Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr

Perrin, Alice; Hamaguchi, Dai; Geringer, Josina W.; Zinkle, Steven J.; Yang, Ying; Skutnik, Steve; Poplawsky, Jonathan D.; Katoh, Yutai

doi:10.3389/fnuen.2024.1486694

Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr

Journal Article · Tue Nov 12 00:00:00 EST 2024 · Frontiers in Nuclear Engineering

DOI:https://doi.org/10.3389/fnuen.2024.1486694· OSTI ID:2477074

^[1]; Hamaguchi, Dai ^[2]; Geringer, Josina W. ^[1]; Zinkle, Steven J. ^[3]; ^[1]; ^[1]; ^[1]; ^[1]

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Rokkasho Fusion Institute (Japan)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)

High strength, high conductivity copper alloys that can resist creep at high temperatures are one of the primary candidates for efficient heat exchangers in fusion reactors. Cu–Cr–Nb–Zr (CCNZ) alloys, which were designed to improve the strength and creep life of ITER Cu–Cr–Zr (CCZ) reference alloys, have been found to have comparable electrical conductivity and tensile properties to CCZ alloys. The measured creep rupture times for these improved alloys is about ten times higher than the ITER reference alloys at 90–125 MPa at 500 °C. However, the effects of neutron irradiation on these alloys, and the ensuing material properties, have not been studied; thus, their utility in a fusion reactor environment is not well understood. This study characterizes the room temperature mechanical and electrical properties of a neutron-irradiated CCNZ alloy and compares them to a neutron-irradiated ITER reference heat sink CCZ alloy. Tensile specimens were neutron irradiated in the High Flux Isotope Reactor (HFIR) to 5 dpa between 250 °C and 325 °C. Post-irradiation characterization included electrical resistivity measurements, hardness, and tensile tests. Microstructural evaluation used scanning electron microscopy, energy dispersive x-ray spectroscopy, and atom probe tomography to characterize the irradiation-produced changes in the microstructure and investigate the mechanistic processes leading to post-irradiation properties. Transmutation calculations were validated with composition measurements from atom probe data and used to calculate contributions to the increased electrical resistivity measured after irradiation. Comparisons with CCZ alloys in the same irradiation heat found that the post-irradiated CCNZ and CCZ alloys had comparable electrical resistivity. Although CCNZ alloys suffered more irradiation hardening than CCZ, the overall tensile behavior deviated very little from non-irradiated values in the temperature range studied.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Laboratory Directed Research and Development (LDRD) Program

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 2477074

Alternate ID(s):: OSTI ID: 2477512

Journal Information:: Frontiers in Nuclear Engineering, Vol. 3; ISSN 2813-3412

Publisher:: Frontiers Media S.A.Copyright Statement

Country of Publication:: United States

Language:: English

References (46)

