Author: C. N. TomePublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Analysis of accelerated irradiation growth in zr-2.5%nb pressure tubes
Author: C. N. TomeVariability of irradiation growth in zr-2.5nb pressure tubes
Author: R. G. FleckThe Contribution of Irradiation Growth to Pressure Tube Deformation
Author: RG. FleckPublisher:
ISBN:
Category : Elongation
Languages : en
Pages : 12
Book Description
Up-to-date growth results on Zr-2.5Nb pressure tube material from the DIDO reactor at AERE Harwell are presented. The observed temperature dependence and magnitude of growth are significantly different from the representations in a recently published model for in-reactor deformation of pressure tubes. These differences are discussed in terms of (1) the effects of stress on growth, (2) the comparability of test reactor and power reactor conditions, and (3) the relative contributions of creep and growth to pressure tube elongation.
The contribution of irradiation growth to pressure tube deformation
Author: R. A. HoltIrradiation growth of pressure tube material in the dido reactor
Author: R. G. FleckAn investigation into the effect of irradiation damage in zr-2.5 wt percent nb pressure tubes on the velocity of ultrasound
Author: J. J. SchankulaResults from the post-irradiation examination of zr-2.5nb pressure tube materials from loop 14 at the oecd halden reactor - coupons removed after the 1st cycle
Author: I. J. MuirWarm prestressing of irradiated zr-2.5nb pressure tubes
Author: D. D. HimbeaultEffect of prior irradiation on the stress relaxation of zr-2.5nb pressure tube material at 250 degrees celsius
Author: R. J. KlassenModelling 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.