Conceptual design study for heat exhaust management in the ARC fusion pilot plant by Kuang, A. Q., Cao, N. M., Creely, Alexander James, Dennett, Cody Andrew, Hecla, Jake J., Labombard, Brian, Tinguely, Roy Alexander., Tolman, Elizabeth Ann, Hoffman, Henry, Major, M., Ruiz Ruiz, Juan, Brunner, Daniel Frederic, Grover, P., Laughman, C., Sorbom, Brandon Nils, Whyte, Dennis G.

“…Sorbom et al., FED 100 (2015) 378] to explore options for managing ∼525 MW of fusion power generated in a compact, high field (B0 = 9.2 T) tokamak that is approximately the size of JET (R0 = 3.3 m). …”
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The irradiation resistance of oxide dispersion strengthened steels by Burrows, C

“…</p> <p>The use of these particles to sequester helium is of particular significance in the development of a structural ODS steel for fusion reactor systems. A fusion power reactor, based on the ITER design, is expected to produce over 2000 appm transmutant helium in any steel components exposed to the core neutron flux. …”

Optical transmittance investigation of 1-keV ion-irradiated sapphire crystals as potential VUV to NIR window materials of fusion reactors by Keisuke Iwano, Kohei Yamanoi, Yuki Iwasa, Kazuyuki Mori, Yuki Minami, Ren Arita, Takuma Yamanaka, Kazuhito Fukuda, Melvin John F. Empizo, Keisuke Takano, Toshihiko Shimizu, Makoto Nakajima, Masashi Yoshimura, Nobuhiko Sarukura, Takayoshi Norimatsu, Masanori Hangyo, Hiroshi Azechi, Bess G. Singidas, Roland V. Sarmago, Makoto Oya, Yoshio Ueda

“…With an optical transmittance in the VUV region that can recover through simple annealing and with a high transparency from the ultraviolet (UV) to the NIR region, sapphire crystals can therefore be used as good optical windows inside modern fusion power reactors in terms of light particle loadings of hydrogen isotopes and helium.…”
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DONES EVO: Risk mitigation for the IFMIF-DONES facility by M. Weber, A. Marchena, J. Aguilar, N. Ballesteros, I. Cobo, A. Echeverría, D. Esperante, E. Fernández, E. Fernández, A. García, T. García, B. Garcinuño, D. Gavela, P. Gil, A. Gómez, L. Gutiérrez, A. Ibarra, D. Iriarte, A. Lázaro, R. Lorenzo, E. López-Melero, J. Maestre, R. Maldonado, A.J. Martínez, L. Mendoza, C. de la Morena, F. Mota, C. Oliver, M.I. Ortíz, J. Patiño, I. Podadera, I. Porras, J. Praena, D. Regidor, F.J. Rodrigo, J. Bastarrarena, J. Romero, M. Sánchez, J. Sánchez, S. Sanz, G. Sarmiento, J. Serna, C. Tarancón, E. Ugarte

“…The International Fusion Materials Irradiation Facility- DEMO Oriented Neutron Source (IFMIF-DONES) is a scientific infrastructure aimed to provide an intense neutron source for the qualification of materials to be used in future fusion power reactors. Its implementation is critical for the construction of the fusion DEMOnstration Power Plant (DEMO).IFMIF-DONES is a unique facility requiring a broad set of technologies. …”
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Large-Scale Tungsten Fibre-Reinforced Tungsten and Its Mechanical Properties by Daniel Schwalenberg, Jan Willem Coenen, Johann Riesch, Till Hoeschen, Yiran Mao, Alexander Lau, Hanns Gietl, Leonard Raumann, Philipp Huber, Christian Linsmeier, Rudolf Neu

