Towards V-based high-entropy alloys for nuclear fusion applications

被引:87
作者
Barron, P. J. [1 ]
Carruthers, A. W. [1 ]
Fellowes, J. W. [1 ]
Jones, N. G. [2 ]
Dawson, H. [3 ]
Pickering, E. J. [1 ]
机构
[1] Univ Manchester, Dept Mat, Oxford Rd, Manchester M13 9PL, Lancs, England
[2] Univ Cambridge, Dept Mat Sci & Met, 27 Charles Babbage Rd, Cambridge CB3 0FS, England
[3] Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England
基金
英国工程与自然科学研究理事会;
关键词
High-entropy alloys; Refractory metals; Transition metals; VANADIUM ALLOYS; IRRADIATION;
D O I
10.1016/j.scriptamat.2019.09.028
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
By mixing elements with favourable nuclear activation properties to create high-entropy alloys, it may be possible to create a material that can withstand a nuclear fusion environment while minimising the radioactive waste produced. Such a material could be used in the extreme thermal and irradiation conditions of a fusion blanket. A suite of previously unexplored V-Cr-Mn and V-Cr-Mn-Ti alloys have been fabricated then homogenised and the resultant microstructures and phases were characterised. Results demonstrate that single-phase body centred cubic solid solution microstructures can be formed in highly-concentrated alloys incorporating low-activation elements, which is promising for a fusion alloy development standpoint. (C) 2019 Acta Materialia Inc. Published by Elsevier Ltd.
引用
收藏
页码:12 / 16
页数:5
相关论文
共 26 条
[1]   Low activation high entropy alloys for next generation nuclear applications [J].
Ayyagari, Aditya ;
Salloom, Riyadh ;
Muskeri, Saideep ;
Mukherjee, Sundeep .
MATERIALIA, 2018, 4 :99-103
[2]  
Carlson O.N., 1959, AMES LAB TECHNICAL R, V12
[3]   Overview of the vanadium alloy researches for fusion reactors [J].
Chen, J. M. ;
Chernov, V. M. ;
Kurtz, R. J. ;
Muroga, T. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :289-294
[4]   Development and testing of vanadium alloys for fusion applications [J].
Chung, HM ;
Loomis, BA ;
Smith, DL .
JOURNAL OF NUCLEAR MATERIALS, 1996, 239 (1-3) :139-156
[5]  
Fuda T., 2002, Journal of Alloys and Compounds, V330-332, P522, DOI DOI 10.1016/S0925-8388(01)01544-4
[6]   Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure [J].
Garner, FA ;
Toloczko, MB ;
Sencer, BH .
JOURNAL OF NUCLEAR MATERIALS, 2000, 276 (01) :123-142
[7]   Waste implications from minor impurities in European DEMO materials [J].
Gilbert, M. R. ;
Eade, T. ;
Rey, T. ;
Vale, R. ;
Bachmann, C. ;
Fischer, U. ;
Taylor, N. P. .
NUCLEAR FUSION, 2019, 59 (07)
[8]   A fracture-resistant high-entropy alloy for cryogenic applications [J].
Gludovatz, Bernd ;
Hohenwarter, Anton ;
Catoor, Dhiraj ;
Chang, Edwin H. ;
George, Easo P. ;
Ritchie, Robert O. .
SCIENCE, 2014, 345 (6201) :1153-1158
[9]  
Hoelzer D., 1999, TECHNICAL REPORT
[10]   Processing and properties of mild interstitial free steels [J].
Hoile, S .
MATERIALS SCIENCE AND TECHNOLOGY, 2000, 16 (10) :1079-1093