Thermal gradient effect on helium and self-interstitial transport in tungsten
Abstract
First-wall materials in a fusion reactor are expected to withstand harsh conditions, with high heat and particle fluxes that modify the materials microstructure. These fluxes will create strong gradients of temperature and concentration of diverse species. Besides the He ash and the hydrogenic species, neutron particles generated in the fusion reaction will collide with the material creating intrinsic defects, such as vacancies, self-interstitials atoms (SIAs), and clusters of such point defects. These defects and the He atoms will then migrate in the presence of the aforementioned gradients. In this study, we use nonequilibrium molecular dynamics to analyze the transport of He and SIAs in the presence of a thermal gradient in tungsten. We observe that, in all cases, the defects and impurity atoms tend to migrate toward the hot regions of the tungsten sample. The resulting species concentration profiles are exponential distributions, rising toward the hot regions of the sample, in agreement with irreversible thermodynamics analysis. For both He atoms and SIAs, we find that the resulting species flux is directed opposite to the heat flux, indicating that species transport is governed by a Soret effect (thermal-gradient-driven diffusion) characterized by a negative heat of transport that drives species diffusion uphillmore »
- Authors:
-
- Clemson Univ., SC (United States)
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Univ. of Tennessee, Knoxville, TN (United States)
- Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Univ. of Massachusetts, Amherst, MA (United States)
- Publication Date:
- Research Org.:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR)
- OSTI Identifier:
- 1868296
- Alternate Identifier(s):
- OSTI ID: 1833870
- Report Number(s):
- LA-UR-21-28937
Journal ID: ISSN 0021-8979; TRN: US2306580
- Grant/Contract Number:
- 89233218CNA000001; SC0008875; SC0018421
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Applied Physics
- Additional Journal Information:
- Journal Volume: 130; Journal Issue: 21; Journal ID: ISSN 0021-8979
- Publisher:
- American Institute of Physics (AIP)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; Material Science; Fusion; Helium; Thermal gradients; Concentration gradients; Crystallographic defects; Molecular dynamics; Thermodynamic states and processes; Thermal conductivity; Transition metals; Irreversible thermodynamics; Fusion reactors; Thermophoresis; Computer simulation; Nuclear fusion
Citation Formats
Martínez, Enrique, Mathew, Nithin, Perez, Danny, Blondel, Sophie, Dasgupta, Dwaipayan, Wirth, Brian D., and Maroudas, Dimitrios. Thermal gradient effect on helium and self-interstitial transport in tungsten. United States: N. p., 2021.
Web. doi:10.1063/5.0071935.
Martínez, Enrique, Mathew, Nithin, Perez, Danny, Blondel, Sophie, Dasgupta, Dwaipayan, Wirth, Brian D., & Maroudas, Dimitrios. Thermal gradient effect on helium and self-interstitial transport in tungsten. United States. https://doi.org/10.1063/5.0071935
Martínez, Enrique, Mathew, Nithin, Perez, Danny, Blondel, Sophie, Dasgupta, Dwaipayan, Wirth, Brian D., and Maroudas, Dimitrios. Fri .
"Thermal gradient effect on helium and self-interstitial transport in tungsten". United States. https://doi.org/10.1063/5.0071935. https://www.osti.gov/servlets/purl/1868296.
@article{osti_1868296,
title = {Thermal gradient effect on helium and self-interstitial transport in tungsten},
author = {Martínez, Enrique and Mathew, Nithin and Perez, Danny and Blondel, Sophie and Dasgupta, Dwaipayan and Wirth, Brian D. and Maroudas, Dimitrios},
abstractNote = {First-wall materials in a fusion reactor are expected to withstand harsh conditions, with high heat and particle fluxes that modify the materials microstructure. These fluxes will create strong gradients of temperature and concentration of diverse species. Besides the He ash and the hydrogenic species, neutron particles generated in the fusion reaction will collide with the material creating intrinsic defects, such as vacancies, self-interstitials atoms (SIAs), and clusters of such point defects. These defects and the He atoms will then migrate in the presence of the aforementioned gradients. In this study, we use nonequilibrium molecular dynamics to analyze the transport of He and SIAs in the presence of a thermal gradient in tungsten. We observe that, in all cases, the defects and impurity atoms tend to migrate toward the hot regions of the tungsten sample. The resulting species concentration profiles are exponential distributions, rising toward the hot regions of the sample, in agreement with irreversible thermodynamics analysis. For both He atoms and SIAs, we find that the resulting species flux is directed opposite to the heat flux, indicating that species transport is governed by a Soret effect (thermal-gradient-driven diffusion) characterized by a negative heat of transport that drives species diffusion uphill (from the cooler to the hot regions of the sample). We demonstrate that the steady-state species profiles obtained accounting for the Soret effect vary significantly from those where temperature-gradient-driven transport is not considered and discuss the implications of such a Soret effect on the response to plasma exposure of plasma-facing tungsten.},
doi = {10.1063/5.0071935},
journal = {Journal of Applied Physics},
number = 21,
volume = 130,
place = {United States},
year = {Fri Dec 03 00:00:00 EST 2021},
month = {Fri Dec 03 00:00:00 EST 2021}
}
Works referenced in this record:
Visualization and analysis of atomistic simulation data with OVITO–the Open Visualization Tool
journal, December 2009
- Stukowski, Alexander
- Modelling and Simulation in Materials Science and Engineering, Vol. 18, Issue 1
Interatomic potentials for modelling radiation defects and dislocations in tungsten
journal, September 2013
- Marinica, M-C; Ventelon, Lisa; Gilbert, M. R.
