Download or read book Environmentally Assisted Cracking in Light Water Reactors Semiannual Report July 2000 december 2000 Nureg cr 4667 Vol 31 U s Nuclear written by and published by . This book was released on 2002* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmentally Assisted Cracking In Light Water Reactors Semiannual Report Jan 2000 June 2000 NUREG CR 4667 Vol 30 U S Nuclear Regulatory Commission written by and published by . This book was released on 2001* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS SEMIANNUAL REPORT NUREG CR 4667 VOL 23 ANL 97 10 U S NUCLEAR REGULATORY CO written by U.S. Nuclear Regulatory Commission 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 Environmentally Assisted Cracking In Light Water Reactors Semiannual Report NUREG CR 4667 Vol 24 ANL 98 6 U S Nuclear Regulatory Commission January 1997 June 1997 written by U.S. Nuclear Regulatory Commission 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 Environmentally Assisted Cracking in Light Water Reactors written by O. K. Chopra and published by . This book was released on 2002-05-01 with total page 83 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmentally Assisted Cracking in Light Water Reactors written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from July 2000 to December 2000. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. The fatigue strain-vs.-life data are summarized for the effects of various material, loading, and environmental parameters on the fatigue lives of carbon and low-alloy steels and austenitic SSs. Effects of the reactor coolant environment on the mechanism of fatigue crack initiation are discussed. Two methods for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations are presented. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to (almost equal to)0.9 x 1021 n · cm−2 (E> 1 MeV) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. A fracture toughness J-R curve test was conducted on a commercial heat of Type 304 SS that was irradiated to (almost equal to)2.0 x 1021 n · cm−2 in the Halden reactor. The results were compared with the data obtained earlier on steels irradiated to 0.3 and 0.9 x 1021 n · cm−2 (E> 1 MeV) (0.45 and 1.35 dpa). Neutron irradiation at 288 C was found to decrease the fracture toughness of austenitic SSs. Tests were conducted on compact-tension specimens of Alloy 600 under cyclic loading to evaluate the enhancement of crack growth rates in LWR environments. Then, the existing fatigue crack growth data on Alloys 600 and 690 were analyzed to establish the effects of temperature, load ratio, frequency, and stress intensity range on crack growth rates in air.

Download or read book ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS ANNUAL REPORT JANUARY DECEMBER 2001 NUREG CR 4667 VOL 32 U S NUCLEAR R written by and published by . This book was released on 2003* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmentally Assisted Cracking In Light Water Reactors Semiannual Report Jan 2000 June 2000 NUREG written by and published by . This book was released on 2001* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmentally Assisted Cracking in Light Water Reactors written by W. J. Shack and published by . This book was released on 1983 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT WATER REACTORS SEMIANNUAL REPORT JULY 1998 DECEMBER 1998 NUREG 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 Environmentally Assisted Cracking in Light Water Reactors Semiannual Report July 1999 December 1999 Nureg written by U.S. Nuclear Regulatory Commission and published by . This book was released on 2001* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmentally Assisted Cracking in Light Water Reactors written by and published by . This book was released on 1991 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmentally Assisted Cracking in Light Water Reactors Semiannual Report October 1993 March 1994 written by and published by . This book was released on 1995 with total page 51 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) during the six months from October 1993 to March 1994. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns in operating plants and as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels, (b) EAC of wrought and cast austenitic stainless steels (SSs), and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS after accumulation of relatively high fluence. Fatigue tests have been conducted on A302-Gr B low-alloy steel to verify whether the current predictions of modest decreases of fatigue life in simulated pressurized water reactor water are valid for high-sulfur heats that show environmentally enhanced fatigue crack growth rates. Additional crack growth data were obtained on fracture-mechanics specimens of austenitic SSs to investigate threshold stress intensity factors for EAC in high-purity oxygenated water at 289°C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air from Section XI of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating boiling water reactors were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements, which are not specified in the ASTM specifications, may contribute to IASCC of solution-annealed materials.

Download or read book Environmentally Assisted Cracking in Light Water Reactors Semiannual Report July 1996 December 1996 written by and published by . This book was released on 1997 with total page 107 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from July 1996 to December 1996. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Type 304 SS, (c) EAC of Alloy 600, and (d) characterization of residual stresses in welds of boiling water reactor (BWR) core shrouds by numerical models. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen to determine whether a slow strain rate applied during various portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated BWR water at 288 C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from a low-carbon content heat of Alloy 600 in high-purity oxygenated water at 289 C. Residual stresses and stress intensity factors were calculated for BWR core shroud welds.

Download or read book Environmentally Assisted Cracking in Light Water Reactors written by W. J. Shack and published by . This book was released on 1984 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmental Assisted Cracking In Light Water Reactors Semiannual Report July 1997 Dec 1997 NUREG 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 Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors written by Gabriell Ilevbare and published by Springer. This book was released on 2017-07-17 with total page 2354 pages. Available in PDF, EPUB and Kindle. Book excerpt: This 15th Edition of the International Conference on Materials Degradation in Light Water Reactors focuses on subject areas critical to the safe and efficient running of nuclear reactor systems through the exchange and discussion of reseach results as well as field operating and management experience.