Dependence of Heat Removal Rate of Pebble-Based Rods on Inter-Pebble Matrix Fill Fraction

Martinez-Loran, Erick; Schwen, Daniel; Spencer, Benjamin W.; Boedo, Jose; Hollmann, Eric

doi:10.1080/15361055.2024.2395133

Title: Dependence of Heat Removal Rate of Pebble-Based Rods on Inter-Pebble Matrix Fill Fraction

Journal Article · 30 September 2024 · Fusion Science and Technology

DOI: https://doi.org/10.1080/15361055.2024.2395133 · OSTI ID:2462686

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Univ. of California, San Diego, CA (United States). Center for Energy Research
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Carbon pebble rods are a promising candidate for use in high heat flux regions of magnetic fusion energy reactor walls. Under high (10 – 50 MW/m²) heat loads, carbon pebble rods release hot pebbles from the exposed surface, carrying away heat as the pebble rod surface recedes. In this work, we show that the surface recession rate during heating can be adjusted by changing the mechanical strength of the extruded rods, modifying the heat removal rate; this is accomplished here by varying the fill fraction of the inter-pebble matrix. A three-dimensional finite element model is presented that captures many experimental observations, including the sphere temperature and the surface recession rate. The model predicts that pebble release is caused by thermally driven crack propagation through the matrix and that the matrix strength against breaking is the single most important material parameter setting the pebble release rate; this prediction is supported by experimental results.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Advanced Research Projects Agency - Energy (ARPA-E)

Grant/Contract Number:: AC07-05ID14517; AR0001373

OSTI ID:: 2462686

Report Number(s):: INL/JOU--24-78194-Rev000

Journal Information:: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 3 Vol. 81; ISSN 1536-1055

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

References (31)

