Irradiation effects in tungsten-copper laminate composite

Garrison, L. M.; Katoh, Yutai; Snead, Lance L.; Byun, Thak Sang; Reiser, Jens; Rieth, Michael

doi:10.1016/j.jnucmat.2016.09.020

Title: Irradiation effects in tungsten-copper laminate composite

Journal Article · Mon Sep 19 00:00:00 EDT 2016 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2016.09.020· OSTI ID:1326484

Garrison, L. M. ^[1]; Katoh, Yutai ^[1]; Snead, Lance L. ^[2]; Byun, Thak Sang ^[3]; Reiser, Jens ^[4];

^[4]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Karlsruhe Institute of Technology, Karlsruhe (Germany)

Tungsten-copper laminate composite has shown promise as a structural plasma-facing component as compared to tungsten rod or plate. The present study evaluated the tungsten-copper composite after irradiation in the High Flux Isotope Reactor (HFIR) at temperatures of 410–780 °C and fast neutron fluences of 0.02–9.0 × 10²⁵ n/m², E > 0.1 MeV, 0.0039–1.76 displacements per atom (dpa) in tungsten. Tensile tests were performed on the composites, and the fracture surfaces were analyzed with scanning electron microscopy. Before irradiation, the tungsten layers had brittle cleavage failure, but the overall composite had 15.5% elongation at 22 °C. After only 0.0039 dpa this was reduced to 7.7% elongation, and no ductility was observed after 0.2 dpa at all irradiation temperatures when tensile tested at 22 °C. In conclusion, tor elevated temperature tensile tests after irradiation, the composite only had ductile failure at temperatures where the tungsten was delaminating or ductile.

View Accepted Manuscript (DOE)

View Accepted Manuscript (Publisher)

Cite

Export

Save

Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1326484

Alternate ID(s):: OSTI ID: 1396813

Journal Information:: Journal of Nuclear Materials, Vol. 481, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 21 works

Citation information provided by
Web of Science

References (35)

