing the cooling performance of HL-2M divertor target plat [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2018, 2(2): 177-183.
[12]	ZHAO Li, LUO Cui-wen, SONG Xian-ming, XIA Fan, CHEN Liao-yuan. Study on operation and management of measurement and control systems on HL-2M tokamak [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2018, 2(2): 228-235.
[13]	ZHOU Bing, FENG Yong-jin, WANG Xiao-yu, WU Xin-hua. Study of equivalent heat conductivity in the Li4SiO4 pebble bed [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2018, 2(1): 99-104.
[14]	LI Xin-ze, WU Xin-hua, WANG Xiao-yu, LI Qiang. Thermal-hydraulic analyses of HCCB TBM shield [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2017, 37(4): 422-428.
[15]	SUN Zhao-xuan, LI Qiang, WANG Wan-jing, WANG Ji-chao, WANG Xin-li, WEI Ran, XIE Chun-yi, LUO Guang-nan. High heat flux test and post examination of ITER divertor W/Cu monoblock mock-ups [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2017, 37(4): 446-451.

Shielding design of container for radioactive waste of CFETR helium cooling blanket

CFETR氦冷包层放射性废物包装容器的屏蔽设计

PDF

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Recommended Articles

Metrics