Fatigue crack growth of A508 steel in high-temperature, pressurized reactor grade water /

Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996

Chopra, O.K.
Chung, H.M.
Gruber, E.E.

May 1997

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally ...

Environmentally assisted cracking of LWR materials

Chopra, O.K.
Chung, H.M.
Kassner, T.F.
Shack, W.J.

December 1995

Research on environmentally assisted cracking (EAC) of light water reactor materials has focused on ...

Preliminary analysis of the effect of fatigue loading and crack propagation on crack acceptance criteria for nuclear power plant components /

Anderson, W. F.
Johns, E. C. (Earl C.)
Weidenhamer, G. H.
U.S. Nuclear Regulatory Commission. Division of Engineering Standards.

"NUREG-0726.""Date published: April 1981."Includes bibliographical references.Mode of access: Intern...

Fatigue crack growth rates in pressure vessel and piping steels in LWR environments : final report /

Cullen, W. H.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Materials Engineering Associates.

January 1987

"Date published: March 1987.""NRC FIN B8900.""MEA-2175.""NUREG/CR-4724."Bibliography: p. 50-54.Mode ...

Fatigue growth in piping and RPV steels in simulated BWR water environment /

Hale, D. A. author.
Gerber, T. L., author.
Yuen, J. L., author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
General Electric Company. Nuclear Engineering Division.

March 1979.Prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, ...

Environmentally assisted cracking in light water reactors. Semiannual report, April 1994--September 1994, Volume 19

Chopra, O.K.
Chung, H.M.
Gavenda, D.J.

September 1995

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmen...

Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18

Chung, H.M.
Chopra, O.K.
Erck, R.A.
Kassner, T.F.
Michaud, W.F.
Ruther, W.E.
Sanecki, J.E.
Shack, W.J.
Soppet, W.K.

March 1995

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmen...

Review of environmental effects on fatigue crack growth of austenitic stainless steels.

Shack, W. J.
Kassner, T. F.
Technology, Energy

July 1994

Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core componen...

Corrosion of reactor structural materials in high-temperature water.

Fowler, R., Jr.
Zyzes, F. C.
Douglas, D. L.
Knolls Atomic Power Laboratory.
General Electric Company.
U.S. Atomic Energy Commission.

"KAPL-1198.""August 27, 1954."Includes bibliographical references (page 26).U.S. Atomic Energy Commi...

Crack propagation, delayed failure, and residual static strength of titanium, aluminum, and stainless steel alloys in aqueous environments /

Figge, I. E.
Hudson, C. Michael.
Langley Research Center.

January 1967

"February 1967."Includes bibliographical references (p. 15).Mode of access: Internet

Corrosion fatigue crack growth through cladding to base metal of a CrMoV-reactor pressure vessel steel

Saario, Timo
Törrönen, Kari
Ahlstrand, Ralf
Ignatov, V.
Fedorova, V.
Rybin, Valeri
Timofeev, Boris

January 1989

Corrosion fatigue crack growth rate of Soviet reactor pressure vessel steel 15X2M∅A and its cladding...

The influence of water chemistry on fatigue crack propagation in LWR pressure vessel steels

Truswell, A.E.
Scott, P.M.
UKAEA, Harwell. Atomic Energy Research Establishment (United Kingdom)

January 1981

SIGLELD:0678.231F(AD-A--106-116)(microfiche). / BLDSC - British Library Document Supply CentreGBUnit...

Fatigue crack growth and fracture in steels used for high pressure tubing

Klintworth, G

January 1980

SIGLEAvailable from British Library Document Supply Centre- DSC:D70225/81 / BLDSC - British Library ...

Environmentally assisted cracking in light water reactors. Semiannual report, July 1998-December 1998.

Chopra, O. K.
Chung, H. M.
Gruber, E. E.
Kassner, T. F.
Ruther, W. E.
Shack, W. J.
Smith, J. L.
Soppet, W. K.
Strain
Technology), R. V. (Energy
APS-USR), (

October 1999

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally ...

Stress-corrosion cracking of high-strength stainless steels in atmospheric environments /

Slunder, C. J., author.
Defense Metals Information Center (U.S.) issuing body.

Research supported by the Technology Division, Wright-Patterson Air Force Base, Ohio."September 15, ...

Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996

Chopra, O.K.
Chung, H.M.
Gruber, E.E.

May 1997

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally ...

Environmentally assisted cracking of LWR materials

Chopra, O.K.
Chung, H.M.
Kassner, T.F.
Shack, W.J.

December 1995

Research on environmentally assisted cracking (EAC) of light water reactor materials has focused on ...

