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Title: Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials

Abstract

Knowledge of mechanical and physical property evolution due to irradiation damage is essential for the development of future fission and fusion reactors. Ion-irradiation provides an excellent proxy for studying irradiation damage, allowing high damage doses without sample activation. Limited ion-penetration-depth means that only few-micron-thick damaged layers are produced. Substantial effort has been devoted to probing the mechanical properties of these thin implanted layers. Yet, whilst key to reactor design, their thermal transport properties remain largely unexplored due to a lack of suitable measurement techniques. Here we demonstrate non-contact thermal diffusivity measurements in ion-implanted tungsten for nuclear fusion armour. Alloying with transmutation elements and the interaction of retained gas with implantation-induced defects both lead to dramatic reductions in thermal diffusivity. These changes are well captured by our modelling approaches. Our observations have important implications for the design of future fusion power plants.

Authors:
 [1];  [2];  [3];  [3];  [3];  [2]
  1. Univ. of Oxford (United Kingdom)
  2. CCFE, Abingdon (United Kingdom)
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Publication Date:
Research Org.:
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Energy Frontier Research Centers (EFRC) (United States). Solid-State Solar-Thermal Energy Conversion Center (S3TEC)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES)
OSTI Identifier:
1242042
Grant/Contract Number:  
SC0001299
Resource Type:
Accepted Manuscript
Journal Name:
Scientific Reports
Additional Journal Information:
Journal Volume: 5; Journal ID: ISSN 2045-2322
Publisher:
Nature Publishing Group
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats

Hofmann, F., Mason, D. R., Eliason, J. K., Maznev, A. A., Nelson, K. A., and Dudarev, S. L. Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials. United States: N. p., 2015. Web. doi:10.1038/srep16042.
Hofmann, F., Mason, D. R., Eliason, J. K., Maznev, A. A., Nelson, K. A., & Dudarev, S. L. Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials. United States. doi:10.1038/srep16042.
Hofmann, F., Mason, D. R., Eliason, J. K., Maznev, A. A., Nelson, K. A., and Dudarev, S. L. Tue . "Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials". United States. doi:10.1038/srep16042. https://www.osti.gov/servlets/purl/1242042.
@article{osti_1242042,
title = {Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials},
author = {Hofmann, F. and Mason, D. R. and Eliason, J. K. and Maznev, A. A. and Nelson, K. A. and Dudarev, S. L.},
abstractNote = {Knowledge of mechanical and physical property evolution due to irradiation damage is essential for the development of future fission and fusion reactors. Ion-irradiation provides an excellent proxy for studying irradiation damage, allowing high damage doses without sample activation. Limited ion-penetration-depth means that only few-micron-thick damaged layers are produced. Substantial effort has been devoted to probing the mechanical properties of these thin implanted layers. Yet, whilst key to reactor design, their thermal transport properties remain largely unexplored due to a lack of suitable measurement techniques. Here we demonstrate non-contact thermal diffusivity measurements in ion-implanted tungsten for nuclear fusion armour. Alloying with transmutation elements and the interaction of retained gas with implantation-induced defects both lead to dramatic reductions in thermal diffusivity. These changes are well captured by our modelling approaches. Our observations have important implications for the design of future fusion power plants.},
doi = {10.1038/srep16042},
journal = {Scientific Reports},
number = ,
volume = 5,
place = {United States},
year = {2015},
month = {11}
}

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Cited by: 13 works
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Works referenced in this record:

Recent progress in research on tungsten materials for nuclear fusion applications in Europe
journal, January 2013


Power plant conceptual studies in Europe
journal, October 2007


A simulation study of large power handling in the divertor for a Demo reactor
journal, November 2013


Review on the EFDA programme on tungsten materials technology and science
journal, October 2011


Progress of He-cooled divertor development for DEMO
journal, October 2011


Effects of transmutation elements on the microstructural evolution and electrical resistivity of neutron-irradiated tungsten
journal, April 2009


Effect of neutron irradiation on thermal diffusivity of tungsten–rhenium alloys
journal, December 2000


Post irradiation testing of samples from the irradiation experiments PARIDE 3 and PARIDE 4
journal, August 2004


Overview of recent European materials R&D activities related to ITER
journal, August 2004


Review of recent works in development and evaluation of high-Z plasma facing materials
journal, March 1999


Helium behaviour and vacancy defect distribution in helium implanted tungsten
journal, May 2007


Ab initio study of helium in α Fe : Dissolution, migration, and clustering with vacancies
journal, August 2005


Helium effects on displacement cascades in α-iron
journal, September 2008


The interaction of injected helium with lattice defects in a tungsten crystal
journal, April 1972


