核聚变堆包层结构材料研究进展及展望

doi:10.11896/j.issn.1005-023X.2018.17.001

Abstract
Figure/Table
References
Related Citation (2)

Download:

Full Text ( PDF ) (2227KB)
Export: BibTeX | EndNote (RIS)

Abstract  With the advance of ITER and CFETR, issues concerning materials become a serious problem which limits the development of fusion energy. Blanket is an important components for energy transform, tritium sustain and radiation shielding. The development of structural materials which fit the requirement of the harsh service environment has become a research focus worldwide.
   Various blanket structural materials such as reduced activation ferritic/martensitic steels (RAFMs) have been developed for decades. Based on the Roadmap of Fusion Energy of China, the neutron irradiation dose in the structural materials can reach 10 dpa in Phase 1, and 50 dpa in Phase 2. Until now, there are no materials that can satisfy both the harsh working environment requirement and engineering building requirement.
   RAFM steels are the main candidate for the blanket structural materials. Several specification of RAFM steels have been deve-loped worldwide, and the database has been established. However, limited by the narrow working temperature range and the low creep strength at high temperature, RAFM steels cannot reach the requirement of the CFETR Phase 2 and future fusion reactor. Two method have been proposed, one is adding oxide dispersion phase into the steel to promote the high creep performance, the steels obtained by this method is called oxide dispersion strengthened steels (ODSs). This method can be further classified into two kinds depending on if the mechanical alloyed (MA) is needed in the manufacture process. The other method is based on computational thermodynamics modelling. The density of MX phase can be increased by modifying chemical composition and thermomechanical treatments. The ODSs obtained by MA have the best performance at high temperature and under irradiation, but it should be noted that the MA process is of high cost and low efficiency. The none-MA ODSs and modified RAFM steels have the properties close to those of the MA ODSs, and they are much cheaper than the MA ODSs with potential for large-scale manufacture. Except for structural materials based on iron, vanadium alloys and SiC composite materials are all candidates for blanket structural materials with some good properties over the steels. For vanadium alloys, their working upper temperature is low and they are not compatible with hydrogen isotopes, which limits the application of vanadium in fusion reactor. For SiC composite materials, the joint technology and large-scale manufacture remain as problems. For future fusion reactor, the irradiation dose of the structural materials is larger, thus the current candidate materials may not fully satisfy the requirement. In the future, two aspects should be attached great attention to, one is exploring the performance potential of existing materials with the help of new ideas and new methods of material design and preparation, the other one is development of new materials like the metallic glass composites and high-entropy alloys.
   According to the Roadmap of Fusion Reactor Materials of China, we review the development of the structural materials of the fusion blanket in this article. The development of RAFM steel, mechanical alloyed (MA)oxide dispersion strengthened steels (ODSs), vanadium alloys and SiCf/SiC has been introduced. In recent years, new types of structural materials emerge, such as mo-dified RAFMs and none-MA ODSs, which have also been described in this article. Finally, the authors look ahead the development of advanced structural materials with better performance.

Key words： nuclear fusion blanket structural materials

Published: 19 September 2018

CLC number:	TG142
	TG146

	Service
	E-mail this article
	Add to my bookshelf
	Add to citation manager
	E-mail Alert
	RSS
	Articles by authors
	XU Yuping
	LYU Yiming
	ZHOU Haishan
	LUO Guangnan

Cite this article:

XU Yuping,LYU Yiming,ZHOU Haishan, et al. A Review on the Development of the Structural Materials of the Fusion Blanket[J]. Materials Reports, 2018, 32(17): 2897-2906.

URL:

http://www.mater-rep.com/EN/10.11896/j.issn.1005-023X.2018.17.001 OR http://www.mater-rep.com/EN/Y2018/V32/I17/2897

