Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor

Ken R. Anderson (Corresponding Author), Wade Karlsen, Mykola Ivanchenko, Jesse J. Carter, Richard W. Smith

Research output: Contribution to journalArticleResearchpeer-review

Abstract

Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth.

Original languageEnglish
Pages (from-to)260-270
Number of pages11
JournalJournal of Nuclear Materials
Volume513
DOIs
Publication statusPublished - Jan 2019
MoE publication typeNot Eligible

Fingerprint

Zircaloy 2 (trademark)
Creep testing
zirconium alloys
Zirconium alloys
piles
Piles
examination
reactors
Irradiation
hardening
irradiation
Hardening
high flux isotope reactors
creep strength
Defects
Neutron flux
defects
flux (rate)
sinks
Creep

Keywords

  • In-pile creep
  • Microstructure
  • Neutron-irradiated
  • Rate-theory
  • Zircaloy-2

Cite this

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title = "Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor",
abstract = "Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1{\%} Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth.",
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Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor. / Anderson, Ken R. (Corresponding Author); Karlsen, Wade; Ivanchenko, Mykola; Carter, Jesse J.; Smith, Richard W.

In: Journal of Nuclear Materials, Vol. 513, 01.2019, p. 260-270.

Research output: Contribution to journalArticleResearchpeer-review

TY - JOUR

T1 - Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor

AU - Anderson, Ken R.

AU - Karlsen, Wade

AU - Ivanchenko, Mykola

AU - Carter, Jesse J.

AU - Smith, Richard W.

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AB - Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth.

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KW - Rate-theory

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