“…Tungsten-fibre-reinforced tungsten composites (<inline-formula><math xmlns="http://www.w3.org/1998/Math/MathML" display="inline"><semantics><mrow><msub><mi>W</mi><mi>f</mi></msub><mo>/</mo><mi>W</mi></mrow></semantics></math></inline-formula>) have been in development to overcome the inherent brittleness of tungsten as one of the most promising candidates for the first wall and divertor armour material in a future fusion power plant. As the development of <inline-formula><math xmlns="http://www.w3.org/1998/Math/MathML" display="inline"><semantics><mrow><msub><mi>W</mi><mi>f</mi></msub><mo>/</mo><mi>W</mi></mrow></semantics></math></inline-formula> continues, the fracture toughness of the composite is one of the main design drivers. …”
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Composition Stability and Cr-Rich Phase Formation in W-Cr-Y and W-Cr-Ti Smart Alloys by Damian Sobieraj, Jan S. Wróbel, Mark R. Gilbert, Andrey Litnovsky, Felix Klein, Krzysztof J. Kurzydłowski, Duc Nguyen-Manh

“…W-Cr-Y smart alloys are potential material candidates for plasma facing components due to their protective behaviour during the loss-of-coolant accident (LOCA), while maintaining beneficial properties of W during the normal operation of the fusion power plant. During plasma exposure, the lighter alloying elements are preferentially sputtered at the surface, but in case of a LOCA, the plasma quenches and sputtering stops and diffusion of the alloying elements to the surface becomes intensive. …”
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Development of accelerator based spatially resolved ion beam analysis techniques for the study of plasma materials interactions in magnetic fusion devices by Barnard, Harold Salvadore

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Changeover between helium and hydrogen fueled plasmas in JET and WEST by T. Wauters, R. Bisson, E. Delabie, D. Douai, A. Gallo, J. Gaspar, I. Jepu, Y. Kovtun, E. Pawelec, D. Matveev, A. Meigs, S. Brezinsek, I. Coffey, T. Dittmar, N. Fedorczak, J. Gunn, A. Hakola, P. Jacquet, K. Kirov, E. Lerche, J. Likonen, E. Litherland-Smith, T. Loarer, P. Lomas, C. Lowry, M. Maslov, I. Monakhov, J. Morales, C. Noble, R. Nouailletas, B. Pégourié, C. Perez von Thun, R.A. Pitts, C. Reux, F. Rimini, H. Sheikh, S. Silburn, H. Sun, D. Taylor, E. Tsitrone, S. Vartanian, E. Wang, A. Widdowson

“…The pre-fusion power operation (PFPO) phase of ITER, as described in the ITER research plan with Staged Approach,22 ITER Organization, “ITER Research Plan within the Staged Approach,” ITR-18–003, Aug. 2018. includes both hydrogen (H) and helium (He) plasma operations. …”
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Controlling implosion symmetry around a deuterium-tritium target by Norreys, P

“…Fusion power is a step closer with the demonstration of control over the extreme thermal radiation pressure created by high-power laser beams within a cavity.…”

Automatic identification of edge localized modes in the DIII-D tokamak by Finn H. O’Shea, Semin Joung, David R. Smith, Ryan Coffee

“…Fusion power production in tokamaks uses discharge configurations that risk producing strong type I edge localized modes. …”
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Status, Features, and Future Development of the LIFUS5/Mod4 Experimental Facility Design by Nicolò Badodi, Marica Eboli, Antonio Cammi, Alessandro Del Nevo

“…The Water-Cooled Lithium–Lead (WCLL) is one of the most promising technologies for power conversion and tritium production in future fusion-powered reactors; it will be implemented in one of the Test Breeding Modules (TBM) inside the ITER reactor and the DEMO EU reactor. …”
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Recent advances towards a lithium vapor box divertor by R.J. Goldston, A. Hakim, G.W. Hammett, M.A. Jaworski, J. Schwartz

“…Fusion power plants are likely to require near complete detachment of the divertor plasma from the divertor target plates, in order to have both acceptable heat flux at the target to avoid prompt damage and also acceptable plasma temperature at the target surface, to minimize long-term erosion. …”
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