Comparison of GRCop-84 to Other Cu Alloys with High Thermal Conductivities de Groh, Henry C.; Ellis, David L.; Loewenthal, William S. Journal of Materials Engineering and Performance, Vol. 17, Issue 4 https://doi.org/10.1007/s11665-007-9175-3	journal	August 2008
Assessment of creep in reactor-irradiated CuCrZr alloy intended for the ITER first wall panels Gusarov, Andrei; Pohl, Christoph; Pfalz, Torsten Fusion Engineering and Design, Vol. 137 https://doi.org/10.1016/j.fusengdes.2018.09.001	journal	December 2018
Operating temperature windows for fusion reactor structural materials Zinkle, S. J.; Ghoniem, N. M. Fusion Engineering and Design, Vol. 51-52, p. 55-71 https://doi.org/10.1016/S0920-3796(00)00320-3	journal	November 2000
Tailoring microstructure in sintered Cu-Cr-Nb-Zr alloys for fusion components Cheng, Bin; Wang, Ling; Sprouster, David J. Journal of Nuclear Materials, Vol. 551 https://doi.org/10.1016/j.jnucmat.2021.152956	journal	August 2021
Degradation of electrical resistivity of tungsten following shielded neutron irradiation Echols, J. R.; Garrison, L. M.; Reid, N. Acta Materialia, Vol. 257 https://doi.org/10.1016/j.actamat.2023.119025	journal	June 2023
Damage saturation effects on volume and resistivity changes induced by fission-fragment irradiation of copper Birtcher, R. C.; Blewitt, T. H. Journal of Nuclear Materials, Vol. 98, Issue 1-2 https://doi.org/10.1016/0022-3115(81)90387-1	journal	May 1981
Evaluation of high strength, high conductivity CuNiBe alloys for fusion energy applications Zinkle, S. J. Journal of Nuclear Materials, Vol. 449, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.007	journal	June 2014
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature Campbell, Anne A.; Porter, Wallace D.; Katoh, Yutai Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 370 https://doi.org/10.1016/j.nimb.2016.01.005	journal	March 2016
Effect of high doses of neutron irradiation on physico-mechanical properties of copper alloys for ITER applications Fabritsiev, S. A.; Pokrovsky, A. S. Fusion Engineering and Design, Vol. 73, Issue 1 https://doi.org/10.1016/j.fusengdes.2004.12.003	journal	April 2005
Critical thermodynamic evaluation and optimization of the Ag–Zr, Cu–Zr and Ag–Cu–Zr systems and its applications to amorphous Cu–Zr–Ag alloys Kang, Dae Hoon; Jung, In-Ho Intermetallics, Vol. 18, Issue 5 https://doi.org/10.1016/j.intermet.2009.12.013	journal	May 2010
DEMO physics challenges beyond ITER Siccinio, M.; Biel, W.; Cavedon, M. Fusion Engineering and Design, Vol. 156 https://doi.org/10.1016/j.fusengdes.2020.111603	journal	July 2020
Development of a Flexible Design for Irradiation of Miniature Tensile and Charpy Test Specimens in the High Flux Isotope Reactor Howard, Richard H.; Smith, Kurt R. https://doi.org/10.2172/1460197	report	July 2018
Improvement in strength and thermal conductivity of powder metallurgy produced Cu–Ni–Si–Cr alloy by adjusting Ni/Si weight ratio and hot forging Wang, Huei-Sen; Chen, Hou-Guang; Gu, Jhen-Wang Journal of Alloys and Compounds, Vol. 633 https://doi.org/10.1016/j.jallcom.2015.02.024	journal	June 2015
The influence of transmutation, void swelling, and flux/spectra uncertainties on the electrical properties of copper and copper alloys Edwards, D. J.; Garner, F. A.; Greenwood, L. R. Journal of Nuclear Materials, Vol. 212-215 https://doi.org/10.1016/0022-3115(94)90094-9	journal	September 1994
Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors Asakura, N.; Hoshino, K.; Kakudate, S. Nuclear Materials and Energy, Vol. 35 https://doi.org/10.1016/j.nme.2023.101446	journal	June 2023
Copper and Copper Alloys Davis, J. R. Alloying: Understanding the Basics https://doi.org/10.31399/asm.tb.aub.t61170457	book	January 2001
The stability of precipitates in an irradiation environment Nelson, R. S.; Hudson, J. A.; Mazey, D. J. Journal of Nuclear Materials, Vol. 44, Issue 3 https://doi.org/10.1016/0022-3115(72)90043-8	journal	September 1972
Properties of copper and copper alloys at cryogenic temperatures Simon, N. J.; Drexler, E. S.; Reed, R. P. https://doi.org/10.6028/NIST.MONO.177	report	February 1992
High-Performance dispersion-strengthened Cu-8 Cr-4 Nb alloy Anderson, Ken R.; Groza, Joanna R.; Dreshfield, Robert L. Metallurgical and Materials Transactions A, Vol. 26, Issue 9 https://doi.org/10.1007/BF02671235	journal	September 1995
Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determination Field, Kevin G.; McDuffee, Joel L.; Geringer, Josina W. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 445 https://doi.org/10.1016/j.nimb.2019.02.022	journal	April 2019
Effect of fast-neutron irradiation on tensile properties of precipitation-hardened Cu-Cr-Zr alloy Fenici, P.; Boerman, D. J.; Tartaglia, G. P. Journal of Nuclear Materials, Vol. 212-215 https://doi.org/10.1016/0022-3115(94)90093-0	journal	September 1994
The effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys Kalinin, G. M.; Artyugin, A. S.; Yvseev, M. V. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.02.036	journal	October 2011
Al-Cu-Ce(-Zr) alloys with an exceptional combination of additive processability and mechanical properties Bahl, Sumit; Sisco, Kevin; Yang, Ying Additive Manufacturing, Vol. 48 https://doi.org/10.1016/j.addma.2021.102404	journal	December 2021
