Download or read book Irradiation assisted Stress Corrosion Cracking Considerations at Temperatures Below 288degreeC written by and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted Stress Corrosion Cracking Considerations at Temperatures Below 288 C written by and published by . This book was released on 1995 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation-assisted stress corrosion cracking (IASCC) occurs above a critical neutron fluence in light-water reactor (LWR) water environments at 288 C, but very little information exists to indicate susceptibility as temperatures are reduced. Potential low-temperature behavior is assessed based on the temperature dependencies of intergranular (IG) SCC in the absence of irradiation, radiation-induced segregation (RIS) at grain boundaries and micromechanical deformation mechanisms. IGSCC of sensitized SS in the absence of irradiation exhibits high growth rates at temperatures down to 200 C under conditions of anodic dissolution control, while analysis of hydrogen-induced cracking suggests a peak crack growth rate near 100 C. Hence from environmental considerations, IASCC susceptibility appears to remain likely as water temperatures are decreased. Irradiation experiments and model predictions indicate that RIS also persists to low temperatures. Chromium depletion may be significant at temperatures below 100C for irradiation doses greater than 10 displacements per atom (dpa). Macromechanical effects of irradiation on strength and ductility are not strongly dependent on temperature below 288 C. However, temperature does significantly affect radiation effects on SS microstructure and micromechanical deformation mechanisms. The critical conditions for material susceptibility to IASCC at low temperatures may be controlled by radiation-induced grain boundary microchemistry, strain localization due to irradiation microstructure and irradiation creep processes. 39 refs.

Download or read book Understanding Susceptibility of In core Components to Irradiation assisted Stress Corrosion Cracking written by and published by . This book was released on 1991 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Isolation of the Role of Radiation induced Segregation in Irradiation assisted Stress Corrosion Cracking of Proton irradiated Austenitic Stainless Steels written by Jeremy Todd Busby and published by . This book was released on 2001 with total page 1008 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted Stress Corrosion Cracking of Model Austenitic Stainless Steels Irradiated in the Halden Reactor written by H. M. Chung and published by . This book was released on 1999 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments written by and published by . This book was released on 2010 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted stress corrosion cracking of austenitic stainless steels written by Takashi Tsukada and published by . This book was released on 1998 with total page 187 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Studies on the Mechanism for Irradiation Assisted Stress Corrosion Cracking written by Kjell Pettersson and published by . This book was released on 1994 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments written by Y. Chen and published by . This book was released on 2010 with total page 89 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book IRRADIATION ASSISTED STRESS CORROSION CRACKING OF MODEL AUSTENITIC STAINLESS STEELS IRRADIATED IN THE HALDEN REACTOR NUREG CR 5608 U S NUCLEAR REGULATORY Commission written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1999* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted Stress Corrosion Cracking Behavior of Austenitic Stainless Steels Applicable to LWR Core Internals written by and published by . This book was released on 2006 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Current Understanding of the Irradiation Assisted Stress Corrosion Cracking Potential for PWRs written by H. Xu and published by . This book was released on 1998 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation assisted Stress Corrosion Cracking of Fusion Reactor Material written by and published by . This book was released on 1990 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation-assisted stress-corrosion cracking (IASCC) is a phenomenon produced by radiation-induced alterations in the material and environment. These alternations include radiation-induced segregation and depletion of specific elements at grain boundaries, radiation creep and hardening and radiolytic effects induced in the aqueous environment. This phenomenon has been clearly identified as an active crack growth mechanism for in-core components in fission reactor must be considered as a potential crack growth mechanism for water-cooled fusion reactors such as ITER or power reactors. The potential for IASCC phenomenon occurring in ITER structural materials is being evaluated by modeling and experiment. Results from modeling calculations for impurity segregation at ITER-relevant temperatures have been completed and suggest that this phenomenon is not likely to induce IASCC during the ITER design life. If a fusion power reactor is water cooled, IASCC is a definite concern for austenitic stainless steels. It has been clearly demonstrated with modeling and experimental measurements that Cr depletion occurs within about 1 dpa. Phosphorus and Si grain boundary segregation can also occur at this same dose and temperature but their effect on IASCC appears to be secondary to Cr depletion. Also, irradiation creep-induced crack tip strain appears to be a secondary effect. However, there are a number of unexplained observations in the literature on IASCC which may be caused by radiation damage effects other than Cr depletion or impurity segregation.

Download or read book Irradiation Assisted Stress Corrosion Cracking Susceptibility of Low Fluence Stainless Steels Evaluated by In flux Slow Strain Rate Tests written by Bruce A. Hilton and published by . This book was released on 1996 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Stress corrosion Cracking written by Russell H. Jones and published by ASM International(OH). This book was released on 1992 with total page 466 pages. Available in PDF, EPUB and Kindle. Book excerpt: Details the many conditions under which stress-corrosion cracking (SCC) can occur, the parameters which control SCC, and the methodologies for mitigating and testing for SCC, plus information on mechanisms of SCC with experimental data on a variety of materials. Contains information about environmen

Download or read book Deposits near Medicine Hat Alberta Canada written by and published by . This book was released on 1970 with total page 3927 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Role of Fine Defect Clusters in Irradiation Assisted Stress Corrosion Cracking of Proton Irradiated 304 Stainless Steel written by GS. Was and published by . This book was released on 2004 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The influence of small defect clusters on irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels has been examined. A CP-304 SS alloy was irradiated with 3.2 MeV protons to 1.0 dpa at 360°C and then annealed for 45 min. to 1 h at temperatures ranging from 400-600°C. Dislocation microstructure was analyzed using both bright field and dark field techniques and cracking susceptibility was measured in an oxygenated water environment. Intergranular cracking was mitigated following annealing at 500°C/45 min. while only the smallest dislocation loops had been removed. Analysis of the slip step bands on the surface of deformed samples indicates that deformation mode may be important in determining cracking susceptibility. Low-temperature irradiation (