Full-Size Pressure Vessel Testing and Its Application to Design

Kooistra, L. F.; Lange, E. A.; Pickett, A.G.

doi:10.1115/1.3677630

Cited by 19 publications

(10 citation statements)

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“…; these can significantly decrease the conservatisms. Fatigue tests conducted on vessels at Southwest Research Institute for the PVRC 85 show that ª5-mm-deep cracks can form in carbon and low-alloy steels very close to the fatigue cycles predicted by the ASME Code design curve (Fig. 42).…”

Section: Conservatism In Fatigue Design Curvesmentioning

confidence: 99%

“…89 In addition, some effect of size and geometry has been observed on small-scale-vessel tests conducted at the Ecole Polytechnique in conjunction with the large-size-pressure-vessel tests carried out by the Southwest Research Institute. 85 The tests at the Ecole Polytechnique were conducted in room-temperature water on ª305-mm-inner-diameter, 19-mm-thick shells with nozzles made of machined bar stock. The results indicate that the number of cycles to form a 3-mm-deep crack in a 19-mm-thick shell may be 30-50% lower than those in a small test specimen.…”

Section: Conservatism In Fatigue Design Curvesmentioning

confidence: 99%

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Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments.

Chopra¹

2002

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The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life (e-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of fatigue crack initiation in austenitic stainless steels in LWR coolant environments. The existing fatigue e-N data have been evaluated to establish the effects of key material, loading, and environmental parameters (such as steel type, strain range, strain rate, temperature, dissolved-oxygen level in water, and flow rate) on the fatigue lives of these steels. Statistical models are presented for estimating the fatigue e-N curves for austenitic stainless steels as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are presented. The influence of reactor environments on the mechanism of fatigue crack initiation in these steels is also discussed. Executive SummarySection III, Subsection NB, of the ASME Boiler and Pressure Vessel Code contains rules for the design of Class 1 components of nuclear power plants. Figures I-9.1 through I-9.6 of Appendix I to Section III specify the Code design fatigue curves for applicable structural materials. However, Section III, Subsection NB-3121, of the Code states that effects of the coolant environment on fatigue resistance of a material were not intended to be addressed in these design curves. Therefore, the effects of environment on fatigue resistance of materials used in operating pressurized water reactor (PWR) and boiling water reactor (BWR) plants, whose primary-coolant pressure boundary components were designed in accordance with the Code, are uncertain.The current Section-III design fatigue curves of the ASME Code were based primarily on strain-controlled fatigue tests of small polished specimens at room temperature in air. Best-fit curves to the experimental test data were first adjusted to account for the effects of mean stress and then lowered by a factor of 2 on stress and 20 on cycles (whichever was more conservative) to obtain the design fatigue curves. These factors are not safety margins but rather adjustment factors that must be applied to experimental data to obtain estimates of the lives of components. They were not intended to address the effects of the coolant environment on fatigue life. Recent fatigue-strain-vs.-life (e-N) data obtained in the U.S. and Japan demonstrate that light water reactor (LWR) environments can have potentially significant effects on the fatigue resistance of materials. Specimen lives obtained from tests in simulated LWR environments can be much shorte...

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Section: Conservatism In Fatigue Design Curvesmentioning

confidence: 99%

Section: Conservatism In Fatigue Design Curvesmentioning

confidence: 99%

Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments.

Chopra¹

2002

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“…Our major concern has been with the potentials of the sub-size test and the nature of correlation with the CAT curve of the Fracture Analysis Diagram. (9,10,11)) for which the DWT indicated a 0°F NDT value and thereby provided for charting the Fracture Analysis Diagram at the illustrated position on the temperature axis. The DWTT correspondence shown in Fig.…”

Section: Naval Research Laboratorymentioning

confidence: 99%

Review of Concepts and Status of Procedures for Fracture-Safe Design of Complex Welded Structures Involving Metals of Low to Ultrahigh Strength Levels

Pellini¹,

Goode²,

Puzak³

et al. 1965

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“…60,61 Southwest Research Institute performed fatigue tests in room-temperature water on 0.914-m-diameter carbon and low-alloy steel vessels with 19-mm walls. 60 In the low-cycle regime, ª5-mm-deep cracks were initiated slightly above (a factor of <2) the number of cycles predicted by the ASME Code design curve (Fig. 22a).…”

Section: Margins In Asme Code Fatigue Design Curvesmentioning

confidence: 99%

Review of the margins for ASME code fatigue design curve - effects of surface roughness and material variability.

Chopra¹,

Shack²

2003

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The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. The Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life (e-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of the existing fatigue e-N data for carbon and low-alloy steels and wrought and cast austenitic SSs to define the effects of key material, loading, and environmental parameters on the fatigue lives of the steels. Experimental data are presented on the effects of surface roughness on the fatigue life of these steels in air and LWR environments. Statistical models are presented for estimating the fatigue e-N curves as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are discussed. Data available in the literature have been reviewed to evaluate the conservatism in the existing ASME Code fatigue evaluations. A critical review of the margins for ASME Code fatigue design curves is presented. Executive SummarySection III, Subsection NB, of the ASME Boiler and Pressure Vessel Code contains rules for the design of Class 1 components of nuclear power plants. Figures I-9.1 through I-9.6 of Appendix I to Section III specify the Code fatigue design curves for applicable structural materials. However, Section III, Subsection NB-3121, of the Code states that the effects of the coolant environment on fatigue resistance of a material were not intended to be addressed in these design curves. Therefore, the effects of environment on the fatigue resistance of materials used in operating pressurized water reactor and boiling water reactor plants, whose primary-coolant pressure boundary components were designed in accordance with the Code, are uncertain.The current Section-III fatigue design curves of the ASME Code were based primarily on strain-controlled fatigue tests of small polished specimens at room temperature in air. Best-fit curves to the experimental test data were first adjusted to account for the effects of mean stress and then lowered by a factor of 2 on stress and 20 on cycles (whichever was more conservative) to obtain the fatigue design curves. These factors are not safety margins but rather adjustment factors that must be applied to experimental data to obtain estimates of the lives of components. They were not intended to address the effects of the coolant environment on fatigue life. Recent fatigue-strain-vs.-life (e-N) data obtained in the U.S. and Japan demonstrate that light water reactor (LWR) environments can have potentially significant effects on the fatigue resistance of materials. Specimen lives obtained from tests in simulated LWR environments can be much shorter than those obtain...

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Full-Size Pressure Vessel Testing and Its Application to Design

Cited by 19 publications

References 0 publications

Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments.

Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments.

Review of Concepts and Status of Procedures for Fracture-Safe Design of Complex Welded Structures Involving Metals of Low to Ultrahigh Strength Levels

Review of the margins for ASME code fatigue design curve - effects of surface roughness and material variability.

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