- Journal of Physics: Condensed Matter, Vol. 25, Issue 39
Integration of an advanced He-cooled divertor in a DEMO-relevant tokamak geometry
journal, February 2006
- Ihli, T.; Hermsmeyer, S.; Köhly, C.
- Fusion Engineering and Design, Vol. 81, Issue 1-7
Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions
journal, August 2009
- Kajita, Shin; Sakaguchi, Wataru; Ohno, Noriyasu
- Nuclear Fusion, Vol. 49, Issue 9
Molecular dynamics simulation of the diffusion of self-interstitial atoms and interstitial loops under temperature gradient field in tungsten
journal, August 2020
- Fang, Jingzhong; Liu, Lixia; Gao, Ning
- Journal of Applied Physics, Vol. 128, Issue 6
Boltzmann Transport in Nanostructures as a Friction Effect
journal, July 2017
- Cepellotti, Andrea; Marzari, Nicola
- Nano Letters, Vol. 17, Issue 8
Migration Energy of He in W Revisited by Ab Initio Calculations
journal, November 2006
- Becquart, Charlotte S.; Domain, Christophe
- Physical Review Letters, Vol. 97, Issue 19
Efficient Management of Parallelism in Object-Oriented Numerical Software Libraries
book, January 1997
- Balay, Satish; Gropp, William D.; McInnes, Lois Curfman
- Modern Software Tools for Scientific Computing
Materials research for fusion
journal, May 2016
- Knaster, J.; Moeslang, A.; Muroga, T.
- Nature Physics, Vol. 12, Issue 5
Use of tungsten material for the ITER divertor
journal, December 2016
- Hirai, T.; Panayotis, S.; Barabash, V.
- Nuclear Materials and Energy, Vol. 9
Size effects in thermal conduction by phonons
journal, August 2014
- Allen, Philip B.
- Physical Review B, Vol. 90, Issue 5
Interatomic potentials for simulation of He bubble formation in W
journal, January 2013
- Juslin, N.; Wirth, B. D.
- Journal of Nuclear Materials, Vol. 432, Issue 1-3
Thermomigration and Electromigration in Zirconium
journal, March 1969
- Campbell, D. R.; Huntington, H. B.
- Physical Review, Vol. 179, Issue 3
Benchmarks and Tests of a Multidimensional Cluster Dynamics Model of Helium Implantation in Tungsten
journal, January 2017
- Blondel, Sophie; Bernholdt, David E.; Hammond, Karl D.
- Fusion Science and Technology, Vol. 71, Issue 1
Fast Parallel Algorithms for Short-Range Molecular Dynamics
journal, March 1995
- Plimpton, Steve
- Journal of Computational Physics, Vol. 117, Issue 1
Crystal orientation effects on helium ion depth distributions and adatom formation processes in plasma-facing tungsten
journal, October 2014
- Hammond, Karl D.; Wirth, Brian D.
- Journal of Applied Physics, Vol. 116, Issue 14
Thermal conductivity of tungsten: Effects of plasma-related structural defects from molecular-dynamics simulations
journal, August 2017
- Hu, Lin; Wirth, Brian D.; Maroudas, Dimitrios
- Applied Physics Letters, Vol. 111, Issue 8
Present Research Status on Divertor and Plasma Facing Components for Fusion Power Plants
journal, July 2003
- Suzuki, S.; Ueda, Y.; Tokunaga, K.
- Fusion Science and Technology, Vol. 44, Issue 1
He cluster dynamics in W in the presence of cluster induced formation of He traps
journal, January 2016
- Krasheninnikov, S. I.; Smirnov, R. D.
- Physica Scripta, Vol. T167
Reciprocal Relations in Irreversible Processes. I.
journal, February 1931
- Onsager, Lars
- Physical Review, Vol. 37, Issue 4