Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiation

JOURNAL OF NUCLEAR MATERIALS

卷:514

Article

Barcellini, C.¹  Harrison, R. W.²  Dumbill, S.³  Donnelly, S. E.²  Jimenez-Melero, E.¹ 

[1] Univ Manchester, Sch Mat, Mat Performance Ctr, Oxford Rd, Manchester M13 9PL, Lancs, England

[2] Univ Huddersfield, Sch Comp & Engn, Huddersfield HD1 3DH, W Yorkshire, England

[3] Natl Nucl Lab, Sellafield CA20 1PG, Seascale, England

关键词: Austenitic stainless steel;    In-situ proton irradiation;    Dislocation analysis;    Transmission electron microscopy;    Advanced gas-cooled reactor;   

DOI  :  10.1016/j.jnucmat.2018.11.019

来源: Elsevier

【 摘 要 】

We have monitored in situ the lattice defect evolution induced by proton irradiation in 20Cr-25Ni Nb-stabilised stainless steel, used as fuel cladding material in advanced gas-cooled reactors. At 420 degrees C, the damaged microstructure is mainly characterised by black spots and faulted a(0)/3 < 111 > Frank loops. Defect saturation is reached at only 0.1dpa. In contrast, at 460 degrees C and 500 degrees C proton bombardment induces the formation of a mixture of a(0)/3 < 111 > Frank loops and perfect a(0)/2 < 110 > loops. These perfect loops evolve into dislocation lines that form a dense network. This transition coincides with the saturation in the dislocation loop size and number density at 0.8dpa (460 degrees C) and 0.2dpa (500 degrees C), respectively. The presence of a high density of dislocation loops and lines at those two temperatures causes a vacancy supersaturation in the matrix, leading to the formation of voids and stacking fault tetrahedra. (C) 2018 Elsevier B.V. All rights reserved.

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