Contaminants and stagnant conditions affecting stress corrosion cracking in stainless steel piping in pressurized water reactors.
| Format: | Government Document eBook |
|---|---|
| Language: | English |
| Published: |
Washington, DC :
United States. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation : Office of New Reactors,
2011.
|
| Series: | NRC information notice ;
2011-04. |
| Subjects: | |
| Online Access: | https://purl.fdlp.gov/GPO/gpo157137 |
Similar Items
Circumferential cracking in the stainless steel pressurized heater sleeves of pressurized water reactors.
Published: (2006)
Published: (2006)
Stress corrosion cracking in pressurized water reactor systems.
Published: (1984)
Published: (1984)
Pipe cracks in stagnant borated water systems at PWR plants.
Published: (1979)
Published: (1979)
Primary water stress corrosion cracking (PWSCC) of Inconel 600.
Published: (1990)
Published: (1990)
Stress corrosion cracking in PWR steam generator tubes.
Published: (1990)
Published: (1990)
Cracking in main steam lines.
Published: (1981)
Published: (1981)
Boric acid corrosion of light water reactor pressure vessel materials /
Published: (2005)
Published: (2005)
Intergranular stress corrosion cracking in pressurized water reactor safety injection accumulator nozzles.
Published: (1991)
Published: (1991)
Corrosion issues in light water reactors : stress corrosion cracking /
Published: (2007)
Published: (2007)
Crack growth rates of irradiated nickel alloy welds in a PWR environment /
by: Alexandreanu, B.
Published: (2006)
by: Alexandreanu, B.
Published: (2006)
Primary water stress corrosion cracking of high-chromium, nickel-base welds near dissimilar metal weld interfaces /
by: Alexandreanu, B.
Published: (2018)
by: Alexandreanu, B.
Published: (2018)
U.S. plant experience with alloy 600 cracking and boric acid corrosion light-water reactor pressure vessel materials /
by: Grimmel, B.
Published: (2005)
by: Grimmel, B.
Published: (2005)
Environmental effects on fatigue crack initiation in piping and pressure vessel steels /
by: Chopra, O. K.
Published: (2001)
by: Chopra, O. K.
Published: (2001)
Cracking in the upper shell to transition cone girth weld of a steam generator at an operating pressurized water reactor.
Published: (1982)
Published: (1982)
Boric acid corrosion of carbon steel reactor pressure boundary components in PWR plants.
Published: (1988)
Published: (1988)
Circumferential cracking of steam generator tubes.
Published: (1995)
Published: (1995)
Reactor coolant pressure boundary leakage attributable to propagation of cracking in reactor vessel nozzle welds.
Published: (2004)
Published: (2004)
Corrosion rate measurements and chemical speciation of corrosion products using thermodynamic modeling of debris components to support GSI-191 /
by: Jain, V.
Published: (2005)
by: Jain, V.
Published: (2005)
Corrosion and wear handbook for water-cooled reactors.
by: DePaul, D. J.
Published: (1957)
by: DePaul, D. J.
Published: (1957)
Failure to detect freespan cracks in PWR steam generator tubes.
Published: (2003)
Published: (2003)
Intergranular stress corrosion cracking leading to steam generator tube failure.
Published: (1984)
Published: (1984)
Crack growth rates in a PWR environment of nickel alloys from the Davis-Besse and V.C. Summer power plants /
by: Alexandreanu, B.
Published: (2006)
by: Alexandreanu, B.
Published: (2006)
Irradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations /
by: Chen, Y.
Published: (2008)
by: Chen, Y.
Published: (2008)
Potential for stress corrosion cracking in steam generator tube plugs supplied by Babcock and Wilcox.
Published: (1989)
Published: (1989)
NRC position on IGSCC in BWR austenitic stainless steel piping.
Published: (1988)
Published: (1988)
Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments /
Published: (2010)
Published: (2010)
Loss of thermal sleeves in reactor coolant system piping at certain Westinghouse Pwr power plants.
Published: (1982)
Published: (1982)
Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators : held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978 /
Published: (1982)
Published: (1982)
Pipe cracking in U.S. BWRs : a regulatory history /
by: Strosnider Jr., J. R.
Published: (2000)
by: Strosnider Jr., J. R.
Published: (2000)
Aluminum chemistry in a prototypical post-loss-of-coolant-accident, pressurized-water-reactor containment environment /
Published: (2006)
Published: (2006)
Additional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports".
Published: (1980)
Published: (1980)
GSI-191 : experimental studies of loss-of-coolant-accident-generated debris accumulation and head loss with emphasis on the effects of calcium silicate insulation /
Published: (2005)
Published: (2005)
Pressurized Heavy Water Reactors : CANDU /
Published: (2022)
Published: (2022)
Pressurized Heavy Water Reactors : Atucha II /
Published: (2022)
Published: (2022)
Corrosion issues in light water reactors : stress corrosion cracking /
Published: (2007)
Published: (2007)
Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals /
by: Chung, H. M.
Published: (2006)
by: Chung, H. M.
Published: (2006)
Crack growth rates of irradiated austenitic stainless steel weld heat affected zone in BWR environments /
Published: (2006)
Published: (2006)
Pressurized water reactor in the United Kingdom /
Published: (1982)
Published: (1982)
Generic activity A-10 BWR cracks.
Published: (1980)
Published: (1980)
The nuclear fuel of pressurized water reactors and fast neutron reactors : design and behaviour /
Published: (1999)
Published: (1999)