Author: G. R. Smolik
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 124
Book Description
The Effects of Neutron Irradiation Upon the Strength and Ductility of Vanadium
Effects of Neutron Irradiation on High-purity Vanadium
Author: Richard Francis Stevens (Jr)
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 36
Book Description
Because of the potential elevated-temperature applications of high-purity vanadium in nuclear reactors an investigation was conducted to determine the effects of nuclear irradiation upon the properties of the pure metal. The results of this investigation indicated that the effects caused by irradiation, increased strength and hardness and decreased ductility, could be removed by annealing at 650°C. Thus, when suitable protected, high-purity vanadium metal could be used in the portions of nuclear reactors subjected to temperatures of 600°C and to neutron bombardment levels as high as 1.8x1020 neutrons/cm2/sec. (NVT).
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 36
Book Description
Because of the potential elevated-temperature applications of high-purity vanadium in nuclear reactors an investigation was conducted to determine the effects of nuclear irradiation upon the properties of the pure metal. The results of this investigation indicated that the effects caused by irradiation, increased strength and hardness and decreased ductility, could be removed by annealing at 650°C. Thus, when suitable protected, high-purity vanadium metal could be used in the portions of nuclear reactors subjected to temperatures of 600°C and to neutron bombardment levels as high as 1.8x1020 neutrons/cm2/sec. (NVT).
Effects of Neutron Irradiation on the Elevated Temperature Mechanical Properties of Nickel-Base and Refractory Metal Alloys
Author: T. T. Claudson
Publisher:
ISBN:
Category : Ductility
Languages : en
Pages : 28
Book Description
Nuclear research and power reactors are now being designed which must operate at temperatures and coolant environments dictating the use of nickel-base and refractory metal alloys for structural components, fuel cladding, and power equipment. Investigation of the effects of irradiation and environment upon the mechanical properties of several nickel-base and refractory metal alloys has been initiated at the Pacific Northwest Laboratory. Tension specimens of Inconel 600, Inconel 625, Inconel 702, Inconel 718, Incoloy 800, Hastelloy C, Hastelloy N, Hastelloy X-280, and Hastelloy R-235 have been irradiated to exposures exceeding 1 x 1021 nvt (E > 1 Mev) in 50 C water, 280 C water, and 740 C gaseous environments. These specimens have been tested in the pre- and postirradiated conditions at room temperature, 300 C, and 650 C. Several metallurgical conditions of the materials have also been examined and the changes in mechanical properties due to the irradiation have been noted. The Cb-1 Zr, Cb-752, TZM Mo, and W-25 Re refractory metals have been irradiated at ambient temperatures, and the effects of irradiation upon the mechanical properties have been evaluated at room temperature and 1090 C. The data obtained for both the nickel-base and refractory metal alloys tested indicate that there is a marked effect upon the mechanical properties due to the thermal environment. In addition to this effect, effects due to the irradiation were also found. Comparison of the elevated temperature data to the room temperature data shows a marked decrease in both strength and ductility. Metallographic examination of these materials is continuing in an attempt to find the cause of these damages.
Publisher:
ISBN:
Category : Ductility
Languages : en
Pages : 28
Book Description
Nuclear research and power reactors are now being designed which must operate at temperatures and coolant environments dictating the use of nickel-base and refractory metal alloys for structural components, fuel cladding, and power equipment. Investigation of the effects of irradiation and environment upon the mechanical properties of several nickel-base and refractory metal alloys has been initiated at the Pacific Northwest Laboratory. Tension specimens of Inconel 600, Inconel 625, Inconel 702, Inconel 718, Incoloy 800, Hastelloy C, Hastelloy N, Hastelloy X-280, and Hastelloy R-235 have been irradiated to exposures exceeding 1 x 1021 nvt (E > 1 Mev) in 50 C water, 280 C water, and 740 C gaseous environments. These specimens have been tested in the pre- and postirradiated conditions at room temperature, 300 C, and 650 C. Several metallurgical conditions of the materials have also been examined and the changes in mechanical properties due to the irradiation have been noted. The Cb-1 Zr, Cb-752, TZM Mo, and W-25 Re refractory metals have been irradiated at ambient temperatures, and the effects of irradiation upon the mechanical properties have been evaluated at room temperature and 1090 C. The data obtained for both the nickel-base and refractory metal alloys tested indicate that there is a marked effect upon the mechanical properties due to the thermal environment. In addition to this effect, effects due to the irradiation were also found. Comparison of the elevated temperature data to the room temperature data shows a marked decrease in both strength and ductility. Metallographic examination of these materials is continuing in an attempt to find the cause of these damages.
The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys
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
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
Effects of Neutron Irradiation and Hydrogen on Ductile-brittle Transition Temperatures of V-Cr-Ti Alloys
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
The effects of neutron irradiation and hydrogen on the ductile- brittle transition temperatures (DBTTs) of unalloyed vanadium and V-Cr-Ti alloys were determined from Charpy-impact tests on 1/3 ASTM standard size specimens and from impact tests on 3-mm diameter discs. The tests were conducted on specimens containing
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
The effects of neutron irradiation and hydrogen on the ductile- brittle transition temperatures (DBTTs) of unalloyed vanadium and V-Cr-Ti alloys were determined from Charpy-impact tests on 1/3 ASTM standard size specimens and from impact tests on 3-mm diameter discs. The tests were conducted on specimens containing
The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys. [Viewgraphs].
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).
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).
Effect of Neutron Irradiation on Vanadium
Author: R. Bajaj
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 12
Book Description
The effect of neutron irradiation on vanadium containing 50 to 800 weight ppm oxygen was studied using electrical resistivity, internal friction, and mechanical property measurements. The resistivity and internal friction specimens were irradiated to 3 x 1018 neutrons/cm2 (E > 1 MeV) at -190 C(-310 F) and the tension test specimens were irradiated to 1.2 x 1019 neutrons/cm2 (E > 1 MeV) at 106 C (223 F). Postirradiation annealing treatments were performed up to 220 C (428 F) for the resistivity and internal friction specimens and up to 520 C (968 F) for the tension test specimens.
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 12
Book Description
The effect of neutron irradiation on vanadium containing 50 to 800 weight ppm oxygen was studied using electrical resistivity, internal friction, and mechanical property measurements. The resistivity and internal friction specimens were irradiated to 3 x 1018 neutrons/cm2 (E > 1 MeV) at -190 C(-310 F) and the tension test specimens were irradiated to 1.2 x 1019 neutrons/cm2 (E > 1 MeV) at 106 C (223 F). Postirradiation annealing treatments were performed up to 220 C (428 F) for the resistivity and internal friction specimens and up to 520 C (968 F) for the tension test specimens.
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 960
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 960
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Report on the Effects of Neutron Radiation on Structural Materials
Author: M. Kangilaski
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 264
Book Description
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 264
Book Description