Effect of microstructure on the end-to-end and tube-to-tube variations in the irradiation Creep and growth of cold-worked zr-2.5nb pressure tubes PDF Download
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Author: R. J. Klassen
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: R. J. Klassen
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: L. Walters
Publisher:
ISBN:
Category : In-reactor deformation
Languages : en
Pages : 33
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Creep experiments have been performed on biaxially stressed 10 mm diameter Zr-2.5Nb capsules. As the pressurized capsules were obtained from micro-pressure tubes, which were fabricated by the same process as CANDU power reactor pressure tubes, they have a similar microstructure to that of the full-size tubes. The experiments were performed in the OSIRIS test reactor at nominal operating temperatures ranging from 553 and 613 K in fast neutron fluxes up to 2 x 1018 n.m-2.s-1 (E > 1 MeV). Diametral and axial strains are reported as functions of fluence for specimens internally pressurized to hoop stresses from 0 to 160 MPa and irradiated to 26.5 dpa. The effects of microstructure, temperature, and cold work on irradiation creep are shown. The analysis of OSIRIS data combined with data from in-service CANDU tubes has revealed some significant observations regarding pressure tube deformation: (i) that irradiation creep anisotropy varies with temperature, (ii) texture appears to have a more significant effect on axial creep than on diametral creep, (iii) diametral strain appears to be strongly dependent on grain size and aspect ratio, and (iv) that whereas cold-work correlates with the axial creep of the capsules, there appears to be no statistically significant dependence of diametral creep on cold-work.
Author: RA. Holt
Publisher:
ISBN:
Category : Dislocation density
Languages : en
Pages : 16
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Specimens of cold-worked Zr-2.5% Nb pressure tube material fabricated by several different routes have been irradiated unstressed in the Dido reactor at Atomic Energy Research Establishment (AERE) Harwell to fluences up to 7.5 x 1025 n/m2, E & 1 MeV (about 18 dpa). Their irradiation growth behavior has been investigated as a function of temperature in the range 553 to 623 K.
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: F. A. Garner
Publisher: ASTM International
ISBN: 0803109628
Category : Conferences
Languages : en
Pages : 919
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Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: RG. Fleck
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 18
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Pressure tube elongation in CANDU (CANada Deuterium Uranium) reactors occurs mainly as a result of irradiation growth and may limit the useful lifetime of the pressure tubes. The object of this investigation was to examine the effects of microstructural variation on the irradiation growth rate as part of a pressure tube development program. Three modifications of Zr-2.5Nb material have been irradiated at 553 K to high fast fluences of 3 x 1025 n/m2 in the Dido reactor at the United Kingdom Atomic Energy Authority Harwell, and the irradiation growth was measured at preselected fluences up to the highest fluence.
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: A. Bind
Publisher:
ISBN:
Category : Bearings industry
Languages : en
Pages : 24
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In heavy water cooled nuclear reactors, Zr-2.5Nb alloy is used for pressure tubes under cold worked and stress relieved (CWSR) condition in Canadian Deuterium Uranium (CANDU) reactors and under quenched and aged condition in RBMK and Fugen reactors. Because of its ease of use and the lower cost of fabrication, most of the work reported in literature is focused on the development and characterization of cold worked and stress relieved pressure tube material. However, recent work showed that the tubes manufactured using quenched and aged route showed a lower and predictable rate of in-reactor deformation during reactor operation as compared to those fabricated using the CWSR route. One of the important stages in the fabrication of heat treated pressure tube material is solution heat treatment (SHT), which governs the microstructure and hence, the mechanical properties of pressure tubes. Usually, SHT is carried out in two phase (? + ?) region at a temperature closer to the ? transus. The present work characterizes the influence of different SHT parameters such as soaking temperature (850, 870, and 890°C) and duration (15 and 30 min) on microstructure, texture, and Nb partitioning between phases and mechanical properties such as tensile properties, hardness, and fracture toughness. Fracture toughness parameters were determined as per ASTM standard E1820-11. Optical microscopy was used for microstructure, X-ray diffraction for texture, and EPMA for Nb partitioning investigation. The fracture surfaces were examined using SEM.
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 767
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