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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 {approx}80 C to two fluences, 2 x 10{sup 24} and 2 x 10{sup 25} n/m{sup 2} (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 {approx}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{sub Q} > 200 kJ/m{sup 2}) for both heat treatment conditions.

Authors:
 [1];  [1];  [2]
  1. ORNL
  2. Argonne National Laboratory (ANL)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); High Flux Isotope Reactor
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
979117
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 393; Journal Issue: 1
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; ALLOYS; ATOMS; DIVERTORS; FRACTURE PROPERTIES; HARDENING; HEAT TREATMENTS; INSTABILITY; IRRADIATION; MANUFACTURING; NEUTRONS; PLASTICS; SATURATION; WATER

Citation Formats

Sokolov, Mikhail A, Zinkle, Steven J, and Li, Meimei. Tensile and Fracture Toughness Properties of Neutron-Irradiated CuCrZr. United States: N. p., 2009. Web.
Sokolov, Mikhail A, Zinkle, Steven J, & Li, Meimei. Tensile and Fracture Toughness Properties of Neutron-Irradiated CuCrZr. United States.
Sokolov, Mikhail A, Zinkle, Steven J, and Li, Meimei. Thu . "Tensile and Fracture Toughness Properties of Neutron-Irradiated CuCrZr". United States. doi:.
@article{osti_979117,
title = {Tensile and Fracture Toughness Properties of Neutron-Irradiated CuCrZr},
author = {Sokolov, Mikhail A and Zinkle, Steven J and Li, Meimei},
abstractNote = {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 {approx}80 C to two fluences, 2 x 10{sup 24} and 2 x 10{sup 25} n/m{sup 2} (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 {approx}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{sub Q} > 200 kJ/m{sup 2}) for both heat treatment conditions.},
doi = {},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 393,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 2009},
month = {Thu Jan 01 00:00:00 EST 2009}
}