The Effect of Fusion-relevant Helium Levels on the Mechanical Properties of Isotopically Tailored Ferritic Alloys PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages : 6
Book Description
The yield and maximum strengths of an irradiated series of isotopically tailored ferritic alloys were evaluated using the shear punch test. The composition of three of the alloys was Fe-12Cr-1.5Ni. Different balances of nickel isotopes were used in each alloy in order to produce different helium levels. A fourth alloy, which contained no nickel, was also irradiated. The addition of nickel at any isotopic balance to the Fe-12Cr base alloy significantly increased the shear yield and maximum strengths of the alloys, and as expected, the strength of the alloys decreased with increasing irradiation temperature. Helium itself, up to 75 appm over 7 dpa appears to have little effect on the mechanical properties of the alloys.
Author: Publisher: ISBN: Category : Languages : en Pages : 6
Book Description
The yield and maximum strengths of an irradiated series of isotopically tailored ferritic alloys were evaluated using the shear punch test. The composition of three of the alloys was Fe-12Cr-1.5Ni. Different balances of nickel isotopes were used in each alloy in order to produce different helium levels. A fourth alloy, which contained no nickel, was also irradiated. The addition of nickel at any isotopic balance to the Fe-12Cr base alloy significantly increased the shear yield and maximum strengths of the alloys, and as expected, the strength of the alloys decreased with increasing irradiation temperature. Helium itself, up to 75 appm over 7 dpa appears to have little effect on the mechanical properties of the alloys.
Author: Publisher: ISBN: Category : Languages : en Pages : 11
Book Description
Three Fe-Cr-Ni alloys have been doped with 0.4% 59Ni for side-by-side irradiations of doped and undoped materials in order to determine the effects of fusion-relevant levels of helium production on microstructural development and mechanical properties. The alloys were irradiated in three successive cycles of the Materials Open Test Assembly (MOTA) located in the Fast Flux Test Facility (FFTF). Following irradiation, helium levels were measured by isotope dilution mass spectrometry. The highest level of helium achieved in doped alloys was 172 appm at 9.1 dpa for a helium(appm)-to-dpa ratio of 18.9. The overall pattern of predicted helium generation rates in doped and undoped alloys is in good agreement with the helium measurements.
Author: DS. Gelles Publisher: ISBN: Category : Ferritic/martensitic steels Languages : en Pages : 12
Book Description
A series of alloys have been made adding various isotopes of nickel in order to vary the production of helium during irradiation by a two step nuclear reaction in a mixed spectrum reactor. The alloys use a base composition of Fe-12Cr with an addition of 1.5% nickel, either in the form of 60Ni which produces no helium, 59Ni which produces helium at a rate of about 10 appm He/dpa, or natural nickel which provides an intermediate level of helium due to delayed development of 59Ni. Specimens were irradiated in the HFIR at Oak Ridge, TN to 7.5 dpa at 300 and 400°C. Microstructural examinations indicated that nickel additions promote precipitation in all alloys, but the effect appears to be much stronger at 400°C than at 300°C. There is sufficient dose by 7 dpa (and with 2 appm He) to initiate void swelling in ferritic/martensitic alloys. Little difference was found between response from 59Ni and natural nickel. Also, helium bubble development for high helium generation conditions appeared to be very different at 300 and 400°C. At 300°C, it appeared that high densities of bubbles formed whereas at 400°C, bubbles could not be identified, possibly because of the complexity of the microstructure, but more likely because helium accumulated at precipitate interfaces.
Author: W. R. Corwin Publisher: ASTM International ISBN: 0803124767 Category : Light water reactors Languages : en Pages : 630
Book Description
As part of an increasing interest in radiation embrittlement for aging nuclear reactors, scientists gathered in New Orleans in January 1997 to consider the interests and capabilities of the scientific-testing community and of the commercial light-water-cooled power-reactor industry in terms of improving methods to characterize component integrity. The resulting 37 papers concentrate on the use of unique small and miniature specimens; nondestructive, nonintrusive, and in- situ test techniques for measuring mechanical and fracture properties; the application of tests to irradiation-induced embrittlement; and actual examples of tests to determine material integrity and to evaluate potential component life extension. They consider experimental, analytical, and computational aspects. Annotation copyrighted by Book News, Inc., Portland, OR
Author: Publisher: ISBN: Category : Languages : en Pages : 8
Book Description
The objective of this effort is to study the separate and synergistic effects of helium and other important variables on the evolution of microstructure and macroscopic properties during irradiation of structural metals. The alloys employed in this study were nominally Fe-15Cr-25Ni, Fe-15Cr-25Ni-0.04P and Fe-15Cr-45Ni (wt %) in both the cold worked and annealed conditions. Tensile testing and microscopy continue on specimens removed from the first, second and third discharges of the 59Ni isotopic doping experiment. The results to date indicate that helium/dpa ratios typical of fusion reactors (4 to 19 appm/dpa) do not lead to significant changes in the yield strength of model Fe-Cr-Ni alloys. Measurements of helium generated in undoped specimens from the second and third discharges show that the helium/dpa ratio increases during irradiation in FFTF due to the production of 59Ni. In specimens doped with 59Ni prior to irradiation, the helium/dpa ratio can increase, decrease or remain the same during the second irradiation interval. This behavior occurs because the cross sections for the production and burnout of 59Ni are very sensitive to core location and the nature of neighboring components. 14 refs., 5 figs., 3 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages : 14
Book Description
Tensile testing on model Fe-Cr-Ni alloys removed from four discharges of the 59Ni isotopic doping experiment in FFTF indicates that helium/dpa ratios typical of fusion reactors do not produce changes in the yield strength or elongation that are significantly different from those at much lower helium generation rates. It also appears that tensile properties approach a saturation level that is dependent only on the final irradiation temperature, but not prior temperature history or thermomechanical starting condition. 14 refs., 4 figs., 1 tab.
Author: ML. Hamilton Publisher: ISBN: Category : Ferritic alloys Languages : en Pages : 6
Book Description
The shear punch test was used to evaluate the strengthening associated with the production of helium in model Fe-Cr-Ni alloys during irradiation in HFIR at 300-600°C. Four alloys, were considered, a base alloy of composition Fe-12Cr and three alloys with 1.5% Ni, doped isotopically to contain 60Ni, natural nickel or 59Ni. The addition of nickel in any isotopic balance significantly strengthened the base alloy, and as expected, the strength of the alloys decreased with increasing irradiation temperature. Helium itself, however, up to the 75 appm produced over 7 dpa appeared to have little effect on the strength of the alloys.
Author: Robert Odette Publisher: Newnes ISBN: 012397349X Category : Technology & Engineering Languages : en Pages : 676
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
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Author: DS. Gelles
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