Search Results - "Nuclear materials and energy"

Physics basis for the first ITER tungsten divertor by Pitts, R.A., Bonnin, X., Escourbiac, F., Frerichs, H., Gunn, J.P., Hirai, T., Kukushkin, A.S., Kaveeva, E., Miller, M.A., Moulton, D., Rozhansky, V., Senichenkov, I., Sytova, E., Schmitz, O., Stangeby, P.C., De Temmerman, G., Veselova, I., Wiesen, S.

“…•Reviews the fundamental physics aspects of the first ITER W divertor and defines the required operational lifetime within the Staged Approach.•Uses the ITER…”
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Use of tungsten material for the ITER divertor by Hirai, T., Panayotis, S., Barabash, V., Amzallag, C., Escourbiac, F., Durocher, A., Merola, M., Linke, J., Loewenhoff, Th, Pintsuk, G., Wirtz, M., Uytdenhouwen, I.

“…Since the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as…”
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Additive manufacturing of pure tungsten by means of selective laser beam melting with substrate preheating temperatures up to 1000 ∘C by Müller, A. v., Schlick, G., Neu, R., Anstätt, C., Klimkait, T., Lee, J., Pascher, B., Schmitt, M., Seidel, C.

“…•Investigations regarding additive manufacturing of pure tungsten by means of selective laser beam melting are presented.•Results for material fabricated with…”
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European divertor target concepts for DEMO: Design rationales and high heat flux performance by You, J.H., Visca, E., Barrett, T., Böswirth, B., Crescenzi, F., Domptail, F., Fursdon, M., Gallay, F., Ghidersa, B-E., Greuner, H., Li, M., Müller, A.v., Reiser, J., Richou, M., Roccella, S., Vorpahl, Ch

“…•The European approaches for DEMO divertor target R&D and the recent progress achieved in the divertor project (WPDIV) of the EUROfusion Consortium are…”
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ELM divertor peak energy fluence scaling to ITER with data from JET, MAST and ASDEX upgrade by Eich, T., Sieglin, B., Thornton, A.J., Faitsch, M., Kirk, A., Herrmann, A., Suttrop, W.

“…A newly established scaling of the ELM energy fluence using dedicated data sets from JET operation with CFC & ILW plasma facing components (PFCs), ASDEX…”
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Physics conclusions in support of ITER W divertor monoblock shaping by Pitts, R.A., Bardin, S., Bazylev, B., van den Berg, M.A., Bunting, P., Carpentier-Chouchana, S., Coenen, J.W., Corre, Y., Dejarnac, R., Escourbiac, F., Gaspar, J., Gunn, J.P., Hirai, T., Hong, S-H., Horacek, J., Iglesias, D., Komm, M., Krieger, K., Lasnier, C., Matthews, G.F., Morgan, T.W., Panayotis, S., Pestchanyi, S., Podolnik, A., Nygren, R.E., Rudakov, D.L., De Temmerman, G., Vondracek, P., Watkins, J.G.

“…•Focus is on protection of leading edges between toroidally adjacent monoblocks.•Summarizes conclusions of coordinated, multi-device ITPA Divertor and SOL…”
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Analytical expressions for thermophysical properties of solid and liquid tungsten relevant for fusion applications by Tolias, P.

“…•Review and critical assessment of experimental results.•High accuracy analytical fits involving a minimum degree of extrapolations.•Standardization of basic…”
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Hydrogen permeation barriers: Basic requirements, materials selection, deposition methods, and quality evaluation by Nemanič, Vincenc

“…•Permeation reduction of gaseous hydrogen through metal membranes.•Coating techniques for preparation of well adhered and perfect hydrogen barriers.•Classical…”
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European DEMO divertor target: Operational requirements and material-design interface by You, J.H., Visca, E., Bachmann, Ch, Barrett, T., Crescenzi, F., Fursdon, M., Greuner, H., Guilhem, D., Languille, P., Li, M., McIntosh, S., Müller, A.V., Reiser, J., Richou, M., Rieth, M.

“…•An overview is given on the work program of the EUROfusion project ‘divertor target’.•Operational requirements, structural design rationale and…”
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Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET by Bernert, M., Wischmeier, M., Huber, A., Reimold, F., Lipschultz, B., Lowry, C., Brezinsek, S., Dux, R., Eich, T., Kallenbach, A., Lebschy, A., Maggi, C., McDermott, R., Pütterich, T., Wiesen, S.

