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A layman`s guide to radiation-induced deformation processes in zirconium alloys

Technical Report:

Abstract

The fuel channel (comprising a pressure tube and a calandria tube fabricated from zirconium alloys) in a CANDU reactor undergoes shape changes because of radiation-induced deformation. This is a consequence of the microstructural modification arising from radiation damage produced by the fast-neutron flux. This report summarizes our current understanding of the physical processes responsible for the deformation. With the non-specialist reader in mind, the underlying mechanisms are described in a manner that avoids much of the associated technical terminology. Thus, the basic concepts of plasticity in a crystalline material are introduced and related to the various microstructural defects created during irradiation. In particular, the mechanisms of creep (a time-dependent strain activated by an applied stress) and growth (a time-dependent strain occurring in the absence of stress) are discussed in a non-technical language assisted by simple diagrams. Reference is made to both theoretical investigations (avoiding mathematical complexity) and experimental measurements. It is shown how the qualitative and quantitative knowledge can be used to derive a predictive model for reactor designers and operators. The current status of such a model is evaluated and suggestions for future improvements made.
Authors:
Publication Date:
Jul 01, 1990
Product Type:
Technical Report
Report Number:
AECL-10158; COG-90-49.
Reference Number:
SCA: 210400; 360103; PA: AIX-23:005643; SN: 91000615932
Resource Relation:
Other Information: PBD: Jul 1990
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; ZIRCONIUM BASE ALLOYS; PHYSICAL RADIATION EFFECTS; CANDU TYPE REACTORS; DEFORMATION; DISLOCATIONS; EMBRITTLEMENT; FRACTURE PROPERTIES; FUEL CHANNELS; GRAIN BOUNDARIES; POINT DEFECTS; PRESSURE TUBES; STRAINS; 210400; 360103; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED; MECHANICAL PROPERTIES
OSTI ID:
10102473
Research Organizations:
Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE92611888; TRN: CA9111077005643
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
84 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Dutton, R. A layman`s guide to radiation-induced deformation processes in zirconium alloys. Canada: N. p., 1990. Web.
Dutton, R. A layman`s guide to radiation-induced deformation processes in zirconium alloys. Canada.
Dutton, R. 1990. "A layman`s guide to radiation-induced deformation processes in zirconium alloys." Canada.
@misc{etde_10102473,
title = {A layman`s guide to radiation-induced deformation processes in zirconium alloys}
author = {Dutton, R}
abstractNote = {The fuel channel (comprising a pressure tube and a calandria tube fabricated from zirconium alloys) in a CANDU reactor undergoes shape changes because of radiation-induced deformation. This is a consequence of the microstructural modification arising from radiation damage produced by the fast-neutron flux. This report summarizes our current understanding of the physical processes responsible for the deformation. With the non-specialist reader in mind, the underlying mechanisms are described in a manner that avoids much of the associated technical terminology. Thus, the basic concepts of plasticity in a crystalline material are introduced and related to the various microstructural defects created during irradiation. In particular, the mechanisms of creep (a time-dependent strain activated by an applied stress) and growth (a time-dependent strain occurring in the absence of stress) are discussed in a non-technical language assisted by simple diagrams. Reference is made to both theoretical investigations (avoiding mathematical complexity) and experimental measurements. It is shown how the qualitative and quantitative knowledge can be used to derive a predictive model for reactor designers and operators. The current status of such a model is evaluated and suggestions for future improvements made.}
place = {Canada}
year = {1990}
month = {Jul}
}