Results of fracture mechanics tests on PNC SUS 304 plate

Mills, W.J.; James, L.A.; Blackburn, L.D.

doi:10.2172/5505761

Cited by 4 publications

(4 citation statements)

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“…[13][14][15][16]; experimental data for the tests are given in the Appendix. Duplicate tests were conducted for Heats L2 and C16.…”

Section: Nonirradiated Type 304 Stainless Steelmentioning

confidence: 99%

“…1. [10][11][12][13][14][15][16][17][18] The effects of irradiation may be divided into three regimes: little or no loss of toughness below a threshold exposure of ª1 dpa, substantial decrease in toughness at exposures of 1-10 dpa, and no further reduction in toughness above a saturation exposure of 10 dpa. The effect is largest in high-toughness steels.…”

Section: Introductionmentioning

confidence: 99%

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Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Chopra¹,

Gruber²,

Shack³

2003

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Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10 21 n/cm 2 (E > 1 MeV) (ª3.0 dpa) at ª288°C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling water reactor (BWR) environments, and fracture toughness tests were conducted in air. Neutron irradiation at 288°C decreases the fracture toughness of the steels; the data from commercial heats fall within the scatter band for the data obtained at higher temperatures. In addition, the results indicate significant enhancement of CGRs of the irradiated steels in normal water chemistry BWR environment; the CGRs for irradiated steels are a factor of ª5 higher than the disposition curve proposed for sensitized austenitic SSs. The rates decreased by more than an order of magnitude in low-dissolved-oxygen BWR environment.

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“…[13][14][15][16]; experimental data for the tests are given in the Appendix. Duplicate tests were conducted for Heats L2 and C16.…”

Section: Nonirradiated Type 304 Stainless Steelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Chopra¹,

Gruber²,

Shack³

2003

View full text Add to dashboard Cite

show abstract

“…[11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26] In these studies, the embrittlement of the materials has been characterized in terms of tensile properties, Charpy-impact properties, and fracture toughness. Irradiation damage is characterized by either the neutron fluence in neutrons per square centimeter (n/cm 2 ) or the average number of displacements experienced by each atom, i.e., displacements per atom (dpa).…”

Section: Introductionmentioning

confidence: 99%

“…1a and b, respectively. 2,3,[11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26][27] The fast reactor data show a rapid decrease in fracture toughness at a neutron dose of 1-2 dpa (Fig. 1a); the neutron dose at the onset of the rapid decrease varies with the chemical composition and heat treatment of the steel.…”

Section: Introductionmentioning

confidence: 99%

Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments.

Chopra¹,

Shack²

2008

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In light water reactors, austenitic stainless steels (SSs) are used extensively as structural alloys in reactor core internal components because of their high strength, ductility, and fracture toughness. However, exposure to high levels of neutron irradiation for extended periods degrades the fracture properties of these steels by changing the material microstructure (e.g., radiation hardening) and microchemistry (e.g., radiation-induced segregation). Experimental data are presented on the fracture toughness and crack growth rates (CGRs) of wrought and cast austenitic SSs, including weld heataffected-zone materials, that were irradiated to fluence levels as high as ≈ 2 x 10 21 n/cm 2 (E > 1 MeV) (≈ 3 dpa) in a boiling heavy water reactor at 288-300°C. The results are compared with the data available in the literature. The effects of material composition, irradiation dose, and water chemistry on CGRs under cyclic and stress corrosion cracking conditions were determined. A superposition model was used to represent the cyclic CGRs of austenitic SSs. The effects of neutron irradiation on the fracture toughness of these steels, as well as the effects of material and irradiation conditions and test temperature, have been evaluated. A fracture toughness trend curve that bounds the existing data has been defined. The synergistic effects of thermal and radiation embrittlement of cast austenitic SS internal components have also been evaluated. Paperwork Reduction Act StatementThis NUREG does not contain information collection requirements and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Public Protection NotificationThe NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a current valid OMB control number. ForewordThis report presents the results of a study of simulated light-water reactor coolants, material chemistry, and irradiation damage and their effects on the susceptibility to stress-corrosion cracking of various commercially available and laboratory-melted stainless steels. This report is one of a series dating back about 8 years, describing such results, which are required to support analysis of the structural integrity of reactor internal components, many of which are subject to irradiation-assisted stress-corrosion cracking (IASCC).The earlier reports detailed crack growth rates in heat-affected zones adjacent to stainless steel weldments, and they comprised the final publications based on specimens irradiated in Phase I (of two) in the Halden test reactor. Phase I irradiations principally involved stainless steels of wide-ranging chemistry (including commercial steels of typical chemistry) and conventional heat treatment and product form processing. By contrast, this report is the first to present data from specimens irradiated in Phase II, which featured a variety of innovatively fabricated and engineered ...

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Neutron irradiation effect on the fracture toughness of 18Cr-10Ni-Ti steel and metal of its welds

Smirnov

Марголин

Lapin

et al. 2012

Inorg. Mater. Appl. Res.

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Results of fracture mechanics tests on PNC SUS 304 plate

Cited by 4 publications

References 0 publications

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Fracture toughness and crack growth rates of irradiated austenitic stainless steels.

Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments.

Neutron irradiation effect on the fracture toughness of 18Cr-10Ni-Ti steel and metal of its welds

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