In-reactor deformation of zirconium alloy tubes at 330 k PDF Download
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Author: E. F. Ibrahim
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: E. F. Ibrahim
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: R. A. Holt
Publisher:
ISBN:
Category : Anisotropy
Languages : en
Pages : 16
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Book Description
This paper briefly reviews work by the author identifying and describing in-reactor deformation mechanisms of materials and structures used in nuclear reactors, in particular, Zircaloy-2, Zircaloy-4, and Zr-2.5Nb, and the CANDU fuel channel (comprising Zr alloy pressure tubes, calandria tubes, and spacers). The discussion is set in the context of contemporary findings of other workers in the international community. The following themes are highlighted: The contributions of creep and growth to deformation; c-component dislocations and the fluence dependence of irradiation growth; anisotropy of irradiation growth; deformation equations and pressure tube-to-calandria tube contact in CANDU reactors; low temperature flux (damage rate) dependence of deformation rates. The first developments were reported in 1976 at the third conference in this series and there are ongoing developments in all areas. The linear low temperature flux dependence of creep and growth rates is yet to be satisfactorily explained.
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
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Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
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Author: D.S. Wood
Publisher:
ISBN:
Category :
Languages : en
Pages : 13
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Author: DS. Wood
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 18
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Book Description
High creep strain experiments have been carried out under irradiation using cold worked Zircaloy-2, cold-worked Zr-Nb, and heat treated Zr-Nb 0.6-in.-diameter tubes in DFR, DMTR, and PLUTO reactor. The tests in PLUTO were found to be the most useful since full creep curves were obtained using neutron radiography techniques. Creep strains of up to 9 percent were obtained on cold-worked Zircaloy-2 tubes without failure, thus substantiating the recommended pressure tube creep strain limit of 3 percent. Up to 5 percent creep strain was observed with cold-worked Zr-Nb tubing, but since one tube failed at only 1.8 percent strain it is not yet possible to specify a realistic yet safe creep limit for this material.
Author: Erich Tenckhoff
Publisher: ASTM International
ISBN: 080310958X
Category : Anisotropy
Languages : en
Pages : 85
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Book Description
Author: A. R. Causey
Publisher: Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories
ISBN: 9780660151892
Category : Nuclear reactors
Languages : en
Pages : 22
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Book Description
The anistropy of creep deformation of Zr-2.5Nb pressure tubes during service in CANDU reactors is related to the anisotropic physical properties of the hexagonal crystal structure of zirconium. These physical properties contribute to the development during fabrication of an anisotropic microstructure, including crystallographic textures, grain morphologies, and dislocation structures. A number of studies tried to relate the anisotropic deformation of the polycrystalline zirconium alloys to those of their individual grains by accounting for the microstructural features, particularly the crystallographic texture, but they suffered from a lack of experimental data from biaxial creep tests on materials that have crystallographic texture similar to that of the pressure tubes. This experiment contributes to the development of a reliable model for Zr-2.5Nb tubes by using two batches of small tubes, one of which has a crystallographic texture similar to that of the CANDU power reactor pressure tubing, the other having a texture that is completely different. The results are analyzed in terms of texture using a self-consistent model to account for the effects of the grain interactions.
Author: P. A. Ross-Ross
Publisher:
ISBN:
Category :
Languages : en
Pages : 36
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Author: AR. Causey
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 15
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Book Description
Changes in shape of internally pressurized tubes caused by operating temperatures and pressures are enhanced by fast neutron irradiation. Lengths and diameters of Zr-2.5 wt% Nb pressure tubes in CANada Deuterium Uranium-Pressurized Heavy Water (CANDU-PHW) power reactors and test reactors have been monitored periodically over the past 15 years. Axial and transverse strain rates have been evaluated in terms of the operating variables and the crystallographic texture and anisotropic microstructure of the extruded and cold-drawn tubes. The anisotropic deformation can be described by models for creep and irradiation growth in which the anisotropy factors are calculated from texture. It is assumed that prismatic slip is the dominant creep mode and that growth occurs by net fluxes of interstitials to a nonrandom distribution of ?a? type edge dislocations and vacancies to ?a? type screw dislocations, ?c? type edge dislocations, and grain boundaries. The equations based on data from the Pickering Generating Station and WR1 test reactors give good agreement with measurements on internally pressurized tubes in Bruce Generating Station and the National Reactor Universal (NRU) test reactor and uniaxially stressed specimen in NRU.
