Estimation of the Thermal-Fluids and Thermal-Structural Performance of Helium-Cooled Modular Finger-Type Divertors

Lee, D. S.; Lanahan, M. L.; Grohmann, J.; Abdel-Khalik, S. I.; Blanchard, J. P.; Yoda, M.

doi:10.1016/j.fusengdes.2024.114217

Estimation of the Thermal-Fluids and Thermal-Structural Performance of Helium-Cooled Modular Finger-Type Divertors

Journal Article · Fri Feb 09 23:00:00 EST 2024 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2024.114217· OSTI ID:2570350

^[1]; Lanahan, M. L. ^[1]; Grohmann, J. ^[1]; Abdel-Khalik, S. I. ^[1]; Blanchard, J. P. ^[2]; ^[3]

Georgia Institute of Technology, Atlanta, GA (United States)
Univ. of Wisconsin, Madison, WI (United States)
Michigan State Univ., East Lansing, MI (United States)

Over the past decade, our group has investigated the thermal-fluid performance of the helium-cooled modular divertor with multiple jets (HEMJ) and a simplified “flat” design of the HEMJ for long-pulse magnetic fusion energy (MFE) reactors. Experimental studies were performed in a helium (He) loop at the prototypical pressure of 10 MPa, nearly prototypical He temperatures and incident heat fluxes using test sections made from stainless steel and tungsten alloys. Correlations for average Nusselt numbers and pressure loss coefficients were developed from the data and are used to validate computational fluid dynamics (CFD) models. Here, this work presents updated thermal-fluids performance curves based on these correlations that estimate the maximum heat flux that can be accommodated by the plasma-facing surface and coolant pumping power requirements at prototypical operating conditions. Thermal-structural performance curves developed from ITER structural design criteria are introduced, which include protection against ductile and non-ductile failure, ratcheting fatigue, and creep fatigue. The performance design curves for these finger-type divertors demonstrate that the “flat” design, with a significantly less complicated geometry than the HEMJ, has thermal-fluid and thermal-structural performance comparable to the original HEMJ concept, and may be superior in terms of non-ductile failure criteria.

View Accepted Manuscript (DOE)

Research Organization:: Georgia Institute of Technology, Atlanta, GA (United States); Univ. of Wisconsin, Madison, WI (United States); Michigan State Univ., East Lansing, MI (United States)

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

Grant/Contract Number:: FG02-01ER54656; FG02-01ER54656

OSTI ID:: 2570350

Alternate ID(s):: OSTI ID: 2301794

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 200; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (15)

ITER structural design criteria and their extension to advanced reactor blankets Majumdar, S.; Kalinin, G. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00324-X	journal	December 2000
Material/plasma surface interaction issues following neutron damage Barabash, V.; Federici, G.; Linke, J. Journal of Nuclear Materials, Vol. 313-316 https://doi.org/10.1016/S0022-3115(02)01330-2	journal	March 2003
Treatment of irradiation effects in structural design criteria for fusion reactors Majumdar, Saurin; Smith, Peter Fusion Engineering and Design, Vol. 41, Issue 1-4 https://doi.org/10.1016/S0920-3796(97)00142-7	journal	September 1998
He-cooled divertor for DEMO: Status of development and HHF tests Norajitra, Prachai; Giniyatulin, Radmir; Kuznetsov, Vladimir Fusion Engineering and Design, Vol. 85, Issue 10-12 https://doi.org/10.1016/j.fusengdes.2010.09.006	journal	December 2010
Thermo-structural design of the European DEMO water-cooled blanket with a multiscale-multiphysics framework Huang, Yue; Cismondi, Fabio; Diegele, Eberhard Fusion Engineering and Design, Vol. 135 https://doi.org/10.1016/j.fusengdes.2018.07.007	journal	October 2018
Steady state thermo-mechanics and material property definition framework for analyzing DCLL blanket in the fusion nuclear science facility Aduloju, Sunday C.; Kessel, Charles; Youchison, Dennis Fusion Engineering and Design, Vol. 183 https://doi.org/10.1016/j.fusengdes.2022.113257	journal	October 2022
Post irradiation testing of samples from the irradiation experiments PARIDE 3 and PARIDE 4 Roedig, M.; Kuehnlein, W.; Linke, J. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.176	journal	August 2004
Limitations of W and W–1%La2O3 for use as structural materials Rieth, Michael; Dafferner, Bernhard Journal of Nuclear Materials, Vol. 342, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2005.03.013	journal	June 2005
A full tungsten divertor for ITER: Physics issues and design status Pitts, R. A.; Carpentier, S.; Escourbiac, F. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.008	journal	July 2013
Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan Nogami, Shuhei; Hasegawa, Akira; Fukuda, Makoto Journal of Nuclear Materials, Vol. 543 https://doi.org/10.1016/j.jnucmat.2020.152506	journal	January 2021
Recrystallization behavior of hot-rolled pure tungsten and its alloy plates during high-temperature annealing Tsuchida, Kohei; Miyazawa, Takeshi; Hasegawa, Akira Nuclear Materials and Energy, Vol. 15 https://doi.org/10.1016/j.nme.2018.04.004	journal	May 2018
Thermal Hydraulics of Helium-Cooled Finger-Type Divertors at Higher Incident Heat Fluxes Lee, D. S.; Musa, S. A.; Abdel-Khalik, S. I. Fusion Science and Technology, Vol. 75, Issue 8 https://doi.org/10.1080/15361055.2019.1593008	journal	May 2019
Updated Thermofluid Performance of the Simplified Flat Variant of the HEMJ Lee, D. S.; Musa, S. A.; Abdel-Khalik, S. I. Fusion Science and Technology, Vol. 77, Issue 7-8 https://doi.org/10.1080/15361055.2021.1920783	journal	September 2021
Performance Comparison of Helium and sCO ₂ as Coolants for Modular Finger-Type Divertors Lanahan, Michael L.; Abdel-Khalik, Said I.; Yoda, Minami Fusion Science and Technology, Vol. 80, Issue 1 https://doi.org/10.1080/15361055.2023.2198046	journal	May 2023
Tungsten as a Structural Divertor Material Rieth, Michael; Armstrong, Dave; Dafferner, Bernhard Advances in Science and Technology https://doi.org/10.4028/www.scientific.net/AST.73.11	conference	October 2010

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Estimation of the Thermal-Fluids and Thermal-Structural Performance of Helium-Cooled Modular Finger-Type Divertors

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