Author: S. Chatterjee
Publisher:
ISBN:
Category : Crack initiation energy
Languages : en
Pages : 12
Book Description
Four A533B pressure vessel steels containing 0.16 wt% copper, nickel and phosphorous ranging from 0.10 to 0.82 wt% and 0.006 to 0.02 wt% respectively, and a AISI 403 stainless steel, a typical end fitting material used in pressurised heavy water reactors, in the unirradiated condition, were evaluated by instrumented impact testing to determine the crack initiation energy (CVNi), total absorbed energy (CVN), ductilebrittle transition temperature (T41J,T0.89mm), dynamic yield strength (?yd) and dynamic initiation fracture toughness (Kid). Three of these steels were irradiated at 563K to a nominal fast fluence of 1x1019, n/cm2 (E > 1 MeV) and the corresponding parameters were evaluated.
Fracture Toughness and Impact Tests on Neutron Irradiated Ferritic Steels
Author: S. Chatterjee
Publisher:
ISBN:
Category : Crack initiation energy
Languages : en
Pages : 12
Book Description
Four A533B pressure vessel steels containing 0.16 wt% copper, nickel and phosphorous ranging from 0.10 to 0.82 wt% and 0.006 to 0.02 wt% respectively, and a AISI 403 stainless steel, a typical end fitting material used in pressurised heavy water reactors, in the unirradiated condition, were evaluated by instrumented impact testing to determine the crack initiation energy (CVNi), total absorbed energy (CVN), ductilebrittle transition temperature (T41J,T0.89mm), dynamic yield strength (?yd) and dynamic initiation fracture toughness (Kid). Three of these steels were irradiated at 563K to a nominal fast fluence of 1x1019, n/cm2 (E > 1 MeV) and the corresponding parameters were evaluated.
Publisher:
ISBN:
Category : Crack initiation energy
Languages : en
Pages : 12
Book Description
Four A533B pressure vessel steels containing 0.16 wt% copper, nickel and phosphorous ranging from 0.10 to 0.82 wt% and 0.006 to 0.02 wt% respectively, and a AISI 403 stainless steel, a typical end fitting material used in pressurised heavy water reactors, in the unirradiated condition, were evaluated by instrumented impact testing to determine the crack initiation energy (CVNi), total absorbed energy (CVN), ductilebrittle transition temperature (T41J,T0.89mm), dynamic yield strength (?yd) and dynamic initiation fracture toughness (Kid). Three of these steels were irradiated at 563K to a nominal fast fluence of 1x1019, n/cm2 (E > 1 MeV) and the corresponding parameters were evaluated.
Radiation Effects on Toughness of Ferritic Steels for Reactor Vessels
Author: L. P. Trudeau
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 200
Book Description
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 200
Book Description
Effect of Specimen Size and Material Condition on the Charpy Impact Properties of 9Cr-1Mo-V-Nb Steel
Author: WR. Corwin
Publisher:
ISBN:
Category : Charpy specimens
Languages : en
Pages : 14
Book Description
The degradation of fracture resistance of ferritic steels subjected to neutron irradiation can be qualitatively evaluated by examining the shift in the ductile-to-brittle transition temperature and the drop in the upper-shelf energy as determined in the Charpy impact test. That is an empirical test, however, and its usefulness is derived primarily from either correlation to more quantitative measures of fracture toughness or comparison with other Charpy test results for different materials or conditions of interest. Any departures from the standard testing procedures, including specimen dimensions, will yield results which will vary in some degree from those of a standard test.
Publisher:
ISBN:
Category : Charpy specimens
Languages : en
Pages : 14
Book Description
The degradation of fracture resistance of ferritic steels subjected to neutron irradiation can be qualitatively evaluated by examining the shift in the ductile-to-brittle transition temperature and the drop in the upper-shelf energy as determined in the Charpy impact test. That is an empirical test, however, and its usefulness is derived primarily from either correlation to more quantitative measures of fracture toughness or comparison with other Charpy test results for different materials or conditions of interest. Any departures from the standard testing procedures, including specimen dimensions, will yield results which will vary in some degree from those of a standard test.
The Effects of Neutron Irradiation on Fracture Toughness of Austenitic Stainless Steels
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 16
Book Description
Austenitic stainless steels are used extensively as structural alloys in reactor pressure vessel internal components 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. This paper presents results of fracture toughness J-R curve tests on four heats of Type 304 stainless steel that were irradiated to fluence levels of (almost equal to)0.3 and 0.9 x 1021 n cm−2 (E>1 MeV) at (almost equal to)288 C in a helium environment in the Halden heavy water boiling reactor. The tests were performed on 1/4-T compact tension specimens in air at 288 C; crack extensions were determined by both DC potential and elastic unloading compliance techniques.
