Primary analysis of radiation damage on first wall and the outboard blanket on equatorial plane for CFETR

Wei SHI; Qin ZENG; Wei LI; Hongli CHEN

doi:10.11889/j.0253-3219.2016.hjs.39.120602

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Primary analysis of radiation damage on first wall and the outboard blanket on equatorial plane for CFETR

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-24

- Primary analysis of radiation damage on first wall and the outboard blanket on equatorial plane for CFETR
- NUCLEAR TECHNIQUES Vol. 39, Issue 12, Article number: 120602(2016)
- 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：
- 基金信息：
  
  Fundamental Research Funds for the Central Universities
- DOI：10.11889/j.0253-3219.2016.hjs.39.120602
  CLC： TL613
- Received：05 September 2016，
  
  Revised：01 November 2016，
  
  Published：2016-12
- 稿件说明：
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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：

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:

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:

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:

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:

The results cover the neutron radiation damage distribution of first walls and the structure material of CFETR outboard blanket.

Conclusion:

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

Wan Y.Consideration of the missions of CFETR[C].2012 ITER Training Forum & Second Workshop on MFE Development Strategy in China, Hefei, 2012

Y T Song , S T Wu , J G Li , . Concept design of CFETR tokamak machine . IEEE Transactions on Plasma Science , 2014 . 42 ( 3 ): 503 - 509 . DOI: 10.1109/TPS.2014.2299277 http://doi.org/10.1109/TPS.2014.2299277 .

Q Zeng , H Chen , Z Lyu , . Impact analysis of the model on CFETR neutronics calculation . Journal of Fusion Energy , 2016 . 35 ( 4 ): 1 - 6 . https://www.researchgate.net/profile/Zhongliang_Lv/publication/299552461_Impact_Analysis_of_the_Model_on_CFETR_Neutronics_Calculation/links/5719d63f08aed8a339e70761.pdf?origin=publication_detail .

吕中良.CFETR氦冷固态氚增殖剂包层中子学设计及性能研究[D].合肥:中国科学技术大学, 2016 http://cdmd.cnki.com.cn/Article/CDMD-10358-1016102042.htm

LYU Zhongliang.Neutronics design and analysis of helium cooled solid breeder blanket for CFETR[D].Hefei:University of Science and Technology of China, 2016

Q Liu , M Li , S Wang , . Thermal-mechanical analysis of the first wall for CFETR helium cooled solid breeder blanket . Annals of Nuclear Energy , 2015 . 85 12 - 16 . DOI: 10.1016/j.anucene.2015.04.030 http://doi.org/10.1016/j.anucene.2015.04.030 .

Cambi G, Cepraga D G, Frisoni M, et al.Neutron irradiation effects on the ITER-EDA and ITER-RC first wall/blanket materials[C].18th Symposium on Fusion Engineering, IEEE, 1999:330-333

M Kaufmann , R Neu . Tungsten as first wall material in fusion devices . Fusion Engineering and Design , 2007 . 82 ( 5 ): 521 - 527 .

P Chen , M Ye , X Peng , . Preliminary thermo-hydraulic and mechanical analysis for CFETR divertor . Journal of Fusion Energy , 2015 . 34 ( 4 ): 901 - 904 . DOI: 10.1007/s10894-015-9892-9 http://doi.org/10.1007/s10894-015-9892-9 .

L Lu , U Fischer , P Pereslavtsev . Improved algorithms and advanced features of the CAD to MC conversion tool McCad . Fusion Engineering and Design , 2014 . 89 ( 9 ): 1885 - 1888 . https://www.researchgate.net/publication/263391265_Improved_algorithms_and_advanced_features_of_the_CAD_to_MC_conversion_tool_McCad .

Z Lyu , H Chen , C Chen , . Preliminary neutronics design and analysis of helium cooled solid breeder blanket for CFETR . Fusion Engineering and Design , 2015 . 95 79 - 83 . DOI: 10.1016/j.fusengdes.2015.04.038 http://doi.org/10.1016/j.fusengdes.2015.04.038 .

邹俊.聚变堆材料辐照损伤数值模拟初步研究[D].合肥:合肥工业大学, 2007 http://cdmd.cnki.com.cn/Article/CDMD-10359-2007101946.htm

ZOU Jun.Preliminary study on radiation damage for the material of the fusion system[D].Hefei:HeFei University of Technology, 2007

S Liu , J Li , S Zheng , . Neutronics analysis of inboard shielding capability for a DEMO fusion reactor CFETR . Fusion Engineering and Design , 2013 . 88 ( 9 ): 2404 - 2407 . https://www.researchgate.net/publication/275723235_Neutronics_analysis_of_inboard_shielding_capability_for_a_DEMO_fusion_reactor_CFETR .

S Ishino , P Schiller , A F Rowcliffe . Need for and requirements for a neutron irradiation facility for fusion materials testing . Journal of Fusion Energy , 1989 . 8 ( 3-4 ): 147 - 155 . DOI: 10.1007/BF01051645 http://doi.org/10.1007/BF01051645 .

Li J G.Closing gaps to CFETR readiness[C].IAEA TCM 3rd DEMO Workshop, Hefei, China, 2015:11-14

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