Glassy Carbon low-temperature thermodynamic properties Takahashi, Yoichi; Westrum, Edgar F. The Journal of Chemical Thermodynamics, Vol. 2, Issue 6 https://doi.org/10.1016/0021-9614(70)90028-5	journal	November 1970
Blister formation of tungsten due to ion bombardment Wang, Wenmin; Roth, J.; Lindig, S. Journal of Nuclear Materials, Vol. 299, Issue 2 https://doi.org/10.1016/S0022-3115(01)00679-1	journal	November 2001
Irradiation experiments of divertor pebbles Isobe, M.; Matsuhiro, K.; Ueda, Y. Fusion Engineering and Design, Vol. 49-50 https://doi.org/10.1016/S0920-3796(00)00444-0	journal	November 2000
Pumping performance of pebble drop divertor Matsuhiro, K.; Isobe, M.; Ueda, Y. Fusion Engineering and Design, Vol. 49-50 https://doi.org/10.1016/S0920-3796(00)00446-4	journal	November 2000
An injector device for producing clean-surface liquid metal samples of Li, Ga and Sn–Li in vacuum Baldwin, M. J.; Lynch, T.; Chousal, L. Fusion Engineering and Design, Vol. 70, Issue 2 https://doi.org/10.1016/S0920-3796(03)00415-0	journal	February 2004
Tritium retention and clean-up in JET Andrew, P.; Brennan, P. D.; Coad, J. P. Fusion Engineering and Design, Vol. 47, Issue 2-3 https://doi.org/10.1016/S0920-3796(99)00084-8	journal	December 1999
Thermal expansion of graphite revisited Zorzi, Janete E.; Perottoni, Cláudio A. Computational Materials Science, Vol. 199 https://doi.org/10.1016/j.commatsci.2021.110719	journal	November 2021
LAMMPS - a flexible simulation tool for particle-based materials modeling at the atomic, meso, and continuum scales Thompson, Aidan P.; Aktulga, H. Metin; Berger, Richard Computer Physics Communications, Vol. 271 https://doi.org/10.1016/j.cpc.2021.108171	journal	February 2022
The cascading pebble divertor for the spherical tokamak power plant Voss, G. M.; Bond, A.; Davis, S. Fusion Engineering and Design, Vol. 81, Issue 1-7 https://doi.org/10.1016/j.fusengdes.2005.08.090	journal	February 2006
Overview of the JET ITER-like Wall Project Philipps, V.; Mertens, Ph.; Matthews, G. F. Fusion Engineering and Design, Vol. 85, Issue 7-9 https://doi.org/10.1016/j.fusengdes.2010.04.048	journal	December 2010
Overview over DEMO design integration challenges and their impact on component design concepts Bachmann, C.; Ciattaglia, S.; Cismondi, F. Fusion Engineering and Design, Vol. 136 https://doi.org/10.1016/j.fusengdes.2017.12.040	journal	November 2018
Sigma phase formation in irradiated tungsten, tantalum and molybdenum in a fusion power plant Cottrell, G. A. Journal of Nuclear Materials, Vol. 334, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.07.001	journal	September 2004
Modelling of deposition of hydrocarbon films underneath the divertor and in the pumping ducts of ITER Federici, G.; Mayer, M.; Strohmayer, G. Journal of Nuclear Materials, Vol. 337-339 https://doi.org/10.1016/j.jnucmat.2004.10.007	journal	March 2005
Reduced deuterium retention in simultaneously damaged and annealed tungsten Simmonds, M. J.; Wang, Y. Q.; Barton, J. L. Journal of Nuclear Materials, Vol. 494 https://doi.org/10.1016/j.jnucmat.2017.06.010	journal	October 2017
Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI Nygren, R. E.; Tabarés, F. L. Nuclear Materials and Energy, Vol. 9 https://doi.org/10.1016/j.nme.2016.08.008	journal	December 2016
Impact of wall materials and seeding gases on the pedestal and on core plasma performance Wolfrum, E.; Beurskens, M.; Dunne, M. G. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.01.002	journal	August 2017
Flowing liquid lithium plasma-facing components – Physics, technology and system analysis of the LiMIT system Ruzic, D. N.; Szott, M.; Sandoval, C. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.06.001	journal	August 2017
European divertor target concepts for DEMO: Design rationales and high heat flux performance You, J. H.; Visca, E.; Barrett, T. Nuclear Materials and Energy, Vol. 16 https://doi.org/10.1016/j.nme.2018.05.012	journal	August 2018
3.0 - MOOSE: Enabling massively parallel multiphysics simulations Giudicelli, Guillaume; Lindsay, Alexander; Harbour, Logan SoftwareX, Vol. 26 https://doi.org/10.1016/j.softx.2024.101690	journal	May 2024
Study of ice and snow melting process on conductive asphalt solar collector Chen, Mingyu; Wu, Shaopeng; Wang, Hong Solar Energy Materials and Solar Cells, Vol. 95, Issue 12 https://doi.org/10.1016/j.solmat.2011.07.013	journal	December 2011
Development of pebble-based extruded carbon rods for extreme plasma heat flux environments Martinez-Loran, Erick; Izadi, Alborz; Jain, Amit Journal of Applied Physics, Vol. 133, Issue 24 https://doi.org/10.1063/5.0139921	journal	June 2023
A liquid metal dropper for experiments on the wettability of liquid metals on plasma facing components López Pérez, C.; Marchhart, T.; Kawashimo, K. Review of Scientific Instruments, Vol. 94, Issue 10 https://doi.org/10.1063/5.0165646	journal	October 2023
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms Williamson, Richard L.; Hales, Jason D.; Novascone, Stephen R. Nuclear Technology https://doi.org/10.1080/00295450.2020.1836940	journal	March 2021
Scalable Feature Tracking for Finite Element Meshes Demonstrated with a Novel Phase-Field Grain Subdivision Model Permann, Cody J.; Jokisaari, Andrea M.; Tonks, Michael R. Nuclear Technology, Vol. 207, Issue 7 https://doi.org/10.1080/00295450.2020.1843893	journal	March 2021
Overview of material re-deposition and fuel retention studies at JET with the Gas Box divertor Coad, J. P.; Likonen, J.; Rubel, M. Nuclear Fusion, Vol. 46, Issue 2 https://doi.org/10.1088/0029-5515/46/2/018	journal	January 2006
Overview of the JET results with the ITER-like wall Romanelli, F. Nuclear Fusion, Vol. 53, Issue 10 https://doi.org/10.1088/0029-5515/53/10/104002	journal	September 2013
Transient induced tungsten melting at the Joint European Torus (JET) Coenen, J. W.; Matthews, G. F.; Krieger, K. Physica Scripta, Vol. T170 https://doi.org/10.1088/1402-4896/aa8789	journal	September 2017
Overview of fuel inventory in JET with the ITER-like wall Widdowson, A.; Coad, J. P.; Alves, E. Nuclear Fusion, Vol. 57, Issue 8 https://doi.org/10.1088/1741-4326/aa7475	journal	July 2017
A discrete numerical model for granular assemblies Cundall, P. A.; Strack, O. D. L. Géotechnique, Vol. 29, Issue 1 https://doi.org/10.1680/geot.1979.29.1.47	journal	March 1979
Phenol-Formaldehyde Resin for Optical-Chemical Temperature Sensing Claucherty, Steven; Sakaue, Hirotaka Sensors, Vol. 18, Issue 6 https://doi.org/10.3390/s18061756	journal	May 2018
Mechanical Properties for Reliability Analysis of Structures in Glassy Carbon Garion, Cédric World Journal of Mechanics, Vol. 04, Issue 03 https://doi.org/10.4236/wjm.2014.43009	journal	January 2014

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