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A methodology to analyze the creep behaviour of nuclear fuel waste containers

Abstract

The concept for the disposal of used-fuel waste from CANDU reeactors operating in Canada comprises a system of natural and engineered barriers surrounding the waste in a mined vault situated at a depth of 500 - 1000 m in plutonic rock of the Canadian Shield. The fuel would be packaged in a highly durable metal container, within a matrix of compacted particulate. The design of the container takes into account that it would be subjected to an external hydrostatic pressure. Consideration of the rate of radioactive decay of the radionuclides contained in the fuel, suggests that the lifetime of the container should be at least 500 years. Consequently, the role of creep deformation, and the possibility of creep rupture of the container shell, must be included in the assessment of time-dependent mechanical integrity. This report describes an analytical approach that can be used to quantify the long-term creep properties of the container material and facilitate the engineering design. The overall objective is to formulate a constitutive creep equation that provides the required input for a finite element computer model being developed to analyze the elastic-plastic behaviour of the container. Alternative forms of such equations are reviewed. It is shown that  More>>
Authors:
Dutton, R [1] 
  1. Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.
Publication Date:
Dec 01, 1995
Product Type:
Technical Report
Report Number:
AECL-11249; COG-95-06.
Reference Number:
SCA: 360103; PA: AIX-27:064966; EDB-96:143599; NTS-97:001744; SN: 96001665430
Resource Relation:
Other Information: PBD: Dec 1995
Subject:
36 MATERIALS SCIENCE; CONTAINMENT SHELLS; CREEP; CANDU TYPE REACTORS; COPPER; RADIOACTIVE WASTE DISPOSAL; RADIOISOTOPES; SERVICE LIFE; SPENT FUELS; TITANIUM; UNDERGROUND DISPOSAL
OSTI ID:
368929
Research Organizations:
Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE97600112; TRN: CA9600668064966
Availability:
INIS; OSTI as DE97600112
Submitting Site:
INIS
Size:
106 p.
Announcement Date:
Oct 04, 1996

Citation Formats

Dutton, R. A methodology to analyze the creep behaviour of nuclear fuel waste containers. Canada: N. p., 1995. Web.
Dutton, R. A methodology to analyze the creep behaviour of nuclear fuel waste containers. Canada.
Dutton, R. 1995. "A methodology to analyze the creep behaviour of nuclear fuel waste containers." Canada.
@misc{etde_368929,
title = {A methodology to analyze the creep behaviour of nuclear fuel waste containers}
author = {Dutton, R}
abstractNote = {The concept for the disposal of used-fuel waste from CANDU reeactors operating in Canada comprises a system of natural and engineered barriers surrounding the waste in a mined vault situated at a depth of 500 - 1000 m in plutonic rock of the Canadian Shield. The fuel would be packaged in a highly durable metal container, within a matrix of compacted particulate. The design of the container takes into account that it would be subjected to an external hydrostatic pressure. Consideration of the rate of radioactive decay of the radionuclides contained in the fuel, suggests that the lifetime of the container should be at least 500 years. Consequently, the role of creep deformation, and the possibility of creep rupture of the container shell, must be included in the assessment of time-dependent mechanical integrity. This report describes an analytical approach that can be used to quantify the long-term creep properties of the container material and facilitate the engineering design. The overall objective is to formulate a constitutive creep equation that provides the required input for a finite element computer model being developed to analyze the elastic-plastic behaviour of the container. Alternative forms of such equations are reviewed. It is shown that the capability of many of these equations to extrapolate over long time scales is limited by their empirical nature. Thus, the recommended equation is based on current mechanistic understanding of creep deformation and creep rupture. A criterion for determining the onset of material failure by creep rupture, that could be used in the design of containers with extended structural integrity, is proposed. Interpretation and extrapolation will be supported by the complementary Deformation and Fracture Mechanism Maps. (author) 103 refs., 2 tabs., 54 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}