Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor

Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor PDF Author: E. F. Ibrahim
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Languages : en
Pages : 0

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Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor

Design equation for deformation of cold-worked zr-2.5 percent nb pressure tubes in-reactor PDF Author: E. F. Ibrahim
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Category :
Languages : en
Pages : 0

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An assessment of the design equation for predicting the in-reactor deformation of zr-2.5 wt percent nb pressure tubes

An assessment of the design equation for predicting the in-reactor deformation of zr-2.5 wt percent nb pressure tubes PDF Author: J. Veeder
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Category :
Languages : en
Pages : 0

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The Creep ductility in-reactor of cold worked zr-2.5 wt percent nb pressure tubes

The Creep ductility in-reactor of cold worked zr-2.5 wt percent nb pressure tubes PDF Author: C. E. Ells
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Category :
Languages : en
Pages : 0

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Modelling in-reactor deformation of zr-2.5nb pressure tubes in CANDU power reactors

Modelling in-reactor deformation of zr-2.5nb pressure tubes in CANDU power reactors PDF Author: N. Christodoulou
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Languages : en
Pages : 0

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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

Modeling In-Reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors PDF Author: N. Badie
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Category : Congress
Languages : en
Pages : 20

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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 tube

In-reactor deformation of zr-2.5 wt% nb pressure tube PDF Author: J. D. Parker
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Category :
Languages : en
Pages : 0

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Reactor Technology

Reactor Technology PDF Author:
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Category : Nuclear engineering
Languages : en
Pages : 876

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Power Reactor Technology and Reactor Fuel Processing

Power Reactor Technology and Reactor Fuel Processing PDF Author:
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Category : Nuclear engineering
Languages : en
Pages : 1110

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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Category : Nuclear energy
Languages : en
Pages : 516

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Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
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Category : Aeronautics
Languages : en
Pages : 1330

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