Effect of the irradiation–annealing–irradiation cycle on the mechanical properties of pure copper and copper alloy Fabritsiev, S. A.; Pokrovsky, A. S.; Ostrovsky, S. E. Journal of Nuclear Materials, Vol. 324, Issue 1 https://doi.org/10.1016/j.jnucmat.2003.09.004	journal	January 2004
Effects of heat treatments and neutron irradiation on microstructures and physical and mechanical properties of copper alloys Singh, B. N.; Edwards, D. J.; Eldrup, M. Journal of Nuclear Materials, Vol. 249, Issue 1 https://doi.org/10.1016/S0022-3115(97)00184-0	journal	September 1997
SCALE 6.3.1 User Manual Wieselquist, William; Lefebvre, Robert https://doi.org/10.2172/1959594	report	February 2023
High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign You, J. H.; Visca, E.; Barrett, T. Journal of Nuclear Materials, Vol. 544 https://doi.org/10.1016/j.jnucmat.2020.152670	journal	February 2021
Materials challenges for ITER – Current status and future activities Barabash, V.; Peacock, A.; Fabritsiev, S. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.017	journal	August 2007
The effect of neutron irradiation on the electrical resistivity of high-strength copper alloys Fabritsiev, S. A.; Pokrovsky, A. S. Journal of Nuclear Materials, Vol. 249, Issue 2-3 https://doi.org/10.1016/S0022-3115(97)00144-X	journal	October 1997
Effect of irradiation temperature on microstructure, radiation hardening and embrittlement of pure copper and copper-based alloy Fabritsiev, S. A.; Pokrovsky, A. S. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.056	journal	August 2007
Modified Matthiessen's rule: More scattering leads to less resistance Žnidarič, Marko Physical Review B, Vol. 105, Issue 4 https://doi.org/10.1103/PhysRevB.105.045140	journal	January 2022
Evaluation of copper alloys for fusion reactor divertor and first wall components Fabritsiev, S. A.; Zinkle, S. J.; Singh, B. N. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00091-8	journal	October 1996
Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects Barabash, V. R.; Kalinin, G. M.; Fabritsiev, S. A. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.158	journal	October 2011
High Flux Isotope Reactor Neutron Spectrum Shape Estimation From Activation Experiment Data Skutnik, Steven E.; Stanford, Austin C. IEEE Transactions on Nuclear Science, Vol. 70, Issue 1 https://doi.org/10.1109/TNS.2022.3226870	journal	January 2023
Porosity swelling and transmutation contributions to conductivity changes in some neutron-irradiated copper alloys Frost, H. M.; Kennedy, J. C. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/S0022-3115(86)80030-7	journal	November 1986
Defects and transmutations in reactor-irradiated copper Chaplin, R. L.; Coltman, R. R. Journal of Nuclear Materials, Vol. 108-109 https://doi.org/10.1016/0022-3115(82)90485-8	journal	July 1982
Copper matrix composites as heat sink materials for water-cooled divertor target You, Jeong-Ha Nuclear Materials and Energy, Vol. 5 https://doi.org/10.1016/j.nme.2015.10.001	journal	December 2015
Effect of heavy ion irradiation dose rate and temperature on α′ precipitation in high purity Fe-18%Cr alloy Zhao, Yajie; Bhattacharya, Arunodaya; Pareige, Cristelle Acta Materialia, Vol. 231 https://doi.org/10.1016/j.actamat.2022.117888	journal	June 2022
Contrasting roles of Laves_Cr2Nb precipitates on the creep properties of novel CuCrNbZr alloys Wang, Ling; Zheng, Ce; Kombaiah, Boopathy Materials Science and Engineering: A, Vol. 779 https://doi.org/10.1016/j.msea.2020.139110	journal	March 2020
Effect of neutron irradiation on tensile properties of advanced Cu-based alloys and composites developed for fusion applications Terentyev, Dmitry; Rieth, Michael; Pintsuk, Gerald Journal of Nuclear Materials, Vol. 584 https://doi.org/10.1016/j.jnucmat.2023.154587	journal	October 2023
Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy Edwards, D. J.; Singh, B. N.; Tähtinen, S. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.064	journal	August 2007
Hot Deformation Behavior and Processing Map of Cu-Cr-Nb-Zr Alloy Krishna, S. Chenna; Muneshwar, Pravin; Pant, Bhanu Journal of Materials Engineering and Performance, Vol. 31, Issue 2 https://doi.org/10.1007/s11665-021-06268-0	journal	September 2021
Long-term radioactivity in fusion reactors Fetter, Steve; Cheng, E. T.; Mann, F. M. Fusion Engineering and Design, Vol. 6 https://doi.org/10.1016/S0920-3796(88)80098-X	journal	January 1988
Effect of neutron dose and spectra, He/dpa ratio and Ni and Zn accumulation on irradiation damage of pure copper and PH and DS copper alloys Fabritsiev, S. A.; Pokrovsky, A. S.; Zinkle, S. J. Fusion Engineering and Design, Vol. 38, Issue 4 https://doi.org/10.1016/S0920-3796(98)00106-9	journal	February 1998
Development of novel Cu-Cr-Nb-Zr alloys with the aid of computational thermodynamics Yang, Ying; Wang, Ling; Snead, Lance Materials & Design, Vol. 156 https://doi.org/10.1016/j.matdes.2018.07.003	journal	October 2018
Applicability of copper alloys for DEMO high heat flux components Zinkle, Steven J. Physica Scripta, Vol. T167 https://doi.org/10.1088/0031-8949/2015/T167/014004	journal	December 2015

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