Tensile and fracture toughness properties of neutron-irradiated CuCrZr

Meimei Li; M. A. Sokolov; S. J. Zinkle

doi:10.1016/j.jnucmat.2009.05.003

Tensile and fracture toughness properties of neutron-irradiated CuCrZr

Meimei Li, M. A. Sokolov, S. J. Zinkle

Advanced Nuclear Materials

Research output: Contribution to journal › Article › peer-review

41 Scopus citations

Abstract

Tensile and fracture toughness properties of a precipitation-hardened CuCrZr alloy were investigated in two heat treatment conditions: solutionized, water quenched and aged (CuCrZr SAA), and hot isostatic pressed, solutionized, slow-cooled and aged (CuCrZr SCA). The second heat treatment simulated the manufacturing cycle for large components, and is directly relevant for the ITER divertor components. Specimens were neutron irradiated at ∼80 °C to two fluences, 2 × 10²⁴ and 2 × 10²⁵ n/m² (E > 0.1 MeV), corresponding to displacement doses of 0.15 and 1.5 displacements per atom (dpa). Tensile and fracture toughness tests were carried out at room temperature. Significant irradiation hardening and plastic instability at yield occurred in both heat treatment conditions with a saturation dose of ∼0.1 dpa. Neutron irradiation slightly reduced fracture toughness in CuCrZr SAA and CuCrZr SCA. The fracture toughness of CuCrZr remained high up to 1.5 dpa (J_Q > 200 kJ/m²) for both heat treatment conditions.

Original language	English
Pages (from-to)	36-46
Number of pages	11
Journal	Journal of Nuclear Materials
Volume	393
Issue number	1
DOIs	https://doi.org/10.1016/j.jnucmat.2009.05.003
State	Published - Aug 15 2009

Funding

The research was sponsored by the Office of Fusion Energy Sciences, the US Department of Energy under Contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed and operated by UT-Battelle, LLC. Dr Alan Peacock at EFDA Close Support Unit in Garching, Germany provided the materials. The authors would like to thank E.T. Manneschmidt, R. Swain and D.A. McClintock and L.T. Gibson for their technical support.

Funders	Funder number
U.S. Department of Energy	DE-AC05-00OR22725
Fusion Energy Sciences
Oak Ridge National Laboratory

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title = "Tensile and fracture toughness properties of neutron-irradiated CuCrZr",

abstract = "Tensile and fracture toughness properties of a precipitation-hardened CuCrZr alloy were investigated in two heat treatment conditions: solutionized, water quenched and aged (CuCrZr SAA), and hot isostatic pressed, solutionized, slow-cooled and aged (CuCrZr SCA). The second heat treatment simulated the manufacturing cycle for large components, and is directly relevant for the ITER divertor components. Specimens were neutron irradiated at ∼80 °C to two fluences, 2 × 1024 and 2 × 1025 n/m2 (E > 0.1 MeV), corresponding to displacement doses of 0.15 and 1.5 displacements per atom (dpa). Tensile and fracture toughness tests were carried out at room temperature. Significant irradiation hardening and plastic instability at yield occurred in both heat treatment conditions with a saturation dose of ∼0.1 dpa. Neutron irradiation slightly reduced fracture toughness in CuCrZr SAA and CuCrZr SCA. The fracture toughness of CuCrZr remained high up to 1.5 dpa (JQ > 200 kJ/m2) for both heat treatment conditions.",

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AU - Sokolov, M. A.

AU - Zinkle, S. J.

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N2 - Tensile and fracture toughness properties of a precipitation-hardened CuCrZr alloy were investigated in two heat treatment conditions: solutionized, water quenched and aged (CuCrZr SAA), and hot isostatic pressed, solutionized, slow-cooled and aged (CuCrZr SCA). The second heat treatment simulated the manufacturing cycle for large components, and is directly relevant for the ITER divertor components. Specimens were neutron irradiated at ∼80 °C to two fluences, 2 × 1024 and 2 × 1025 n/m2 (E > 0.1 MeV), corresponding to displacement doses of 0.15 and 1.5 displacements per atom (dpa). Tensile and fracture toughness tests were carried out at room temperature. Significant irradiation hardening and plastic instability at yield occurred in both heat treatment conditions with a saturation dose of ∼0.1 dpa. Neutron irradiation slightly reduced fracture toughness in CuCrZr SAA and CuCrZr SCA. The fracture toughness of CuCrZr remained high up to 1.5 dpa (JQ > 200 kJ/m2) for both heat treatment conditions.

AB - Tensile and fracture toughness properties of a precipitation-hardened CuCrZr alloy were investigated in two heat treatment conditions: solutionized, water quenched and aged (CuCrZr SAA), and hot isostatic pressed, solutionized, slow-cooled and aged (CuCrZr SCA). The second heat treatment simulated the manufacturing cycle for large components, and is directly relevant for the ITER divertor components. Specimens were neutron irradiated at ∼80 °C to two fluences, 2 × 1024 and 2 × 1025 n/m2 (E > 0.1 MeV), corresponding to displacement doses of 0.15 and 1.5 displacements per atom (dpa). Tensile and fracture toughness tests were carried out at room temperature. Significant irradiation hardening and plastic instability at yield occurred in both heat treatment conditions with a saturation dose of ∼0.1 dpa. Neutron irradiation slightly reduced fracture toughness in CuCrZr SAA and CuCrZr SCA. The fracture toughness of CuCrZr remained high up to 1.5 dpa (JQ > 200 kJ/m2) for both heat treatment conditions.

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Tensile and fracture toughness properties of neutron-irradiated CuCrZr

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