Effect of Hafnium on Radiation-induced Inter-granular Segregation in Ferritic Steel

Acta Metall Sin

2006, Vol. 42

Issue (10): 1041-1045 DOI:

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Effect of Hafnium on Radiation-induced Inter-granular Segregation in Ferritic Steel

英国Loughborough University; Inst. Polymer Technology & Material Engineering

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. Effect of Hafnium on Radiation-induced Inter-granular Segregation in Ferritic Steel. Acta Metall Sin, 2006, 42(10): 1041-1045 .

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Abstract Ferritic steels with and without hafnium (Hf) addition were irradiated by 250 keV nickel-ions at 300 oC in a ion accelerator attached to the Multi-beam High Voltage Electron Microscope (JEOL ARM1300) to study the influence of Hf additions on radiation-induced segregation in a ferritic/martenitic steel. Grain boundary segregation of phosphorus, silicon, chromium and molybdenum were measured by field emission gun transmission electron microscopy with an energy dispersive analyser. The results show that radiation induces the enrichment of undersized atoms (P) and the depletion of oversized atoms (Cr) in the materials without Hf addition. The addition of Hf suppresses radiation-induced undersized atom enrichment and oversized atom depletion. A radiation-induced non-equilibrium segregation (RIS) model is developed to predict undersized and oversized atom segregation behaviour at the grain boundary. The effect of hafnium on freely migrating defect population is discussed and estimated to indicate the effect of the element on segregation behaviour of the elements like P and Cr in the ferritic steel. The predicted results are compared with experimental data.

Key words: hafnium Radiation Inter-granular Segregation Ferritic Steel

Received: 23 March 2006

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[1]English C A,Ortner S R,Gage G,Server W L,Rosinski S T.ASTM STP 1405,2001
[2]Shoji T,Suzuki S,Raja K S.J Nucl Mater,1998;258-263:241
[3]Kato T,Takahashi H,Izumiya M.Mater Trans JIM,1991;32:921
[4]Kato T,Takahashi H,Izumiya M.J Nucl Mater,1992;189:167
[5]Kato T,Takahashi H,Izumiya M.J Atom Energy Soc Jpn,1992;34:889
[6]Fournier L,Sencer B H,Was G S,Simonen E P,Bruemmer S M.J Nucl Mater,2003;321:192
[7]Shigenaka N,Ono S,Isobe Y,Hashimoto T,Fujimori H,Uchida S.J Nucl Sci Technol,1996;33:577
[8]Watanabe H,Muroga T,Yoshida N.J Nucl Mater,1996;239:95
[9]Dumbill S,Hanks W.Proc 6th Int Symp on Environmental Degragdation of Materials in Nuclear Power System—Water Reactors,San Diego,CA,The Minerals,Metal & Materials Society,1993:521
[10]Lu Z,Faulkner R G,Sakaguchi N,Kinoshita H,Takahashi H,Flewitt P E J.J Nucl Mater,2004;329-333:1017
[11]Lee E H.Nucl Instrum Methods Phys Res,1999;151B:29
[12]Faulkner R G,Flewitt P E J,Lu Z.ASTM STP 1447,2004
[13]Faulkner R G,Song S H,Flewitt P E J.Mater Sci Technol,1996;12:904
[14]Ackland G J,Mendelev M I,Srolovitz D J,Han S,Barashev A V.J Phys:Condens Matter,2004;16:S2629
[15]Barashev A V.In:Ghoniem N M ed.,Proc 2nd Int Conf on Multiscale Materials Modelling,Los Angeles,California,USA:Mechanical & Aerospace Eng Dept,UCLA,2004:483
[16]Faulkner R G,Song S,Flewitt P E J,Victoria M,Marmy P.J Nucl Mater,1998;255:189
[17]Faulkner R G,Jones R B,Lu Z,Flewitt P E J.Philos Mag,2005;85:2065
[18]Goodwin C C.PhD Dissertation,Loughborough University,UK,1998
[19]Goodwin C C,Faulkner R G,Fisher S B.ASTM STP 1325,1999
[20]Faulkner R G,Morgan T S,Little E A.X-Ray Spectrom,1994;23:195

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