Effect of irradiation on stress corrosion cracking in supercritical water

被引:43
作者
Teysseyre, S. [1 ]
Jiao, Z. [1 ]
West, E. [1 ]
Was, G. S. [1 ]
机构
[1] Univ Michigan, Ann Arbor, MI 48109 USA
关键词
D O I
10.1016/j.jnucmat.2007.05.008
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Proton irradiation was used to study the effect of irradiation on stress corrosion cracking of 316L stainless steel and nickel-base alloy 690 in supercritical water (SCW). Irradiation to 7 dpa at 400 degrees C and 500 degrees C resulted in increased stress corrosion cracking (SCC) in SCW over the unirradiated case with the severity increasing with temperature. Irradiation results in significant radiation-induced segregation, formation of dislocation loops and voids (at 500 degrees C) and hardening. Neither RIS nor irradiation hardening correlates with SCC susceptibility. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:107 / 117
页数:11
相关论文
共 22 条
[1]  
AST, 1989, ANN BOOK ASTM STAND, pD9
[2]   Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals [J].
Bruemmer, SM ;
Simonen, EP ;
Scott, PM ;
Andresen, PL ;
Was, GS ;
Nelson, JL .
JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (03) :299-314
[3]  
BRUMMER SM, 1993, P 6 INT S ENV DEGR M, P537
[4]   The relationship between hardness and yield stress in irradiated austenitic and ferritic steels [J].
Busby, JT ;
Hash, MC ;
Was, GS .
JOURNAL OF NUCLEAR MATERIALS, 2005, 336 (2-3) :267-278
[5]   Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels [J].
Busby, JT ;
Was, GS ;
Kenik, EA .
JOURNAL OF NUCLEAR MATERIALS, 2002, 302 (01) :20-40
[6]  
FARREL K, 2002, ORNLTM200266
[7]  
FOURNIER L, 2001, 01361 NACE
[8]  
FUJISAWA R, 2005, 05395 NACE INT
[9]  
GOODWIN CC, 1997, ASTM STP, V1325
[10]   Microstructural evolution of proton irradiated T91 [J].
Gupta, G. ;
Jiao, Z. ;
Ham, A. N. ;
Busby, J. T. ;
Was, G. S. .
JOURNAL OF NUCLEAR MATERIALS, 2006, 351 (1-3) :162-173