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

SNPDL work in support of collaborative programmes to study fatigue crack propagation in light water reactor pressure vessel steels

McMinn, A.
UKAEA, Risley. Nuclear Power Development Establishment (United Kingdom)

January 1981

3.00SIGLELD:9091.9F(ND-R--620(S)). / BLDSC - British Library Document Supply CentreGBUnited Kingdo

Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : third annual progress report, October 1976 - September 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."BMI-1995.""NUREG/CR-0057."Inc...

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 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, ...

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

Cullen, W. H. author.
Loss, F. L. author.
Watson, H. E. author.
Torronen, K. J. author.
Provenzano, V. author.
U.S. Nuclear Regulatory Commission.
Naval Research Laboratory (U.S.). Thermostructural Materials Branch.

"NUREG/CR 0969.""September 28, 1979.""Thermostructural Materials Branch, Material Science and Techno...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - March 1980 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: July 1980.""NRC FIN No. A4046.""BMI-2055.""NUREG/CR-1601."Bibliography: p. 4-1.Mode...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, June-December 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: June 1980.""NRC FIN No. A4046.""BMI-2064.""NUREG/CR-1555."Bibliography: p. 4-1.Mode...

Investigation and evaluation of cracking incidents in piping in pressurized water reactors /

U.S. Nuclear Regulatory Commission.
PWR Pipe Crack Study Group (U.S.)

January 1980

"NUREG-0691.""Date published : September 1980."Includes bibliographical references.Mode of access: I...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - June 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1979

"Date published: September 1979.""NRC FIN No. A4046.""BMI-2036.""NUREG/CR-0991."Mode of access: Inte...

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...

An assessment of the failure rate for the beltline region of PWR pressure vessels during normal operation and certain transient conditions /

Gamble, R. (Ronald)
Strosnider, J.
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering.

January 1981

"NUREG-0778.""Date published: June 1981."Includes bibliographical references.Mode of access: Interne...

An interim report on the influence of material variables on corrosion fatigue crack growth in reactor pressure vessel steels in PWR primary water

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

January 1982

SIGLELD:9091.9F(AERE-R--10421) / BLDSC - British Library Document Supply CentreGBUnited Kingdo

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : 4th annual report, October 1977 - October 1978 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1979."Prepared under contract no. AT(49-24)-0293."NRC FIN NO. A4046.""BMI-2025....

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...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear pressure vessel steels : progress report January-June 1979 /

Rosenfield, Alan R. author.
Zielenbach, W. J., author.
Farmelo, D. R., author.
Perrin, J. S., author.
Hoagland, R. G., author.
Marschall, C. (Charles W.), author.
Gillot, R., author.
Barnes, C. R., author.
Landow, M. P., author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"NRC FIN no. A4046.""BMI-2036.""NUREG/CR-0991.""Date published: September 1979.""Battelle Columbus L...

SNPDL work in support of collaborative programmes to study fatigue crack propagation in light water reactor pressure vessel steels

McMinn, A.
UKAEA, Risley. Nuclear Power Development Establishment (United Kingdom)

January 1981

3.00SIGLELD:9091.9F(ND-R--620(S)). / BLDSC - British Library Document Supply CentreGBUnited Kingdo

Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : third annual progress report, October 1976 - September 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."BMI-1995.""NUREG/CR-0057."Inc...

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 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, ...

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

Cullen, W. H. author.
Loss, F. L. author.
Watson, H. E. author.
Torronen, K. J. author.
Provenzano, V. author.
U.S. Nuclear Regulatory Commission.
Naval Research Laboratory (U.S.). Thermostructural Materials Branch.

"NUREG/CR 0969.""September 28, 1979.""Thermostructural Materials Branch, Material Science and Techno...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - March 1980 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: July 1980.""NRC FIN No. A4046.""BMI-2055.""NUREG/CR-1601."Bibliography: p. 4-1.Mode...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, June-December 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1980

"Date published: June 1980.""NRC FIN No. A4046.""BMI-2064.""NUREG/CR-1555."Bibliography: p. 4-1.Mode...

Investigation and evaluation of cracking incidents in piping in pressurized water reactors /

U.S. Nuclear Regulatory Commission.
PWR Pipe Crack Study Group (U.S.)

January 1980

"NUREG-0691.""Date published : September 1980."Includes bibliographical references.Mode of access: I...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear-pressure-vessel steels : progress report, January - June 1979 /

Rosenfield, Alan R.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

January 1979

"Date published: September 1979.""NRC FIN No. A4046.""BMI-2036.""NUREG/CR-0991."Mode of access: Inte...

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...

An assessment of the failure rate for the beltline region of PWR pressure vessels during normal operation and certain transient conditions /

Gamble, R. (Ronald)
Strosnider, J.
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering.

January 1981

"NUREG-0778.""Date published: June 1981."Includes bibliographical references.Mode of access: Interne...

An interim report on the influence of material variables on corrosion fatigue crack growth in reactor pressure vessel steels in PWR primary water

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

January 1982

SIGLELD:9091.9F(AERE-R--10421) / BLDSC - British Library Document Supply CentreGBUnited Kingdo

Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : 4th annual report, October 1977 - October 1978 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1979."Prepared under contract no. AT(49-24)-0293."NRC FIN NO. A4046.""BMI-2025....

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...

Critical experiments, measurements, and analyses to establish a crack-arrest methodology for nuclear pressure vessel steels : progress report January-June 1979 /

Rosenfield, Alan R. author.
Zielenbach, W. J., author.
Farmelo, D. R., author.
Perrin, J. S., author.
Hoagland, R. G., author.
Marschall, C. (Charles W.), author.
Gillot, R., author.
Barnes, C. R., author.
Landow, M. P., author.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"NRC FIN no. A4046.""BMI-2036.""NUREG/CR-0991.""Date published: September 1979.""Battelle Columbus L...

SNPDL work in support of collaborative programmes to study fatigue crack propagation in light water reactor pressure vessel steels

McMinn, A.
UKAEA, Risley. Nuclear Power Development Establishment (United Kingdom)

January 1981

3.00SIGLELD:9091.9F(ND-R--620(S)). / BLDSC - British Library Document Supply CentreGBUnited Kingdo

Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels : third annual progress report, October 1976 - September 1977 /

Hahn, G. T. (George T.)
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Battelle Memorial Institute. Columbus Laboratories.

"Date published: May 1978."Prepared under contract no. AT(49-24)-0293."BMI-1995.""NUREG/CR-0057."Inc...

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

Abstract

Extracted data

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

Abstract

Extracted data

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