Citations (26)
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Read on this site (11)
Michael L. Lanahan, Said I. Abdel-Khalik & Minami Yoda. (2024) Performance Comparison of Helium and sCO2 as Coolants for Modular Finger-Type Divertors. Fusion Science and Technology 80:1, pages 108-116.
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Michael L. Lanahan, Said I. Abdel-Khalik & Minami Yoda. (2023) Bayesian Parameter Estimation of the k-ω Shear Stress Transport Model for Accurate Simulations of Impinging-Jet Heat Transfer. Fusion Science and Technology 0:0, pages 1-11.
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Cody S. Wiggins, Dennis L. Youchison, Fayaz Rasheed, Charles Kessel, Monica Gehrig, Michael Harper, Adam Carroll, Dean McGinnis, Michael Morrow & Chase Joslin. (2023) Qualification and Commissioning of Helium Flow Loop Experiment for Blanket Design Measurements. Fusion Science and Technology 0:0, pages 1-10.
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Dennis Youchison, Charles Kessel & Paul Nogradi. (2023) Large Component Simulation of an Inboard Sector of a Dual-Coolant Lead-Lithium Blanket. Fusion Science and Technology 79:3, pages 222-250.
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Felipe S. Novais, Nicholas R. Brown & G. Ivan Maldonado. (2023) Tritium Breeding Ratio Evaluation of Solid Breeder Concepts for the FESS-FNSF. Fusion Science and Technology 0:0, pages 1-12.
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Feng Xu, Qiusheng Liu & Makoto Shibahara. (2022) Transient forced convective heat transfer of helium gas in a narrow tube heated by exponential time-varying heat source. Experimental Heat Transfer 35:5, pages 591-610.
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C. E. Kessel, T. Bohm, M. S. Tillack, P. Titus & Y. Zhai. (2021) The Compactness and Inboard Radial Build of Fusion Nuclear Devices. Fusion Science and Technology 77:7-8, pages 519-531.
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C. E. Kessel, D. Andruczyk, J. P. Blanchard, T. Bohm, A. Davis, K. Hollis, P. W. Humrickhouse, M. Hvasta, M. Jaworski, J. Jun, Y. Katoh, A. Khodak, J. Klein, E. Kolemen, G. Larsen, R. Majeski, B. J. Merrill, N. B. Morley, G. H. Neilson, B. Pint, M. E. Rensink, T. D. Rognlien, A. F. Rowcliffe, S. Smolentsev, M. S. Tillack, L. M. Waganer, G. M. Wallace, P. Wilson & S.-J. Yoon. (2019) Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility. Fusion Science and Technology 75:8, pages 886-917.
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L. A. El-Guebaly. (2018) Nuclear Assessment to Support ARIES Power Plants and Next-Step Facilities: Emerging Challenges and Lessons Learned. Fusion Science and Technology 74:4, pages 340-369.
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L. El-Guebaly, L. Mynsberge, A. Davis, C. D’Angelo, A. Rowcliffe & B. Pint. (2017) Design and Evaluation of Nuclear System for ARIES-ACT2 Power Plant with DCLL Blanket. Fusion Science and Technology 72:1, pages 17-40.
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C. E. Kessel & F. M. Poli. (2015) Physics Basis for a Conservative Physics and Conservative Technology Tokamak Power Plant: ARIES-ACT2. Fusion Science and Technology 67:1, pages 220-239.
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Articles from other publishers (15)
Sunday C. Aduloju, Charles Kessel, Dennis Youchison, Fayaz Rasheed & Paul Nogradi Jr.. (2022) Steady state thermo-mechanics and material property definition framework for analyzing DCLL blanket in the fusion nuclear science facility. Fusion Engineering and Design 183, pages 113257.
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Corson L. Cramer, Emanuel Ionescu, Magdalena Graczyk-Zajac, Andrew T. Nelson, Yutai Katoh, Jeffery J. Haslam, Lothar Wondraczek, Trevor G. Aguirre, Saniya LeBlanc, Hsin Wang, Mansour Masoudi, Ed Tegeler, Ralf Riedel, Paolo Colombo & Majid Minary-Jolandan. (2022) Additive manufacturing of ceramic materials for energy applications: Road map and opportunities. Journal of the European Ceramic Society 42:7, pages 3049-3088.
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Laila A. El-Guebaly, Wahyu Setyawan, Charles H. Henager Jr, Richard J. Kurtz & G. Robert Odette. (2021) Neutron activation and radiation damage assessment for W-Ni-Fe tungsten heavy alloys with variable Ni content. Nuclear Materials and Energy 29, pages 101092.
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Wahyu Setyawan & David J. Senor. (2021) Influence of hydrogen isotopes on vacancy formation and antisite defect diffusion in palladium and vanadium metals. Computational Materials Science 197, pages 110641.
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Fumito Okino & Satoshi Konishi. (2020) Emissivity measurement of PbLi droplets in a vacuum for heat recovery by radiation. Fusion Engineering and Design 160, pages 111961.
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K.M. Young & Sergey Sadakov. (2020) Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma. Fusion Engineering and Design 153, pages 111457.
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Takashi Nozawa, Takaaki Koyanagi, Yutai Katoh & Hiroyasu Tanigawa. (2019) High-dose, intermediate-temperature neutron irradiation effects on silicon carbide composites with varied fiber/matrix interfaces. Journal of the European Ceramic Society 39:8, pages 2634-2647.
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ChangHo Park, Takashi Nozawa, Ryuta Kasada, Silvano Tosti, Satoshi Konishi & Hiroyasu Tanigawa. (2018) The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C. Fusion Engineering and Design 136, pages 623-627.
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Fumito Okino, Ryuta Kasada & Satoshi Konishi. (2018) Liquid PbLi atomization in vacuum for tritium and heat recovery. Fusion Engineering and Design 136, pages 63-66.
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James Blanchard, Carl Martin & Wei Liu. (2018) Effect of ELMS and disruptions on FNSF plasma-facing components. Fusion Engineering and Design 135, pages 337-345.
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Y. Huang, M.S. Tillack, N.M. Ghoniem, J.P. Blanchard, L.A. El-Guebaly & C.E. Kessel. (2018) Multiphysics modeling of the FW/Blanket of the U.S. fusion nuclear science facility (FNSF). Fusion Engineering and Design 135, pages 279-289.
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Paul W. Humrickhouse & Brad J. Merrill. (2018) Tritium aspects of the fusion nuclear science facility. Fusion Engineering and Design 135, pages 302-313.
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A.F. Rowcliffe, C.E. Kessel, Y. Katoh, L.M. Garrison, L. Tan, Y. Yamamoto & F.W. Wiffen. (2018) Materials-engineering challenges for the fusion core and lifetime components of the fusion nuclear science facility. Nuclear Materials and Energy 16, pages 82-87.
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James P. Blanchard & Carl J. Martin. (2015) Thermomechanical analysis of tungsten plasma-facing components under transient loading. Thermomechanical analysis of tungsten plasma-facing components under transient loading.
Sunday C. Aduloju, Kessel Charles, Youchison Dennis, Rasheed Fayaz & Nogradi Jr. Paul. (2022) Steady State Thermo-Mechanics and Material Property Definition Framework for Analyzing Dcll Blanket in the Fusion Nuclear Science Facility. SSRN Electronic Journal.
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