Tailoring Microstructure of Austenitic Stainless Steel with Improved Performance for Generation-IV Fast Reactor Application: A Review

被引:19
作者
Chen, Shenghu [1 ]
Xie, Ang [1 ,2 ]
Lv, Xinliang [1 ,2 ]
Chen, Sihan [1 ]
Yan, Chunguang [3 ]
Jiang, Haichang [1 ]
Rong, Lijian [1 ]
机构
[1] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
[2] Univ Sci & Technol China, Sch Mat Sci & Engn, Hefei 230026, Peoples R China
[3] China Inst Atom Energy CIAE, Beijing 102413, Peoples R China
基金
中国国家自然科学基金;
关键词
fast reactor; austenitic stainless steel; improved performance; delta-ferrite; grain size; secondary phase evolution; LOW-CYCLE FATIGUE; GRAIN-SIZE; MECHANICAL-PROPERTIES; CREEP STRENGTH; STRUCTURAL-MATERIALS; MATERIALS CHALLENGES; TERNARY ALLOYS; CORE MATERIALS; NUCLEAR-POWER; DELTA-FERRITE;
D O I
10.3390/cryst13020268
中图分类号
O7 [晶体学];
学科分类号
0702 ; 070205 ; 0703 ; 080501 ;
摘要
Austenitic stainless steels are selected as candidate materials for in-core and out-of-core components of Generation-IV fast reactors due to their excellent operating experience in light-water reactors over several decades. However, the performance of conventional austenitic stainless steels proves to be inadequate through operation feedback in fast reactors. To withstand the demands for material performance exposure to the extreme operating environment of fast reactors, modified austenitic stainless steels for in-core and out-of-core components have been developed from the first-generation 300-series steels. The design of an appropriate microstructure becomes a top priority for improving material performance, and key metallurgical features including delta-ferrite content, grain size and secondary phase precipitation pertinent to austenitic stainless steel are focused on in this paper. delta-ferrite content and grain size are closely correlated with the fabrication program and their effects on mechanical properties, especially creep and fatigue properties are critically assessed. Moreover, the impacts of some major elements including nitrogen, stabilization elements (Nb, Ti, V), phosphorus and boron on secondary phase precipitation behaviors during aging or creep are reviewed in detail. Based on the role of the aforementioned metallurgical features, the recommended specification of nitrogen content, stabilization ratio, phosphorus content, boron content, delta-ferrite content and grain size are put forward to guarantee the best-expected performance, which could provide reactors designers with attractive options to optimize fast reactor systems.
引用
收藏
页数:18
相关论文
共 102 条
[1]   Effect of TiC and NbC carbides on creep life of stainless steels [J].
Abe, F. ;
Murata, M. ;
Miyazaki, H. .
MATERIALS AT HIGH TEMPERATURES, 2019, 36 (01) :35-47
[2]   Generation-IV nuclear power: A review of the state of the science [J].
Abram, Tim ;
Ion, Sue .
ENERGY POLICY, 2008, 36 (12) :4323-4330
[3]  
[Anonymous], 2016, JSME COD NUCL POW GE
[4]  
[Anonymous], 2015, ASME Boiler and Pressure Vessel Code
[5]   A summary of sodium-cooled fast reactor development [J].
Aoto, Kazumi ;
Dufour, Philippe ;
Yang Hongyi ;
Glatz, Jean Paul ;
Kim, Yeong-il ;
Ashurko, Yury ;
Hill, Robert ;
Uto, Nariaki .
PROGRESS IN NUCLEAR ENERGY, 2014, 77 :247-265
[6]   INFLUENCE OF POLYCRYSTAL GRAIN SIZE ON SEVERAL MECHANICAL PROPERTIES OF MATERIALS [J].
ARMSTRONG, RW .
METALLURGICAL TRANSACTIONS, 1970, 1 (05) :1169-+
[7]   Quantification of hardening contribution of G-Phase precipitation and spinodal decomposition in aged duplex stainless steel: APT analysis and micro-hardness measurements [J].
Badyka, R. ;
Monnet, G. ;
Saillet, S. ;
Domain, C. ;
Pareige, C. .
JOURNAL OF NUCLEAR MATERIALS, 2019, 514 (266-275) :266-275
[8]   Interplay Between Grain Boundaries and Radiation Damage [J].
Barr, Christopher M. ;
El-Atwani, Osman ;
Kaoumi, Djamel ;
Hattar, Khalid .
JOM, 2019, 71 (04) :1233-1244
[9]  
Buckthorpe D, 2017, WOODHEAD PUBL SER EN, P1, DOI 10.1016/B978-0-08-100906-2.00001-X
[10]   NITROGEN STRENGTHENING OF A STABLE AUSTENITIC STAINLESS-STEEL [J].
BYRNES, MLG ;
GRUJICIC, M ;
OWEN, WS .
ACTA METALLURGICA, 1987, 35 (07) :1853-1862