Author: N. ChristodoulouPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Deformation equation for zr-2.5 nb pressure tubes under normal operating conditions in CANDU reactors
Author: N. ChristodoulouModelling in-reactor deformation of zr-2.5nb pressure tubes in CANDU power reactors
Author: N. ChristodoulouPublisher:
ISBN:
Category :
Languages : en
Pages : 0
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-2.5nb pressure tubes in canada deuterium uranium-pressurized heavy water (candu-phw) power reactors and test reactors have been monitored periodically over the past 20 years. axial and transverse strain rates have been evaluated in terms of operating variables and the crystallographic texture and anisotropic microstructure of the extruded and cold-drawn tubes. the anisotropic deformation occurring during irradiation creep and growth is described by a self-consistent model that takes into account the presence of intergranular stresses without building up any discontinuities of strain and stress at the grain boundaries. in this model it is assumed that climb assisted glide of dislocations on prismatic, basal and pyramidal planes is the dominant creep mode and that growth occurs by net fluxes of interstitials and vacancies to a non random distribution of dislocations and grain boundaries. the predictions from a deformation equation based on data from the pickering, and point lepreau nuclear generating stations and the wr1, osiris, dido and nru test reactors are in good agreement with measurements of pressure tubes in bruce units. the equation has been employed as a material subroutine in the 3-d finite element code h3dmap for predicting the detailed shape change of pressure tubes. the prediction from h3dmap is a more complete description of shape change than that obtained from the closed-form expression.
Modeling In-Reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors
Author: N. BadiePublisher:
ISBN:
Category : Congress
Languages : en
Pages : 20
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-2.5Nb pressure tubes in CANada Deuterium Uranium-Pressurized Heavy Water (CANDU-PHW) power reactors and test reactors have been monitored periodically over the past 20 years. Axial and transverse strain rates have been evaluated in terms of operating variables and the crystallographic texture and anisotropic microstructure of the extruded and cold-drawn tubes. The anisotropic deformation occurring during steady-state irradiation creep and growth is described by a self-consistent model that takes into account the presence of intergranular stresses without building up any discontinuities of strain and stress at the grain boundaries. In this model, it is assumed that climb-assisted glide of dislocations on prismatic, basal, and pyramidal planes is the dominant creep mode and that growth occurs by net fluxes of interstitials and vacancies to a non-random distribution of dislocations and grain boundaries. The predictions from a deformation equation based on data from the Pickering and Point Lepreau Nuclear Generating Stations and the WR1, Osiris, DIDO, and NRU test reactors are in good agreement with measurements of pressure tubes in Bruce units. The equation has been employed as a material subroutine in the 3-D finite element code H3DMAP for predicting the detailed shape change of pressure tubes. The prediction from H3DMAP is a more complete description of shape change than that obtained from the closed-form expression.
In-Reactor Deformation of Zr-2.5 Wt% Nb Pressure Tubes
Author: AR. CauseyPublisher:
ISBN:
Category : Deformation
Languages : en
Pages : 15
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.
Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor
Author: E. F. IbrahimSingle-crystal irradiation deformation modelling for zr-2.5nb pressure tubes in CANDU reactors
Author: M. GriffithsAn assessment of the design equation for predicting the in-reactor deformation of zr-2.5 wt percent nb pressure tubes
Author: J. VeederCycling and inspection of the flaw in pressure tube b1-l08
Author: K. R. ChaplinPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This document consists of candu zr-2.5nb pressure tube inspection and operating data primarily for ontario hydro reactors. the data presented here represent the current contents of the in-reactor deformation database developed and maintained at ohrd/1/. it is intended for use in the understanding of the deformation behaviour of fuel channels in power reactors and in the derivation and fine-tuning of material creep and growth constants for the new deformation equations. in compiling and presenting the deformation and operating data of fuel channels the databse provides a statistical sample of the actual operating behaviour of components in candu power reactors. this sample may be used to detect any abnormal or unexpected effects and to provide a means of comparison between different power reactos. with the future addition of 600 mw and experimental reactor data, this information will play a key role in the development of a broader understanding of fuel channel behaviour in the ongoing process of extending the operating lives of candu reactors. this document represents the first issue of the information in the database in a 3-ring binder format. it is felt that this format will avoid the need to re-issue the entire document when new information becomes available. it will be the responsibility of ohrd to provide updates on a regular basis (most likely annually). the information is divided into three sections: the first section contains diametral expansion inspection data for individual fuel channels, the second contains the sag inspection data, and the third contains the reactor operating data. within each section are three subsections: a legend describing the tables, information on the source and processing of the data in the tables, and the tables of the data.
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.
Author: R. S. W. Shewfelt