快中子反应堆(快堆)的核心结构材料(如燃料包壳等)在服役过程中将承受长期的高通量的中子辐照、高温和嬗变反应产生的He的作用,引起的合金微观结构的改变,导致材料力学性能的严重恶化.高性能抗辐照材料成为快堆发展的关键前提条件之一.本文介绍快堆中辐照引起的金属材料微观结构的变化.
参考文献
[1] | Was G S.Fundamentals of radiation materials science:metals and alloys[M].New York:Springer-Verlag,2007 |
[2] | D.J. Bacon;Yu. N. Osetsky .Modelling atomic scale radiation damage processes and effects in metals[J].International Materials Reviews,2002(5):233-241. |
[3] | Domain C;Becquart CS;Malerba L .Simulation of radiation damage in Fe alloys: an object kinetic Monte Carlo approach[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2004(1):121-145. |
[4] | Jenkins M L;Kirk M A.Characterisation of radiation damage by transmission electron microscopy[M].Bristol and Philadelphia:IOP Publishing,2001 |
[5] | Norgett M J;Robinson M T;Torrens I M .A proposed method of calculating displacement dose rates[J].Nuclear Engineering and Design,1975,33(01):50-55. |
[6] | Schilling W;Ullmaier H.Physics of radiation damage in metals[A].Germany and USA,VCH,1994:10B,179. |
[7] | Garner FA.;Sencer BH.;Toloczko MB. .Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2000(0):123-142. |
[8] | Brailsford A D;Bullough R .The rate theory of swelling due to void growth in irradiated metals[J].Journal of Nuclear Materials,1972,44(02):121-135. |
[9] | Brailsford A D;Bullough R .Void growth and its relation to intrinsic point defect properties[J].Journal of Nuclear Materials,1978,69-70:434-450. |
[10] | Semenov AA.;Woo CH. .Classical nucleation theory of microstructure development under cascade-damage irradiation[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2003(2/3):192-204. |
[11] | 张崇宏,杨义涛,宋银,J.S.Jang,孙友梅,金运范,李炳生.一种低活化铁素体/马氏体钢的高能重离子辐照效应研究[J].原子核物理评论,2009(01):48-54. |
[12] | Little E A.Void swelling resistance of ferritic steels:new perspectives[A].Bristol and Philadelphia:lOP Publishing,1992:141-146. |
[13] | English C A;Murphy S M;Perks J M .Radiation-induced segregation in metals[J].Journal of the Chemical Society,Faraday Transactions,1990,86(08):1263-1271. |
[14] | R.G. Faulkner .Segregation to boundaries and interfaces in solids[J].International Materials Reviews,1996(5):198-208. |
[15] | Lu Z;Faulkner RG;Sakaguchi N;Kinoshita H;Takahashi H;Flewitt PEJ .Control of phosphorus inter-granular segregation in ferritic steels[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2004(0):1017-1021. |
[16] | Lu Z;Faulkner RG;Sakaguchi N;Kinoshita H;Takahashi H;Flewitt PEJ .Effect of hafnium on radiation-induced inter-granular segregation in ferritic steel[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2006(1/3):155-161. |
[17] | Little E A;Morgan T S;Faulkner R G .Microchemistry of neutron irradiated 12% CrMoVNb martensitic steel[J].Materials Science Forum,1992,97-99:323-328. |
[18] | Wiedersich H;Okamoto P R;Lam N Q .A theory of radiation-induced segregation in concentrated alloys[J].Journal of Nuclear Materials,1979,83(01):98-108. |
[19] | Lu, Z;Faulkner, RG;Morgan, TS .Formation of austenite in high Cr ferritic/martensitic steels by high fluence neutron irradiation[J].Journal of Nuclear Materials,2008(2/3):223-228. |
[20] | Cauvin R;Martin G .Radiation induced homogeneous precipitation in undersaturated solid-solutions[J].Journal of Nuclear Materials,1979,83(01):67-78. |
[21] | Garner F A;Cahn R.W.Materials science and technology: Nuclear materials[M].Wiley VCH,1994:419. |
[22] | Little E A .Microstructural evolution in irradiated ferritic-martensitic steels:transiitions to high dose behaviour[J].Journal of Nuclear Materials,1993,206:324-334. |
[23] | Little E A;Stoter L P.Advances in the physical metallurgy and applications of steels[A]. |
[24] | Harries D R .Neutron irradiation-induced embrittlement in type 316 and other austenitic steels and alloys[J].Journal of Nuclear Materials,1979,82(01):2-21. |
[25] | S.J.Zinkle;N.M.Ghoniem .Operating temperature windows for fusion reactor structural materials[J].Fusion engineering and design,2000(0):55-71. |
[26] | Zinkle SJ .Fusion materials science: Overview of challenges and recent progress[J].Physics of plasmas,2005(5):8101-1-8101-8-0. |
[27] | Bloom EE;Busby JT;Duty CE;Maziasz PJ;McGreevy TE;Nelson BE;Pint BA;Tortorelli PF;Zinkle SJ .Critical questions in materials science and engineering for successful development of fusion power[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2007(a):1-10. |
[28] | Hishinuma A;Kohyama A;Klueh R L et al.Current status and future R&D for reduced-activation ferritic/martensitic steels[J].Journal of Nuclear Materials,1998,258-263:193-204. |
[29] | Trinkaus H .On the modeling of the high-temperature embrittlement of metals containing helium[J].Journal of Nuclear Materials,1983,118:39-49. |
[30] | Yamamoto T;Odette GR;Kishimoto H;Rensman JW;Miao PF .On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of similar to 8Cr tempered martensitic steels: Compilation and analysis of existing data[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2006(1/3):27-49. |
[31] | 王志光.利用高能离子模拟研究反应堆结构材料中的辐照效应[J].原子核物理评论,2006(02):155-160. |
[32] | Maziasz P J;McHargue C J .Microstructural evolution in annealed austenitic steels during neutron irradiation[J].International Materials Reviews,1987,32:190-219. |
[33] | Morgan T S;Little E A;Faulkner R G et al.lnteffacial segregation in fast reactor irradiated 12% chromium martensitic steel[J].ASTM Stp,1992,1125:633-644. |
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