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

Corrosion fatigue crack propagation behaviour of a high strength low alloy steel in a synthetic sea water environment

Millar, P.G
Cranfield Inst. of Tech. (United Kingdom)

January 1986

SIGLEAvailable from British Library Document Supply Centre- DSC:DX81783 / BLDSC - British Library Do...

Methods for incorporating the effects of LWR coolant environments in pressure vessel and piping fatigue evaluations.

Chopra, O. K.
Shack, W. J.

July 2002

This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...

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

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...

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...

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 fatigue of pressure vessel steels in LWR environments Influence of steel sulphur content

Druce, S
Truswell, A.
Scott, P.
UKAEA Atomic Energy Research Establishment, Harwell (United Kingdom). Metallurgy Div
UKAEA Atomic Energy Establishment, Harwell (United Kingdom). Materials Development Div.

January 1983

SIGLEAvailable from British Library Document Supply Centre- DSC:9091.9(AERE-R--10964) / BLDSC - Brit...

Corrosion Fatigue Crack Growth Studies on Pressure Vessel and Piping Steels in Water Environment

Mathew, N. M.
Vishnuvardhan, S.
Raghava, G.
Santhi, A. S.

January 2017

Corrosion fatigue crack growth studies were conducted on eccentrically-loaded single edge notch tens...

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 ...

Kansai Electric Power Co.

Yuichiro Nomura
Kazuhiro Jotaki
Kyushu Electric
Power Co
Takashi Hirose
Kazuya Tsutsumi
Naoki Chigusa
Hidetaka Shimizu
Hokkaido Electnc
Power Co
Hitoshi Ohata

October 2016

Although reference fatigue crack growth curves for austenitic stainless teels in air environments an...

Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

김선진

June 2017

The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evalu...

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...

Fatigue crack initiation in carbon and low-alloy steels in light water reactor environments : mechanism and prediction.

Chopra, O. K.
Shack, W. J.

January 1998

Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...

Crack initiation in smooth fatigue specimens of austenitic stainless steel in light water reactor environments.

Chopra, O. K.
Smith, J. L.

April 1999

The fatigue design curves for structural materials specified in Section III of the ASME Boiler and P...

Influence of Strain Rate and Waveshape on Environmentally-Assisted Cracking during Low-Cycle Fatigue of a 304L Austenitic Stainless Steel in a PWR Water Environment

Thibault Poulain
Laurent de Baglion
Jose Mendez
Gilbert Hénaff

February 2019

In this paper, the low cycle fatigue resistance of a 304L austenitic stainless steel in a simulated ...

Corrosion fatigue crack propagation behaviour of a high strength low alloy steel in a synthetic sea water environment

Millar, P.G
Cranfield Inst. of Tech. (United Kingdom)

January 1986

SIGLEAvailable from British Library Document Supply Centre- DSC:DX81783 / BLDSC - British Library Do...

Methods for incorporating the effects of LWR coolant environments in pressure vessel and piping fatigue evaluations.

Chopra, O. K.
Shack, W. J.

July 2002

This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...

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

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...

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...

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 fatigue of pressure vessel steels in LWR environments Influence of steel sulphur content

Druce, S
Truswell, A.
Scott, P.
UKAEA Atomic Energy Research Establishment, Harwell (United Kingdom). Metallurgy Div
UKAEA Atomic Energy Establishment, Harwell (United Kingdom). Materials Development Div.

January 1983

SIGLEAvailable from British Library Document Supply Centre- DSC:9091.9(AERE-R--10964) / BLDSC - Brit...

Corrosion Fatigue Crack Growth Studies on Pressure Vessel and Piping Steels in Water Environment

Mathew, N. M.
Vishnuvardhan, S.
Raghava, G.
Santhi, A. S.

January 2017

Corrosion fatigue crack growth studies were conducted on eccentrically-loaded single edge notch tens...

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 ...

Kansai Electric Power Co.

Yuichiro Nomura
Kazuhiro Jotaki
Kyushu Electric
Power Co
Takashi Hirose
Kazuya Tsutsumi
Naoki Chigusa
Hidetaka Shimizu
Hokkaido Electnc
Power Co
Hitoshi Ohata

October 2016

Although reference fatigue crack growth curves for austenitic stainless teels in air environments an...

Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

김선진

June 2017

The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evalu...

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...

Fatigue crack initiation in carbon and low-alloy steels in light water reactor environments : mechanism and prediction.

Chopra, O. K.
Shack, W. J.

January 1998

Section 111 of the ASME Boiler and Pressure Vessel Code specifies fatigue design curves for structur...

Crack initiation in smooth fatigue specimens of austenitic stainless steel in light water reactor environments.

Chopra, O. K.
Smith, J. L.

April 1999

The fatigue design curves for structural materials specified in Section III of the ASME Boiler and P...

Influence of Strain Rate and Waveshape on Environmentally-Assisted Cracking during Low-Cycle Fatigue of a 304L Austenitic Stainless Steel in a PWR Water Environment

Thibault Poulain
Laurent de Baglion
Jose Mendez
Gilbert Hénaff

February 2019

In this paper, the low cycle fatigue resistance of a 304L austenitic stainless steel in a simulated ...

Corrosion fatigue crack propagation behaviour of a high strength low alloy steel in a synthetic sea water environment

Millar, P.G
Cranfield Inst. of Tech. (United Kingdom)

January 1986

SIGLEAvailable from British Library Document Supply Centre- DSC:DX81783 / BLDSC - British Library Do...

Methods for incorporating the effects of LWR coolant environments in pressure vessel and piping fatigue evaluations.

Chopra, O. K.
Shack, W. J.

July 2002

This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and...

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

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

Abstract

Extracted data

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

Abstract

Extracted data

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