Author: R. S. W. ShewfeltPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
The anisotropic deformation of zr-2.5 wt percent nb CANDU pressure tubes between 20 and 700 degrees c
Author: R. S. W. ShewfeltINIS Atomindex
Author: Assessment of the Kinetics of Local Plastic Deformation of Zr-2.5%Nb CANDU Pressure Tube Material
Author: Bipasha BosePublisher:
ISBN:
Category :
Languages : en
Pages : 318
Book Description
Constant-load pyramidal indentation creep tests and high precision micro-indentation strain rate change tests were performed to assess the effect of indentation depth, irradiation damage and temperature on the mechanical anisotropy and local plastic deformation parameters of the Zr-2.5%Nb CANDU pressure tube material. Polished samples aligned normal to the transverse (TN), axial (AN) and radial (RN) directions of the pressure tube were irradiated with 8.5 MeV Zr+ ions to simulate the effect of neutron irradiation. Constant-load pyramidal indentation creep tests performed at 25ðC show that the average indentation stress, indt =0 s, increases with decreasing indentation depth and increasing levels of irradiation. The ratio of indt =0 s on the TN plane relative to that on the AN and RN planes was 1.3 and 1.2 respectively before irradiation which reduced to 1.04 and 1.08 respectively after irradiation indicating a decrease in anisotropy as a result of irradiation hardening. The apparent activation energy, 0 DG, of the obstacles that limit the rate of dislocation glide during indentation creep at 25ðC does not change with indentation depth and direction but increases with increasing levels of irradiation damage. Samples irradiated at 300°C with 8.5 MeV Zr+ ions show similar changes in indt =0 s, anisotropy and 0 DG with increasing levels of irradiation. However the values are lower than those exposed to Zr+ irradiation at 25°C indicating the effect of concurrent thermal annealing on the accumulation of irradiation damage. Micro-indentation creep tests performed on the non-irradiated samples over the temperature range from 25 to 400ðC show that the ratio of indt =0 s in the transverse direction relative to that in the radial and axial directions decreased with increasing temperature. 0 DG increases with increasing temperature and is independent of indentation direction. Micro-indentation strain rate change tests show that the inverse apparent activation area of the deformation process followed a linear, Cottrell Stokes type, dependence upon the applied stress. The increase in the apparent activation work indicates that the irradiation induced damage act as strong obstacles to dislocation glide and thus increase both the magnitude and the strain rate sensitivity of the yield stress of the Zr-2.5%Nb alloy at 25ðC.
De L'anisotropie Du Fluage en Réacteur Des Tubes en Zr-2,5 Nb
Author: A. R. CauseyPublisher: Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories
ISBN: 9780660151892
Category : Nuclear reactors
Languages : en
Pages : 22
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.
Deformation equation for zr-2.5 nb pressure tubes under normal operating conditions in CANDU reactors
Author: N. ChristodoulouThe Transformation Behaviour of the Beta Phase in Zr-2.5 Wt% Nb Pressure Tubes
Author: M. GriffithsPublisher: Chalk River, Ont. : Chalf River Laboratories
ISBN: 9780660158976
Category : Alloys
Languages : en
Pages : 20
Book Description
Deformation of a CANDU-phw cold-drawn zr-2.5 wt% nb pressure tube in NRU.
Author: M. D. McmanusImproved Zr-2.5Nb Pressure Tubes for Reduced Diametral Strain in Advanced CANDU Reactors
Author: G. A. BickelPublisher:
ISBN:
Category : Crystallographic texture
Languages : en
Pages : 22
Book Description
In an Advanced CANDU Reactor (ACR) (ACR is a registered trademark of Atomic Energy of Canada Limited), pressure tubes of cold-worked Zr-2.5Nb materials will be used in the reactor core to contain the fuel bundles and the light water coolant. They will be subjected to higher temperature, pressure, and flux than those in a CANDU (CANDU is a registered trademark of Atomic Energy of Canada Limited) reactor, and accordingly require a thicker wall (6.5 mm for ACR versus 4.2 mm for CANDU). In order to ensure that these tubes will perform acceptably over their 30-year design life in such an environment, a study to model and forecast the performance of these thicker pressure tubes has been undertaken. One of the main requirements for the pressure tube is to have low diametral creep. Based on previous experience with CANDU reactor pressure tube performance and manufacture, an assessment of the grain structure and texture of the ACR pressure tubes indicates that the in-reactor creep deformation will be improved. Analysis of the distribution of texture parameters from a trial batch of 26 tubes shows that the variability is reduced relative to tubes fabricated in the past. This reduction in variability together with a shift to a coarser grain structure will result in a reduction in diametral creep design limits and thus a longer economic life for the fuel channels of the advanced CANDU reactor.
Author: E. T. C. Ho
Author: M. Griffiths