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Mitigation of degradation mechanisms affecting CANDU pressure tubes

Abstract

The Zr-2.5% Nb alloy pressure tube provides the primary containment for coolant in the CANDU reactor. Because these tubes contain the individual fuel strings and pass neutron flux of up to 4.0 x 10{sup 17} neutrons per square meter per second (E > 1 MeV). Any demonstration of the integrity of these tubes relies on a leak-before-break (LBB) assessment, which, in turn, depends on the fracture properties of the tube. These properties become degraded with service due to both the gradual pickup of hydrogen isotopes and the reduction of fracture toughness due to irradiation. This paper gives an overview of the relevant fracture properties used in the LBB scenario and the effect of service conditions on their degradation. The particular properties discussed are the susceptability to subcritical crack growth by delayed hydride cracking, and the reduction in fracture toughness which reduces the critical crack length. Methods of protecting the tubes against fracture and improving their properties are discussed.
Authors:
Simpson, L A; [1]  Coleman, C E [2] 
  1. Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
  2. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.
Publication Date:
Dec 01, 1990
Product Type:
Conference
Report Number:
AECL-10325; CONF-9010488-
Reference Number:
SCA: 210400; PA: AIX-23:036830; SN: 92000726196
Resource Relation:
Conference: 16. MPA-seminar,Pinawa (Canada),4-5 Oct 1990; Other Information: PBD: Dec 1990
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CANDU TYPE REACTORS; PRESSURE TUBES; FRACTURE PROPERTIES; CRACK PROPAGATION; CRACKS; ZIRCALOY; 210400; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED
OSTI ID:
10140409
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: DE92626943; TRN: CA9200232036830
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
25 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Simpson, L A, and Coleman, C E. Mitigation of degradation mechanisms affecting CANDU pressure tubes. Canada: N. p., 1990. Web.
Simpson, L A, & Coleman, C E. Mitigation of degradation mechanisms affecting CANDU pressure tubes. Canada.
Simpson, L A, and Coleman, C E. 1990. "Mitigation of degradation mechanisms affecting CANDU pressure tubes." Canada.
@misc{etde_10140409,
title = {Mitigation of degradation mechanisms affecting CANDU pressure tubes}
author = {Simpson, L A, and Coleman, C E}
abstractNote = {The Zr-2.5% Nb alloy pressure tube provides the primary containment for coolant in the CANDU reactor. Because these tubes contain the individual fuel strings and pass neutron flux of up to 4.0 x 10{sup 17} neutrons per square meter per second (E > 1 MeV). Any demonstration of the integrity of these tubes relies on a leak-before-break (LBB) assessment, which, in turn, depends on the fracture properties of the tube. These properties become degraded with service due to both the gradual pickup of hydrogen isotopes and the reduction of fracture toughness due to irradiation. This paper gives an overview of the relevant fracture properties used in the LBB scenario and the effect of service conditions on their degradation. The particular properties discussed are the susceptability to subcritical crack growth by delayed hydride cracking, and the reduction in fracture toughness which reduces the critical crack length. Methods of protecting the tubes against fracture and improving their properties are discussed.}
place = {Canada}
year = {1990}
month = {Dec}
}