Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments

Abstract The effects of irradiation on stress corrosion cracking occur through changes in the water chemistry and in the alloy microstructure. Considerable reactor experience has shown that a high-temperature water environment and a radiation field combine to produce irradiation-assisted stress corrosion cracking (IASCC) in core components of light water reactors. The principal effect of irradiation on water chemistry is through radiolysis, which results in an increase in the corrosion potential through the formation of radiolytic species consisting of radicals and molecules that can be oxidizing or reducing. In addition, profound effects of irradiation on the microchemistry and alloy microstructure create numerous pathways for IGSCC to occur. Radiation-induced segregation, the formation of a dislocation loop microstructure, irradiation hardening, and irradiation creep all occur simultaneously in space and time. Unfolding these various effects to determine the primary factors governing the observed effect...

[1]  Robin L. Jones,et al.  Hydrogen water chemistry for BWRs , 1987 .

[2]  J. L. Brimhall,et al.  Radiation hardening effects on localized deformation and stress corrosion cracking of stainless steels , 1993 .

[3]  G. M. Bond,et al.  Proton irradiation emulation of PWR neutron damage microstructures in solution annealed 304 and cold-worked 316 stainless steels , 2003 .

[4]  E. Kenik,et al.  The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys , 2002 .

[5]  P. Cohen Water coolant technology of power reactors , 1980 .

[6]  J. Busby,et al.  The Effect of Hardening Source in Proton Irradiation-Assisted Stress Corrosion Cracking of Cold Worked Type 304 Stainless Steel , 2004 .

[7]  A. Jenssen,et al.  Microchemical characterization of grain boundaries in irradiated steels , 1995 .

[8]  F. P. Ford,et al.  Modeling and prediction of irradiation assisted stress corrosion cracking , 1995 .

[9]  P. Scott,et al.  An Analysis of Baffle/Former Bolt Cracking in French PWRs , 2000 .

[10]  M. Morra,et al.  Effects of Yield Strength, Corrosion Potential, Composition and Stress Intensity Factor in SCC of Stainless Steels , 2004 .

[11]  A. Hindmarsh,et al.  GEAR: ORDINARY DIFFERENTIAL EQUATION SYSTEM SOLVER. , 1971 .

[12]  E. Kenik,et al.  Microchemistry of proton-irradiated austenitic alloys under conditions relevant to LWR core components , 1998 .

[13]  K. Farrell Mapping Flow Localization Processes in Deformation of Irradiated Reactor Structural Alloys , 2002 .

[14]  G. P. Wozadlo,et al.  Irradiation-assisted stress corrosion cracking as a factor in nuclear power plant aging , 1988 .

[15]  P. Andresen,et al.  Strain and Microstructure Characterization of Austenitic Stainless Steel Weld HAZs , 2000 .

[16]  I. Bernstein,et al.  The Role of Metallurgical Variables in Hydrogen-Assisted Environmental Fracture , 1980 .

[17]  P. Andresen,et al.  Characterization of the roles of electrochemistry, convection and crack chemistry in stress corrosion cracking , 1995 .

[18]  F. P. Ford,et al.  Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors , 2002 .

[19]  S. Hettiarachchi,et al.  Resolving Electrocatalytic SCC Mitigation Issues in High Temperature Water , 2004 .

[20]  A. Jenssen,et al.  Importance of molybdenum on irradiation-assisted stress corrosion cracking in austenitic stainless steels , 1998 .

[21]  E. Kenik,et al.  The Role of Fine Defect Clusters in Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated 304 Stainless Steel , 2004 .