1 The ITER Project. http://www.iter.org.
2 Peng Y K M, Canik J M, Diem S J, et al. Fusion nuclear science facility (FNSF) before upgrade to component test facility (CTF)[J].Fusion Science and Technology,2011,60(2):441.
3 Wan B, Ding S, Qian J, et al. Physics design of CFETR: Determination of the device engineering parameters[J].IEEE Transactions on Plasma Science,2014,42(3):495.
4 Wan Y, Li J, Liu Y, et al. Overview of the present progress and activities on the CFETR[J].Nuclear Fusion,2017,57(10):102009.
5 Bai Y Q, Chen H L, Liu S L, et al. Comparison analysis of fusion breeder blanket concepts[J].Chinese Journal of Nuclear Science and Engineering,2008,28(3):249(in Chinese).
柏云清,陈红丽,刘松林,等.聚变堆增殖包层概念特征比较研究[J].核科学与工程,2008,28(3):249.
6 Chen H L, Li M, Lv Z L, et al. Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR[J].Fusion Engineering and Design,2015,96-97:89.
7 Jiang K C, Li J, Zhang X K, et al. The dvelopment and application of one thermal-hydraulic program based on ANSYS for design of ceramic breeder blanket of CFETR[J].Journal of Fusion Energy,2015,34(5):1088.
8 Liu S L, Pu Y, Cheng X M, et al. Conceptual design of a water cooled breeder blanket for CFETR[J].Fusion Engineering and Design,2014,89(7-8):1380.
9 Cramer B A, Davis J W. Fracture-mechanics issues for irradiated blanket structures[J].Nuclear Engineering & Design,1980,58(2):267.
10 Benamati G, Fazio C, Ricapito I, Mechanical and corrosion beha-viour of EUROFER 97 steel exposed to Pb-17Li[J].Journal of Nuc-lear Materials,2002,307,1391.
11 Wrisley K L, Duquette D J, Steiner D, et al. Corrosion studies of a stainless-steel structure for the ITER aqueous lithium salt blanket concept[J].Fusion Engineering and Design,1990,13(1):45.
12 Bloom E E. Mechanical-properties of materials in fusion-reactor 1st-wall and blanket systems[J].Journal of Nuclear Materials,1979,s85-s86:795.
13 Kimura A. Overview of fusion structural materials options: Radiation effects on materials[C]//ICFRM-16. Beijing,2013.
14 王宇钢.中国磁约束聚变堆材料发展路线图[C]//第四届核聚变堆材料论坛.江油,2017.
15 Chen Changan, Liu Changsong, Liu Xiang, et al. Roadmap and developments of fusion reactor materials for CFETR[C]//2nd Technical Exchange Meeting on CFETR and EU-DEMO Fusion Reactor Design.Beijing,2018.
16 Tavassoli A A F, Diegele E, Lindau R, et al. Current status and recent research achievements in ferritic/martensitic steels[J].Journal of Nuclear Materials,2014,455(1-3):269.
17 Wang P, Chen J, Fu H, et al. Effect of N on the precipitation beha-viours of the reduced activation ferritic/martensitic steel CLF-1 after thermal ageing[J].Journal of Nuclear Materials,2013,442(1-3):S9.
18 Huang Q Y, Yu J N, Wan F R, et al. The development of low activation martensitic steels for fusion reactor[J].Chinese Journal of Nuclear Science and Engineering,2004,24(1):56(in Chinese).
黄群英,郁金南,万发荣,等.聚变堆低活化马氏体钢的发展[J].核科学与工程,2004,24(1):56.
19 Feng K M, Pan C H, Zhang G S, et al. Chinese, progress on solid breeder TBM at SWIP[J].Fusion Engineering and Design,2010,85(10-12):2132.
20 Feng K M, Zhang G S, Hu G, et al. New progress on design and R&D for solid breeder test blanket module in China[J].Fusion Engineering and Design,2014,89(7-8):1119.
21 Xiong X, Yang F, Zou X, et al. Effect of twice quenching and tempering on the mechanical properties and microstructures of SCRAM steel for fusion application[J].Journal of Nuclear Materials,2012,430(1-3):114.
22 Yu C, Yang F, Suo J, et al. The effect of Ti, N and V content and heat treatment on irradiation and mechanical property of SCRAM steels[C]//International Conference on Nuclear Engineering.Prague,2014.
23 Shi Q, Liu J, Luan H, et al. Oxidation behavior of ferritic/martensitic steels in stagnant liquid LBE saturated by oxygen at 600 ℃[J].Journal of Nuclear Materials,2015,457:135.
24 Yang K, Yan W, Wang Z G, et al. Development of a novel structu-ral material (simp steel) for nuclear equipment with balanced resis-tances to high temperature,radiation and liquid metal corrosion[J].Acta Metallurgica Sinica,2016,52(10):1207(in Chinese).
杨柯,严伟,王志光,等.核用新型耐高温、抗辐照、耐液态金属腐蚀结构材料——SIMP钢的研究进展[J].金属学报,2016,52(10):1207.
25 Tanigawa H, Gaganidze E, Hirose T, et al. Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications[J].Nuclear Fusion,2017,57(9):092004.
26 Aubert P, Tavassoli F, Rieth M, et al. Review of candidate welding processes of RAFM steels for ITER test blanket modules and DEMO[J].Journal of Nuclear Materials,2011,417(1-3):43.
27 Zhang X, Liu S, Zhu Q, et al. Activation and environmental aspects of in-vacuum vessel components of CFETR[J].Plasma Science & Technology,2016,18(11):1130.
28 Kimura A, Kasada R, Iwata N, et al. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems[J].Journal of Nuclear Materials,2011,417(1-3):176.