Recent progress in research on tungsten materials for nuclear fusion applications in Europe Rieth, M.; Dudarev, S. L.; Gonzalez de Vicente, S. M. Journal of Nuclear Materials, Vol. 432, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.08.018	journal	January 2013
Tungsten foil laminate for structural divertor applications – Basics and outlook Reiser, Jens; Rieth, Michael; Dafferner, Bernhard Journal of Nuclear Materials, Vol. 423, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.01.010	journal	April 2012
Tungsten foil laminate for structural divertor applications – Tensile test properties of tungsten foil Reiser, Jens; Rieth, Michael; Möslang, Anton Journal of Nuclear Materials, Vol. 434, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.12.003	journal	March 2013
Tungsten foil laminate for structural divertor applications – Analyses and characterisation of tungsten foil Reiser, Jens; Rieth, Michael; Dafferner, Bernhard Journal of Nuclear Materials, Vol. 424, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.02.030	journal	May 2012
Ductilisation of tungsten (W): On the shift of the brittle-to-ductile transition (BDT) to lower temperatures through cold rolling Reiser, Jens; Hoffmann, Jan; Jäntsch, Ute International Journal of Refractory Metals and Hard Materials, Vol. 54 https://doi.org/10.1016/j.ijrmhm.2015.09.001	journal	January 2016
Tungsten foil laminate for structural divertor applications – Joining of tungsten foils Reiser, Jens; Rieth, Michael; Möslang, Anton Journal of Nuclear Materials, Vol. 436, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.295	journal	May 2013
Crack deflection in tungsten carbide based laminates Watts, Jeremy; Hilmas, Greg International Journal of Refractory Metals and Hard Materials, Vol. 24, Issue 3 https://doi.org/10.1016/j.ijrmhm.2005.04.005	journal	May 2006
Effect of dislocation density on improved radiation hardening resistance of nano-structured tungsten–rhenium Armstrong, David E. J.; Britton, T. B. Materials Science and Engineering: A, Vol. 611 https://doi.org/10.1016/j.msea.2014.06.013	journal	August 2014
Comparison of microstructure with mechanical properties of irradiated tungsten Rau, R. C.; Moteff, J.; Ladd, R. L. Journal of Nuclear Materials, Vol. 24, Issue 2 https://doi.org/10.1016/0022-3115(67)90005-0	journal	November 1967
Neutron irradiation effects on tungsten materials Hasegawa, Akira; Fukuda, Makoto; Nogami, Shuhei Fusion Engineering and Design, Vol. 89, Issue 7-8 https://doi.org/10.1016/j.fusengdes.2014.04.035	journal	October 2014
Length-scale-dependent deformation mechanisms in incoherent metallic multilayered composites Misra, A.; Hirth, J. P.; Hoagland, R. G. Acta Materialia, Vol. 53, Issue 18 https://doi.org/10.1016/j.actamat.2005.06.025	journal	October 2005
Damage parameters of structural materials in fusion environment compared to fission reactor irradiation Sawan, Mohamed E. Fusion Engineering and Design, Vol. 87, Issue 5-6 https://doi.org/10.1016/j.fusengdes.2012.01.022	journal	August 2012
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
An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments Oliver, W. C.; Pharr, G. M. Journal of Materials Research, Vol. 7, Issue 06, p. 1564-1583 https://doi.org/10.1557/JMR.1992.1564	journal	June 1992
Measurement of hardness and elastic modulus by instrumented indentation: Advances in understanding and refinements to methodology Oliver, W. C.; Pharr, G. M. Journal of Materials Research, Vol. 19, Issue 1 https://doi.org/10.1557/jmr.2004.19.1.3	journal	January 2004
Numerical exploration into the potential of tungsten reinforced CuCrZr matrix composites Hohe, Jörg; Fliegener, Sascha; Findeisen, Claudio Journal of Nuclear Materials, Vol. 470 https://doi.org/10.1016/j.jnucmat.2015.11.056	journal	March 2016
Tensile behaviour of a niobium/alumina composite laminate Beals, J. T.; Nardone, V. C. Journal of Materials Science, Vol. 29, Issue 9 https://doi.org/10.1007/BF00363450	journal	May 1994
Onset of free-edge delamination in composite laminates under tensile loading Lorriot, Th.; Marion, G.; Harry, R. Composites Part B: Engineering, Vol. 34, Issue 5 https://doi.org/10.1016/S1359-8368(03)00016-7	journal	July 2003
High-Temperature Recovery of Tungsten after Neutron Irradiation Keys, L. K.; Smith, J. P.; Moteff, J. Physical Review, Vol. 176, Issue 3 https://doi.org/10.1103/PhysRev.176.851	journal	December 1968
Transmutation of Mo, Re, W, Hf, and V in various irradiation test facilities and STARFIRE Greenwood, L. R.; Garner, F. A. Journal of Nuclear Materials, Vol. 212-215 https://doi.org/10.1016/0022-3115(94)90136-8	journal	September 1994
Effects of transmutation elements on the microstructural evolution and electrical resistivity of neutron-irradiated tungsten Tanno, T.; Hasegawa, A.; He, J. C. Journal of Nuclear Materials, Vol. 386-388 https://doi.org/10.1016/j.jnucmat.2008.12.091	journal	April 2009
Stability and mobility of rhenium and osmium in tungsten: first principles study Suzudo, T.; Yamaguchi, M.; Hasegawa, A. Modelling and Simulation in Materials Science and Engineering, Vol. 22, Issue 7 https://doi.org/10.1088/0965-0393/22/7/075006	journal	September 2014
Effects of Transmutation Elements on Neutron Irradiation Hardening of Tungsten Tanno, Takashi; Hasegawa, Akira; He, Jian-Chao MATERIALS TRANSACTIONS, Vol. 48, Issue 9 https://doi.org/10.2320/matertrans.MAW200722	journal	January 2007
Ion-irradiation-induced clustering in W–Re and W–Re–Os alloys: A comparative study using atom probe tomography and nanoindentation measurements Xu, Alan; Beck, Christian; Armstrong, David E. J. Acta Materialia, Vol. 87 https://doi.org/10.1016/j.actamat.2014.12.049	journal	April 2015
Property change mechanism in tungsten under neutron irradiation in various reactors Hasegawa, Akira; Tanno, Takashi; Nogami, Shuhei Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.114	journal	October 2011
Irradiation hardening of pure tungsten exposed to neutron irradiation Hu, Xunxiang; Koyanagi, Takaaki; Fukuda, Makoto Journal of Nuclear Materials, Vol. 480 https://doi.org/10.1016/j.jnucmat.2016.08.024	journal	November 2016
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
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
Effects of solid transmutants and helium in copper studied by mixed-spectrum neutron irradiation Muroga, T.; Watanabe, H.; Yoshida, N. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00123-8	journal	October 1998
Microstructure and tensile properties of neutron irradiated Cu and Cu5Ni containing isotopically controlled boron Muroga, T.; Watanabe, H.; Yoshida, N. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(95)00027-5	journal	August 1995
14 MeV neutron irradiation effects on the yield stress of highly perfect copper single crystals Shinohara, K.; Kitajima, S. Journal of Nuclear Materials, Vol. 133-134 https://doi.org/10.1016/0022-3115(85)90237-5	journal	August 1985
Tensile fracture of surface-damaged composite laminates Choi, Duk-Hyun; Hwang, Woon-Bong Journal of Materials Science, Vol. 39, Issue 13 https://doi.org/10.1023/B:JMSC.0000033421.50530.3d	journal	July 2004
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
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
High strain rate tensile performance and microstructural evolution of Al/Cu laminated composite under dynamic loading Li, X. B.; Zu, G. Y.; Wang, P. Materials Science and Engineering: A, Vol. 612 https://doi.org/10.1016/j.msea.2014.06.032	journal	August 2014

Cited By (1)

Engineering challenges for accelerated fusion demonstrators Surrey, E. Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 377, Issue 2141 https://doi.org/10.1098/rsta.2017.0442	journal	February 2019

Similar Records

Irradiation effects in tungsten-copper laminate composite

Journal Article · Thu Dec 01 00:00:00 EST 2016 · Journal of Nuclear Materials · OSTI ID:1326484

Garrison, L. M.; Katoh, Y.; Snead, L. L.; +3 more

Second Annual Progress Report on Correlation Between Microstructure and Mechanical Properties of Neutron-Irradiated Ferritic-Martensitic and Austenitic Steels

Technical Report · Sat Feb 01 00:00:00 EST 2020 · OSTI ID:1326484

Zhong, Weicheng; Tan, Lizhen

First Annual Progress Report on the Procurement and Post-Irradiation Examination of the Selected Samples of Alloy 800H and Grade 92 and 91 Steels

Technical Report · Thu Feb 28 00:00:00 EST 2019 · OSTI ID:1326484

Tan, Lizhen; Chen, Tianyi; Linton, Kory; +2 more

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
plasma-facing material
laminate composite
fusion material
tungsten
neutron irradiation

Title: Irradiation effects in tungsten-copper laminate composite

Citation Formats

References (35)

Cited By (1)

Similar Records

Related Subjects