Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
Book Description
Effect of Neutron Irradiation in the Tensile Properties of the Zr-2.5 Wt Pct Nb (Cb)-O.5 Wt Pct Cu Alloy
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 35
Book Description
The effect of neutron irradiation on the tensile properties of the zr-2.5 wt per cent nb(cb)-0.5 wt per cent cu alloy
The Effect of Nuclear Radiation on Structural Metals
Author: Frederic R. Shober
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
Book Description
The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
Book Description
The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
Effect of neutron irradiation on tensile properties of the zirconium-2.5 weight per cent niobium alloy
The Effect of Fast Neutron Irradiation on the Tensile Properties of Specimens from Cold-worked Zirconium-2.5 WT. Percent Niobium Pressure Tubes
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Effect of Neutron Irradiation on the Tensile Properties and Growth of Zirconium 8.6 Wt% Aluminum
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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.
EFFECT OF NEUTRON IRRADIATION ON THE TENSILE PROPERTIES AND GROWTH OF ZIRCONIUM 8.6 WT PER CENT ALUMINUM.
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
Book Description
The Effect of Neutron Irradiation on the Tensile Properties and Growth of Zirconium 8.6 Wt% Aluminium
Author: H. E. Rosinger
Publisher: Pinawa, Man. : Materials and Component Development Branch, Whiteshell Nuclear Research Establishment, Atomic Energy of Canada Limited
ISBN:
Category :
Languages : en
Pages : 38
Book Description
Publisher: Pinawa, Man. : Materials and Component Development Branch, Whiteshell Nuclear Research Establishment, Atomic Energy of Canada Limited
ISBN:
Category :
Languages : en
Pages : 38
Book Description
Effect of Neutron Irradiation on Tensile and Fracture Toughness Properties of Copper Alloys and Their Joints with Stainless Steel
Author: P. Toft
Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 17
Book Description
Dispersion strengthened (CuAl25) and precipitation hardened (CuCrZr) copper alloys are being considered as candidate materials for the first wall and divertor components of ITER. In the present work, the tensile and fracture resistance properties of CuAl25 and CuCrZr alloys and their joints with 316LN stainless steel have been studied in the unirradiated and neutron irradiated conditions. The joints were produced by hot isostatic pressing (HIP) at 960°C for 3 hours at a pressure of 120 MPa. Test specimens of the base materials CuAl25 and CuCrZr alloys and of the joints (CuCrZr / 316LN and CuAl25 / 316LN) were irradiated with fission neutrons in the DR-3 reactor at Risø in the temperature range from 50°C to 350°C to a displacement dose level of about 0.3 dpa (NRT). Tensile specimens of these alloys were tested at temperatures in the range of 50°C to 350°C. Fracture resistance curves were determined using three point bend tests on specimens of the base materials and of the joints. Tensile and fracture toughness results, together with the metallography of the joints will be presented. Implications of these results and the deformation mechanisms will be briefly discussed.
Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 17
Book Description
Dispersion strengthened (CuAl25) and precipitation hardened (CuCrZr) copper alloys are being considered as candidate materials for the first wall and divertor components of ITER. In the present work, the tensile and fracture resistance properties of CuAl25 and CuCrZr alloys and their joints with 316LN stainless steel have been studied in the unirradiated and neutron irradiated conditions. The joints were produced by hot isostatic pressing (HIP) at 960°C for 3 hours at a pressure of 120 MPa. Test specimens of the base materials CuAl25 and CuCrZr alloys and of the joints (CuCrZr / 316LN and CuAl25 / 316LN) were irradiated with fission neutrons in the DR-3 reactor at Risø in the temperature range from 50°C to 350°C to a displacement dose level of about 0.3 dpa (NRT). Tensile specimens of these alloys were tested at temperatures in the range of 50°C to 350°C. Fracture resistance curves were determined using three point bend tests on specimens of the base materials and of the joints. Tensile and fracture toughness results, together with the metallography of the joints will be presented. Implications of these results and the deformation mechanisms will be briefly discussed.