29 Zinkle S J, Mslang A, Muroga T, et al. Multimodal options for materials research to advance the basis for fusion energy in the ITER era[J].Nuclear Fusion,2013,53(10):4024.
30 Lu C, Lu Z, Wang X, et al. Enhanced radiation-tolerant oxide dispersion strengthened steel and its microstructure evolution under helium-implantation and heavy-ion irradiation[J].Scientific Reports,2017,7:40343.
31 Azevedo C R F. Selection of fuel cladding material for nuclear fission reactors[J].Engineering Failure Analysis,2011,18(8):1943.
32 Tan L, Snead L L, Katoh Y. Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors[J].Joural of Nuclear Materials,2016,478:42.
33 Tan L, Katoh Y, Tavassoli A A F, et al. Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service[J].Journal of Nuclear Materials,2016,479:515.
34 Lizhen Tan, Lance Snead. Development of castable nanostructured alloys(CNAs) as a new generation RAFM steels[C]//The 18th International Conference on Fusion Reactor Materials (ICFRM-18). Aomori, Japan,2017.
35 Zinkle S J, Boutard J L, Hoelzer D T, et al. Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications[J].Nuclear Fusion,2017,57(9):092005.
36 Stork D, Agostini P, Boutard J L, et al. Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment[J].Journal of Nuclear Materials,2014,455(1-3):277.
37 Stork D, Agostini P, Boutard J L, et al. Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group[J].Fusion Engineering and Design,2014,89(7-8):1586.
38 Rieken J R, Anderson I E, Kramer M J, et al. Reactive gas atomization processing for Fe-based ODS alloys[J].Journal of Nuclear Materials,2012,428(1-3):65.
39 Gil E, Ordas N, Garcia-Rosales C, et al. ODS ferritic steels produced by an alternative route (STARS): Microstructural characterisation after atomisation, HIPping and heat treatments[J].Powder Metallurgy,2016,59(5):359.
40 Y Q, Xia M. Vacuum casted F/M Steels containing a dense uniform dispersion of oxides nanoclusters with high strength and irradiation resistance stability[C]//The 18th International Conference on Fusion Reactor Materials (ICFRM-18).Aomori,Japan,2017.
41 Wang W, Wu E, Liu S, et al. Segregation and precipitation formation for in situ oxidised 9Cr steel powder[J].Metal Science Journal,2015,33(1):104.
42 Muroga T. 4.12-Vanadium for nuclear systems[J].Comprehensive Nuclear Materials,2012,189(4):391.
43 郝嘉琨.聚变堆材料[M].北京:化学工业出版,2007.
44 Muroga T, Chen J M, Chernov V M, et al. Review of advances in development of vanadium alloys and MHD insulator coatings[J].Journal of Nuclear Materials,2007,367(10):780.
45 Duan X R, Chen J M, Feng K M, et al. Progress in fusion technology at SWIP[J].Fusion Engineering and Design,2016,109:1022.
46 Tanabe T. Tritium issues to be solved for establishment of a fusion reactor[J].Fusion Engineering and Design,2012,87(5-6):722.
47 Richardson I A, Leachman J W. Thermodynamic properties status of deuterium and tritium[J].Advances in Cryogenic Engineering,2012,57a-57b(1434):1841.
48 Roth J, Tsitrone E, Loarte A, et al. Recent analysis of key plasma wall interactions issues for ITER[J].Journal of Nuclear Materials,2009,390-391:1.
49 Shimada M, Pitts R, Loarte A, et al. ITER research plan of plasma-wall interaction[J].Journal of Nuclear Materials,2009,390-391:282.
50 Farabolini W, Ciampichetti A, Dabbene F, et al. Tritium control modelling for a helium cooled lithium-lead blanket of a fusion power reactor[J].Fusion Engineering and Design,2006,81(1):753.
51 Frazer D, Abad M D, Krumwiede D, et al. Localized mechanical property assessment of SiC/SiC composite materials[J].Composites Part A Applied Science & Manufacturing,2015,70:93.
52 Yoshida K, Akimoto H, Yano T, et al. Mechanical properties of unidirectional and crossply SiCf/SiC composites using SiC fibers with carbon interphase formed by electrophoretic deposition process[J].Progress in Nuclear Energy,2014,82:148.
53 Snead L L, Nozawa T, Ferraris M, et al. Silicon carbide composites as fusion power reactor structural materials[J].Journal of Nuclear Materials,2011,417(1-3):330.
54 Hu Z Q, Zhang H F. Recent progress in the area of bulk amorphous alloys and composites[J].Acta Metallurgica Sinica,2010,46(11):1391(in Chinese).
胡壮麒,张海峰.块状非晶合金及其复合材料研究进展[J].金属学报,2010,46(11):1391.
55 Song W, Wu Y, Wang H, et al. Microstructural control via copious nucleation manipulated by in situ formed nucleants: Large-sized and ductile metallic glass composites[J].Advanced Materials,2016,28(37):8156.
56 Yeh J W, Chen S K, Lin S J, et al. Nanostructured high-entropy alloys with multiple principal elements: Novel alloy design concepts and outcomes[J].Advanced Engineering Materials,2004,6(5):299.
57 Gludovatz B, Hohenwarter A, Catoor D, et al. A fracture-resistant high-entropy alloy for cryogenic applications[J].Science,2014,345(6201):1153.
58 Kumar N, Li C, Leonard K J, et al. Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation[J].Acta Materialia,2016,113:230.