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CFETR第一壁及赤道面外包层中子辐照损伤初步分析
Primary analysis of radiation damage on first wall and the outboard blanket on equatorial plane for CFETR
- 核技术 2016年39卷第12期 文章编号：120602
- 作者机构：
中国科学技术大学 核科学技术学院 合肥 230027
- 作者简介：
[ "石巍, 男, 1994年出生, 现为中国科学技术大学本科生, 核工程与核技术专业, 参加\"CFETR超导线圈屏蔽性能分析研究\"大学生创新创业计划", "SHI Wei, male, born in 1994, undergraduate in University of Science and Technology of China, major in nuclear engineering and technology, participate in \"The analysis of shielding performance for superconducting coils for CFETR\" National Undergraduate Training Programs for Innovation and Entrepreneurship" ]
曾勤, E-mail:zengqin@ustc.edu.cn ZENG Qin, E-mail:zengqin@ustc.edu.cn
- 基金信息：中央高校基本科研专项基金(No.WK2140000008)
DOI：10.11889/j.0253-3219.2016.hjs.39.120602
中图分类号： TL613收稿日期：2016-09-05，
修回日期：2016-11-01，
纸质出版日期：2016-12
- 稿件说明：
移动端阅览
石巍, 曾勤, 李卫, 等. CFETR第一壁及赤道面外包层中子辐照损伤初步分析[J]. 核技术, 2016,39(12):120602
Wei SHI, Qin ZENG, Wei LI, et al. Primary analysis of radiation damage on first wall and the outboard blanket on equatorial plane for CFETR[J]. Nuclear techniques, 2016, 39(12): 120602
石巍, 曾勤, 李卫, 等. CFETR第一壁及赤道面外包层中子辐照损伤初步分析[J]. 核技术, 2016,39(12):120602 DOI： 10.11889/j.0253-3219.2016.hjs.39.120602.
Wei SHI, Qin ZENG, Wei LI, et al. Primary analysis of radiation damage on first wall and the outboard blanket on equatorial plane for CFETR[J]. Nuclear techniques, 2016, 39(12): 120602 DOI： 10.11889/j.0253-3219.2016.hjs.39.120602.
摘要
中国聚变工程实验堆（Chinese Fusion Engineering Testing Reactor，CFETR）的包层和偏滤器第一壁面向堆芯等离子体，第一壁辐照损伤分析对于托克马克安全运行至关重要。赤道面外包层较其它包层距离堆芯等离子体中心更近，其结构材料承受中子辐照大。因此，进行中子辐照损伤评估十分必要。基于此目的，采用计算机辅助设计（Computer Aided Design，CAD）模型和蒙特卡罗中子学建模转换接口McCAD完成中子学建模，并用蒙特卡罗方法的粒子输运程序计算第一壁和氦冷固态外包层结构材料辐照损伤。此外，对比了铍和钨作为面向等离子体材料两种情况下第一壁的受损情况。计算结果表明，氦冷固态包层模型下结构材料可以满足CFETR一期的运行要求。
Abstract
Background:
2
Chinese Fusion Engineering Testing Reactor (CFETR) is an International Thermonuclear Experimental Reactor (ITER)-like test superconducting tokamak fusion reactor to bridge the gap between ITER and future fusion power plant. The first wall (FW) of blanket and divertor faces the plasma core directly
and the radiation damage of the FWs is an important parameter for tokamak design.
Purpose:
2
The purpose is to analyze radiation damage on the FWs and the out board blanket structure material on the equatorial plane through primary neutronic evaluation for CFETR to select a better armor material in two candidates-beryllium and tungsten.
Methods:
2
McCAD is used to convert the Computer Aided Design (CAD) model to Monte Carlo geometry model. And Monte Carlo particle transportation method is used to calculate the neutron radiation damage.
Results:
2
The results cover the neutron radiation damage distribution of first walls and the structure material of CFETR outboard blanket.
Conclusion:
2
Tungsten is better than beryllium to be the material of blanket first wall armor because has a better protection for blanket structure materials. The calculation results indicate that divertor and structure material of CFETR blanket can satisfy the radiation damage standard in 8 a's testing stage.
关键词
Keywords
references
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