Application of small-scale testing for investigation of ion-beam-irradiated materials
journal, October 2012

  • Kiener, Daniel; Minor, Andrew M.; Anderoglu, Osman
  • Journal of Materials Research, Vol. 27, Issue 21
  • DOI: 10.1557/jmr.2012.303

Understanding the effects of ion irradiation using nanoindentation techniques
journal, July 2015


Small-scale characterisation of irradiated nuclear materials: Part II nanoindentation and micro-cantilever testing of ion irradiated nuclear materials
journal, July 2015


Near-surface thermal characterization of plasma facing components using the 3-omega method
journal, December 2014


Measurement of thermal conductivity in proton irradiated silicon
journal, April 2014

  • Khafizov, Marat; Yablinsky, Clarissa; Allen, Todd R.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 325
  • DOI: 10.1016/j.nimb.2014.02.003

Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation
journal, November 2014


Transient thermal gratings at surfaces for thermal characterization of bulk materials and thin films
journal, September 1995

  • K�ding, O. W.; Skurk, H.; Maznev, A. A.
  • Applied Physics A Materials Science & Processing, Vol. 61, Issue 3
  • DOI: 10.1007/BF01538190

SRIM – The stopping and range of ions in matter (2010)
journal, June 2010

  • Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
  • DOI: 10.1016/j.nimb.2010.02.091

Thermal Conductivity of the Elements
journal, April 1972

  • Ho, C. Y.; Powell, R. W.; Liley, P. E.
  • Journal of Physical and Chemical Reference Data, Vol. 1, Issue 2
  • DOI: 10.1063/1.3253100

Simple Model for Characterizing the Electrical Resistivity in A 15 Superconductors
journal, April 1977


Incorporating non-adiabatic effects in embedded atom potentials for radiation damage cascade simulations
journal, March 2015


Heat Capacity of Reference Materials: Cu and W
journal, October 1984

  • White, G. K.; Collocott, S. J.
  • Journal of Physical and Chemical Reference Data, Vol. 13, Issue 4
  • DOI: 10.1063/1.555728

The Thermal Expansion of Pure Metals. II: Molybdenum, Palladium, Silver, Tantalum, Tungsten, Platinum, and Lead
journal, January 1942


Trapping and release of helium in tungsten
journal, September 2011


Trapping of He clusters by inert-gas impurities in tungsten: First-principles predictions and experimental validation
journal, June 2015

  • Nguyen-Manh, Duc; Dudarev, S. L.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 352
  • DOI: 10.1016/j.nimb.2014.11.097

Quenching and recovery investigations of vacancies in tungsten
journal, January 1980


A description of stress driven bubble growth of helium implanted tungsten
journal, May 2009


An object Kinetic Monte Carlo Simulation of the dynamics of helium and point defects in tungsten
journal, March 2009


Optimization and limitations of known DEMO divertor concepts
journal, August 2012


Potential and limits of water cooled divertor concepts based on monoblock design as possible candidates for a DEMO reactor
journal, October 2013


    Works referencing / citing this record:

    Recent advances in characterising irradiation damage in tungsten for fusion power
    journal, November 2019


    Thermal diffusivity determination using heterodyne phase insensitive transient grating spectroscopy
    journal, June 2018

    • Dennett, Cody A.; Short, Michael P.
    • Journal of Applied Physics, Vol. 123, Issue 21
    • DOI: 10.1063/1.5026429

    Anomalous thermal diffusivity in underdoped YBa 2 Cu 3 O 6+x
    journal, May 2017

    • Zhang, Jiecheng; Levenson-Falk, Eli M.; Ramshaw, B. J.
    • Proceedings of the National Academy of Sciences, Vol. 114, Issue 21
    • DOI: 10.1073/pnas.1703416114

    An empirical potential for simulating vacancy clusters in tungsten
    journal, November 2017

    • Mason, D. R.; Nguyen-Manh, D.; Becquart, C. S.
    • Journal of Physics: Condensed Matter, Vol. 29, Issue 50
    • DOI: 10.1088/1361-648x/aa9776

    The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets
    journal, March 2018

    • De Temmerman, G.; Hirai, T.; Pitts, R. A.
    • Plasma Physics and Controlled Fusion, Vol. 60, Issue 4
    • DOI: 10.1088/1361-6587/aaaf62

    Impact of irradiation induced dislocation loops on thermal conductivity in ceramics
    journal, June 2019

    • Khafizov, Marat; Pakarinen, Janne; He, Lingfeng
    • Journal of the American Ceramic Society, Vol. 102, Issue 12
    • DOI: 10.1111/jace.16616