Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy

D. J. Edwards (Corresponding Author), B. N. Singh, Seppo Tähtinen

Research output: Contribution to journalArticleScientificpeer-review

45 Citations (Scopus)

Abstract

The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.
Original languageEnglish
Pages (from-to)904-909
JournalJournal of Nuclear Materials
Volume367-370
Issue numberPart. B
DOIs
Publication statusPublished - 2007
MoE publication typeA1 Journal article-refereed

Fingerprint

fracture strength
Fracture toughness
Precipitates
precipitates
heat treatment
Heat treatment
mechanical properties
toughness
Mechanical properties
microstructure
Microstructure
Belgium
plastic flow
ductility
Plastic flow
set theory
fission
Ductility
Neutrons
plastics

Keywords

  • CuCrZr alloy
  • copper
  • chromium
  • zirconium
  • zirconium alloys
  • heat treatment

Cite this

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abstract = "The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.",
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Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy. / Edwards, D. J. (Corresponding Author); Singh, B. N.; Tähtinen, Seppo.

In: Journal of Nuclear Materials, Vol. 367-370 , No. Part. B, 2007, p. 904-909.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy

AU - Edwards, D. J.

AU - Singh, B. N.

AU - Tähtinen, Seppo

PY - 2007

Y1 - 2007

N2 - The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.

AB - The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.

KW - CuCrZr alloy

KW - copper

KW - chromium

KW - zirconium

KW - zirconium alloys

KW - heat treatment

U2 - 10.1016/j.jnucmat.2007.03.064

DO - 10.1016/j.jnucmat.2007.03.064

M3 - Article

VL - 367-370

SP - 904

EP - 909

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

IS - Part. B

ER -