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Author: H. Kinoshita Publisher: ISBN: Category : Alloying element Languages : en Pages : 9
Book Description
To investigate the effect of alloying elements on void formation and precipitation during neutron irradiation, vanadium and vanadium based alloys were irradiated in the experimental fast breeder reactor "JOYO" up to 6 x 1025 n/m2 at 670 to 870 K. Alloying elements were selected on the basis of volume size factors: carbon for an interstitial atom, chromium for an undersized substitutional atom and titanium and molybdenum are oversized ones. Voids were formed in all materials except in V-Ti alloys. The V-Cr alloy shows inhomogeneous void formation, and the swelling was larger compared to other alloys. The void formation was related to the radiation-induced precipitates which nucleated on dislocations. In the matrix of the V-Mo alloy, the precipitation was not confirmed, and homogeneous void formation occurred so the swelling was not large. Void formation and precipitation are discussed on the basis of alloying effects.
Author: H. Kinoshita Publisher: ISBN: Category : Alloying element Languages : en Pages : 9
Book Description
To investigate the effect of alloying elements on void formation and precipitation during neutron irradiation, vanadium and vanadium based alloys were irradiated in the experimental fast breeder reactor "JOYO" up to 6 x 1025 n/m2 at 670 to 870 K. Alloying elements were selected on the basis of volume size factors: carbon for an interstitial atom, chromium for an undersized substitutional atom and titanium and molybdenum are oversized ones. Voids were formed in all materials except in V-Ti alloys. The V-Cr alloy shows inhomogeneous void formation, and the swelling was larger compared to other alloys. The void formation was related to the radiation-induced precipitates which nucleated on dislocations. In the matrix of the V-Mo alloy, the precipitation was not confirmed, and homogeneous void formation occurred so the swelling was not large. Void formation and precipitation are discussed on the basis of alloying effects.
Author: BA. Loomis Publisher: ISBN: Category : Edema Languages : en Pages : 12
Book Description
The microstructures in V-15Cr-5Ti, V-10Cr-5Ti, V-3Ti-lSi, V-15Ti-7.5Cr, and V-20Ti alloys were examined by transmission electron microscopy after neutron irradiation at 600°C to 21 to 84 atom displacements per atom in the Materials Open Test Assembly of the Fast Flux Test Facility. The microstructures in these irradiated alloys were analyzed to determine the radiation-produced dislocation density, precipitate number density and size, and void number density and size. The results of these analyses were used to compute increases in yield stress and swelling of the irradiated alloys. The computed increase in yield stress was compared with the increase in yield stress determined from tension tests on these irradiated alloys. This comparison made it possible to evaluate the influence of alloy composition on the evolution of radiation-damaged microstructures and the resulting tensile properties.
Author: Publisher: ISBN: Category : Languages : en Pages : 28
Book Description
The microstructures in V-15Cr-5Ti, V-10Cr-5RTi, V-3Ti-1Si, V-15Ti-7.5Cr, and V-20Ti alloys were examined by transmission electron microscopy after neutron irradiation at 600°C to 21--84 atom displacements per atom in the Materials Open Test Assembly of the Fast Flux Test Facility. The microstructures in these irradiated alloys were analyzed to determine the radiation-produced dislocation density, precipitate number density and size, and void number density and size. The results of these analyses were used to compute increases in yield stress and swelling of the irradiated alloys. The computed increase in yield stress was compared with the increase in yield stress determined from tensile tests on these irradiated alloys. This comparison made it possible to evaluate the influence of alloy composition on the evolution of radiation-damaged microstructures and the resulting tensile properties. 11 refs.
Author: Publisher: ISBN: Category : Languages : en Pages : 24
Book Description
The microstructures of V-Ti, V-Cr-Ti, and V-Ti-Si alloys were characterized by transmission electron microscopy (TEM) after neutron irradiation in the Fast Flux Test Facility (FFTF) at 420 and 600°C to influences up to 114 dpa. Two types of irradiation-induced precipitates were identified, i.e., Ti2O and Ti5(Si, P)3. Blocky Ti(O, N, C) precipitates, which form by thermal processes during ingot fabrication, also were observed in all unirradiated and irradiated specimens. Irradiation-induced precipitation of spherical (
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Specimens of V-15Cr-5Ti, VANSTAR-7, and V-3Ti-1Si were encapsulated in TZM tubes containing 7Li to prevent interstitial pickup and irradiated in FFTF (MOTA experiment) to a damage level of 40 dpa. The irradiation temperatures were 420, 520, and 600°C. For a better simulation of fusion reactor conditions, helium was preimplanted in some specimens using a modified version of the ''tritium trick.'' The V-15Cr-5Ti alloy was most susceptible to irradiation hardening and helium embrittlement, followed by VANSTAR-7 and V-3Ti-1Si. VANSTAR-7 exhibited a relatively high maximum void swelling of approx. 6% at 520°C while V-15Cr-5Ti and V-3Ti-1Si had values of less than 0.3% at all three temperatures. The V-3Ti-1Si clearly outperformed the other two vanadium alloys in resisting the effects of neutron irradiation.
Author: DN. Braski Publisher: ISBN: Category : Helium embrittlement Languages : en Pages : 20
Book Description
Specimens of V-15Cr-5Ti, VANSTAR-7, and V-3Ti-1Si were encapsulated in molybdenum alloy tubes containing 7Li to prevent interstitial pickup and irradiated in the Fast Flux Test Facility (FFTF), using Materials Open Test Assembly (MOTA) experiments, to a damage level of 40 displacements per atom (dpa). The irradiation temperatures were 420, 520, and 600°C. For a better simulation of fusion reactor conditions, helium was preimplanted in some specimens using a modified version of the "tritium trick." The V-15Cr-5Ti alloy was most susceptible to irradiation hardening and helium embrittlement, followed by VANSTAR-7, and V-3Ti-1Si. VANSTAR-7 exhibited a relatively high maximum void swelling of ~6% at 520°C while V-15Cr-5Ti and V-3Ti-1Si had values of
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
This paper contains viewgraphs describing the effects of neutron irradiation on the tensile properties and microstructure of vanadium alloys in first wall fusion reactors. A tritium trick experiment was used to study the helium embrittlement and the stresses and strains on these materials in a controlled environment. (LSP).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Vanadium and vanadium with boron carbide additions (V-B4C) were irradiated to approx. 1 dpa in the Oak Ridge Research Reactor at controlled temperatures ranging from 455 to 925 K. The V-B4C alloy was enriched in 1°B, which produced approx. 3900 at. ppM helium. In the vanadium specimens, the dislocation microstructures varied from clusters of small (50 nm diam) dislocation loops (455 to 625 K) to larger, homogeneously distributed loops at higher temperatures. Their Burgers vectors were a/2
Author: H. Kinoshita
Author: H. Kinoshita
Author: BA. Loomis
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Author: DN. Braski![The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys. [Viewgraphs]. PDF](https://books.google.com/books/content/images/frontcover/5axEAQAACAAJ?fife=w80-h100)
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Author: C. J. Baroch