“…•Stable operation with fully detached targets in all-metal devices demonstrated•Power exhaust achieved at highest heat fluxes with impurity seeding of N, Ne…”
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Study on irradiation effects of refractory bcc high-entropy alloy by Zong, Yun, Hashimoto, Naoyuki, Oka, Hiroshi

“…•Refractory HEAs exhibit high thermal stabilities after heat-treatment.•The irradiation hardening of MoNbTaTiW is smaller than that of MoNbTaTi.•Refractory…”
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Broadening of the power fall-off length in a high density, high confinement H-mode regime in ASDEX Upgrade by Faitsch, M., Eich, T., Harrer, G.F., Wolfrum, E., Brida, D., David, P., Griener, M., Stroth, U.

“…The search for scenarios in which tolerable power exhaust is combined with good confinement must involve high separatrix densities. We present here the first…”
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Recrystallization behavior of hot-rolled pure tungsten and its alloy plates during high-temperature annealing by Tsuchida, Kohei, Miyazawa, Takeshi, Hasegawa, Akira, Nogami, Shuhei, Fukuda, Makoto

“…•We conducted isothermal and isochronous annealing, electron backscatter diffraction observations and Vickers hardness test.•We observed the change of the…”
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Divertor closure effects on the TCV boundary plasma by Février, O., Reimerdes, H., Theiler, C., Brida, D., Colandrea, C., De Oliveira, H., Duval, B.P., Galassi, D., Gorno, S., Henderson, S., Komm, M., Labit, B., Linehan, B., Martinelli, L., Perek, A., Raj, H., Sheikh, U., Tsui, C.K., Wensing, M.

“…The Tokamak à Configuration Variable (TCV) has recently been equipped with gas baffles to increase its divertor closure for a broad range of divertor magnetic…”
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The high field side high density region in SOLPS-modeling of nitrogen-seeded H-modes in ASDEX Upgrade by Reimold, F., Wischmeier, M., Potzel, S., Guimarais, L., Reiter, D., Bernert, M., Dunne, M., Lunt, T.

“…The understanding of divertor physics and the evolution of divertor detachment is crucial for developing the capability to model power exhaust in current…”
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Additive manufacturing of high density pure tungsten by electron beam melting by Dorow-Gerspach, D., Kirchner, A., Loewenhoff, Th, Pintsuk, G., Weißgärber, T., Wirtz, M.

“…[Display omitted] •Nearly-crack free bulk material with theoretical density above 99% was produced.•Transition regime between sintering, partial, and complete…”
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Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding by Dabney, Tyler, Johnson, Greg, Yeom, Hwasung, Maier, Ben, Walters, Jorie, Sridharan, Kumar

“…•Two FeCrAl alloys were deposited onto Zircaloy-4 substrates via cold spray process.•Corrosion/oxidation tests for FeCrAl alloys coated samples at 400 °C steam…”
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A study of the influence of plasma–molecule interactions on particle balance during detachment by Verhaegh, Kevin, Lipschultz, Bruce, Harrison, James, Duval, Basil, Bowman, Chris, Fil, Alexandre, Gahle, Daljeet Singh, Moulton, David, Myatra, Omkar, Perek, Artur, Theiler, Christian, Wensing, Mirko

“…In this work we provide experimental insights into the impact of plasma–molecule interactions on the target ion flux decrease during divertor detachment…”
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Prospects of core–edge integrated no-ELM and small-ELM scenarios for future fusion devices by Viezzer, E., Austin, M.E., Bernert, M., Burrell, K.H., Cano-Megias, P., Chen, X., Cruz-Zabala, D.J., Coda, S., Faitsch, M., Février, O., Gil, L., Giroud, C., Happel, T., Harrer, G.F., Hubbard, A.E., Hughes, J.W., Kallenbach, A., Labit, B., Merle, A., Meyer, H., Paz-Soldan, C., Oyola, P., Sauter, O., Siccinio, M., Silvagni, D., Solano, E.R.

“…One of our grand challenges towards fusion energy is the achievement of a high-performance plasma core coupled to a boundary solution. The high confinement…”
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Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application by Aghamiri, S.M.S., Oono, N., Ukai, S., Kasada, R., Noto, H., Hishinuma, Y., Muroga, T.

“…•A new ODS copper alloy including 0.42wt%Y2O3 particles was developed successfully by MA method.•MA resulted in decrease of crystallite size and increment of…”
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