Preliminary analysis of the effect of fatigue loading and crack propagation on crack acceptance criteria for nuclear power plant components /

Anderson, W. F.
Johns, E. C. (Earl C.)
Weidenhamer, G. H.
U.S. Nuclear Regulatory Commission. Division of Engineering Standards.

"NUREG-0726.""Date published: April 1981."Includes bibliographical references.Mode of access: Intern...

Fatigue crack growth rates in pressure vessel and piping steels in LWR environments : final report /

Cullen, W. H.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Materials Engineering Associates.

January 1987

"Date published: March 1987.""NRC FIN B8900.""MEA-2175.""NUREG/CR-4724."Bibliography: p. 50-54.Mode ...

Fatigue growth in piping and RPV steels in simulated BWR water environment /

Hale, D. A. author.
Gerber, T. L., author.
Yuen, J. L., author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
General Electric Company. Nuclear Engineering Division.

March 1979.Prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, ...

Environmentally assisted cracking in light water reactors. Semiannual report, April 1994--September 1994, Volume 19

Chopra, O.K.
Chung, H.M.
Gavenda, D.J.

September 1995

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmen...

Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18

Chung, H.M.
Chopra, O.K.
Erck, R.A.
Kassner, T.F.
Michaud, W.F.
Ruther, W.E.
Sanecki, J.E.
Shack, W.J.
Soppet, W.K.

March 1995

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmen...

Review of environmental effects on fatigue crack growth of austenitic stainless steels.

Shack, W. J.
Kassner, T. F.
Technology, Energy

July 1994

Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core componen...

Corrosion of reactor structural materials in high-temperature water.

Fowler, R., Jr.
Zyzes, F. C.
Douglas, D. L.
Knolls Atomic Power Laboratory.
General Electric Company.
U.S. Atomic Energy Commission.

"KAPL-1198.""August 27, 1954."Includes bibliographical references (page 26).U.S. Atomic Energy Commi...

Crack propagation, delayed failure, and residual static strength of titanium, aluminum, and stainless steel alloys in aqueous environments /

Figge, I. E.
Hudson, C. Michael.
Langley Research Center.

January 1967

"February 1967."Includes bibliographical references (p. 15).Mode of access: Internet

Corrosion fatigue crack growth through cladding to base metal of a CrMoV-reactor pressure vessel steel

Saario, Timo
Törrönen, Kari
Ahlstrand, Ralf
Ignatov, V.
Fedorova, V.
Rybin, Valeri
Timofeev, Boris

January 1989

Corrosion fatigue crack growth rate of Soviet reactor pressure vessel steel 15X2M∅A and its cladding...

The influence of water chemistry on fatigue crack propagation in LWR pressure vessel steels

Truswell, A.E.
Scott, P.M.
UKAEA, Harwell. Atomic Energy Research Establishment (United Kingdom)

January 1981

SIGLELD:0678.231F(AD-A--106-116)(microfiche). / BLDSC - British Library Document Supply CentreGBUnit...

Fatigue crack growth and fracture in steels used for high pressure tubing

Klintworth, G

January 1980

SIGLEAvailable from British Library Document Supply Centre- DSC:D70225/81 / BLDSC - British Library ...

Environmentally assisted cracking in light water reactors. Semiannual report, July 1998-December 1998.

Chopra, O. K.
Chung, H. M.
Gruber, E. E.
Kassner, T. F.
Ruther, W. E.
Shack, W. J.
Smith, J. L.
Soppet, W. K.
Strain
Technology), R. V. (Energy
APS-USR), (

October 1999

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally ...

Stress-corrosion cracking of high-strength stainless steels in atmospheric environments /

Slunder, C. J., author.
Defense Metals Information Center (U.S.) issuing body.

Research supported by the Technology Division, Wright-Patterson Air Force Base, Ohio."September 15, ...

Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996

Chopra, O.K.
Chung, H.M.
Gruber, E.E.

May 1997

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally ...

Environmentally assisted cracking of LWR materials

Chopra, O.K.
Chung, H.M.
Kassner, T.F.
Shack, W.J.

December 1995

Research on environmentally assisted cracking (EAC) of light water reactor materials has focused on ...

Preliminary analysis of the effect of fatigue loading and crack propagation on crack acceptance criteria for nuclear power plant components /

Anderson, W. F.
Johns, E. C. (Earl C.)
Weidenhamer, G. H.
U.S. Nuclear Regulatory Commission. Division of Engineering Standards.

"NUREG-0726.""Date published: April 1981."Includes bibliographical references.Mode of access: Intern...

Fatigue crack growth of A508 steel in high-temperature, pressurized reactor grade water /

Abstract

Extracted data

Fatigue crack growth of A508 steel in high-temperature, pressurized reactor grade water /

Abstract

Extracted data

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