Publisher:
ISBN:
Category :
Languages : en
Pages : 16
Book Description
Austenitic stainless steels are used extensively as structural alloys in reactor pressure vessel internal components 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. This paper presents results of fracture toughness J-R curve tests on four heats of Type 304 stainless steel that were irradiated to fluence levels of (almost equal to)0.3 and 0.9 x 1021 n cm−2 (E>1 MeV) at (almost equal to)288 C in a helium environment in the Halden heavy water boiling reactor. The tests were performed on 1/4-T compact tension specimens in air at 288 C; crack extensions were determined by both DC potential and elastic unloading compliance techniques.
Effects of Radiation on Materials
Author: Arvind S. Kumar
Publisher: ASTM International
ISBN: 0803114885
Category : Materials
Languages : en
Pages : 1319
Book Description
Publisher: ASTM International
ISBN: 0803114885
Category : Materials
Languages : en
Pages : 1319
Book Description
Fracture Properties of Irradiated Alloys
Author: F. H. Huang
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 446
Book Description
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 446
Book Description
Brittle Fracture of Steel, 1950-1961
Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 48
Book Description
The bibliography has been compiled from the unclassified literature for the period January 1950 through November 15, 1961. Reviews and bibliographies which have been listed furnish references to historical reviews and earlier studies on brittle fracture. An author and a subject index are included.
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 48
Book Description
The bibliography has been compiled from the unclassified literature for the period January 1950 through November 15, 1961. Reviews and bibliographies which have been listed furnish references to historical reviews and earlier studies on brittle fracture. An author and a subject index are included.
Effects of Radiation on Materials
Author: Todd R. Allen
Publisher: ASTM International
ISBN: 0803134010
Category : Materials
Languages : en
Pages : 411
Book Description
Publisher: ASTM International
ISBN: 0803134010
Category : Materials
Languages : en
Pages : 411
Book Description
The Use of Small-scale Specimens for Testing Irradiated Material
Author: W. R. Corwin
Publisher: ASTM International
ISBN: 0803104405
Category : Alloys
Languages : en
Pages : 387
Book Description
Publisher: ASTM International
ISBN: 0803104405
Category : Alloys
Languages : en
Pages : 387
Book Description
Comparison of Fracture Behavior for Low-swelling Ferritic and Austenitic Alloys Irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 41
Book Description
Fracture toughness testing was conducted to investigate the radiation embrittlement of high-nickel superalloys, modified austenitic steels and ferritic steels. These materials have been experimentally proven to possess excellent resistance to void swelling after high neutron exposures. In addition to swelling resistance, post-irradiation fracture resistance is another important criterion for reactor material selection. By means of fracture mechanics techniques the fracture behavior of those highly irradiated alloys was characterized in terms of irradiation and test conditions. Precipitation-strengthened alloys failed by channel fracture with very low postirradiation ductility. The fracture toughness of titanium-modified austenitic stainless steel D9 deteriorates with increasing fluence to about 100 displacement per atom (dpa), the fluence level at which brittle fracture appears to occur. Ferritic steels such as HT9 are the most promising candidate materials for fast and fusion reactor applications. The upper-shelf fracture toughness of alloy HT9 remained adequate after irradiation to 180 dpa although its ductile- brittle transition temperature (DBTT) shift by low temperature irradiation rendered the material susceptible to brittle fracture at room temperature. Understanding the fracture characteristics under various irradiation and test conditions helps reduce the potential for brittle fracture by permitting appropriate measure to be taken.
Publisher:
ISBN:
Category :
Languages : en
Pages : 41
Book Description
Fracture toughness testing was conducted to investigate the radiation embrittlement of high-nickel superalloys, modified austenitic steels and ferritic steels. These materials have been experimentally proven to possess excellent resistance to void swelling after high neutron exposures. In addition to swelling resistance, post-irradiation fracture resistance is another important criterion for reactor material selection. By means of fracture mechanics techniques the fracture behavior of those highly irradiated alloys was characterized in terms of irradiation and test conditions. Precipitation-strengthened alloys failed by channel fracture with very low postirradiation ductility. The fracture toughness of titanium-modified austenitic stainless steel D9 deteriorates with increasing fluence to about 100 displacement per atom (dpa), the fluence level at which brittle fracture appears to occur. Ferritic steels such as HT9 are the most promising candidate materials for fast and fusion reactor applications. The upper-shelf fracture toughness of alloy HT9 remained adequate after irradiation to 180 dpa although its ductile- brittle transition temperature (DBTT) shift by low temperature irradiation rendered the material susceptible to brittle fracture at room temperature. Understanding the fracture characteristics under various irradiation and test conditions helps reduce the potential for brittle fracture by permitting appropriate measure to be taken.