Preparation and Examination of Beryllium Carbide

Mallett, M. W.; Durbin, E.A.; Udy, Murray C.; Vaughan, D. A.; E.J., None Center,

doi:10.1149/1.2781251

Cited by 20 publications

(3 citation statements)

References 1 publication

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“…Its aim is to adjust the opacity, which keep x-ray flux and suprathermal electrons from preheating the inner DT ice layer, and ensure the hot spot with a low entropy compress before implosion. Moreover, the graded Cu-doped Be has less sensitivity to perturbations, which helps to reduce Rayleigh–Taylor instability during implosion [11, 19, 26, 30] . Due to the small Be atom radius, most elements are fully immiscible with Be each other.…”

Section: Be–cu Capsulementioning

confidence: 99%

“…As for another Be-based material, ablator, is considered as an excellent potential target ablator because it combines the advantages of both hydrocarbon and Be, and achieves a more balanced ablation performance [16, 17] . It owns the lower atomic number ( ), and the higher density ( ) and mechanical strength than many hydrocarbons [18, 19] . Xie et al.…”

Section: Introductionmentioning

confidence: 99%

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An investigation progress toward Be-based ablator materials for the inertial confinement fusion

Luo

Zhang

et al. 2017

High Pow Laser Sci Eng

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The Be-based materials with many particular properties lead to an important research subject. The investigation progresses in the fabrication technologies are introduced here, including main three kinds of Be-based materials, such as Be-Cu capsule, Be 2 C ablator and high-purity Be material. Compared with the pioneer workgroup on Be-based materials, the differences in Be-Cu target fabrication were described, and a grain refinement technique by an active hydrogen reaction for Be coating was proposed uniquely. Be 2 C coatings were first prepared by the DC reactive magnetron sputtering with a high deposition rate (∼300 nm/h). Pure polycrystalline Be 2 C films with uniform microstructures, smooth surface, high density (∼2.2 g · cm 3 ) and good optical transparency were fabricated. In addition, the high-purity Be materials with metal impurities in a ppm magnitude were fabricated by the pyrolysis of organometallic Be.

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Section: Be–cu Capsulementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

An investigation progress toward Be-based ablator materials for the inertial confinement fusion

Luo

Zhang

et al. 2017

High Pow Laser Sci Eng

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“…При взаимодействии карбида бериллия с водой возможно также образование ацетилена [14,15]. Если метан самовоспламеняется в воздухе при температуре 810 К, то для ацетилена эта температура равна 608 К [16].…”

Section: взаимодействие карбида бериллия с водяным паром и газамиunclassified

Carbon — Beryllium Interaction and Its Possible Consequences

Kolbasov¹,

Davydov²,

Kholopova³

2011

PAST-TF

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При работе Международного термоядерного экспериментального реактора ИТЭР в результате взаимодействия плазмы с первой стенкой будет образовываться бериллиевая пыль, которая будет мигрировать в дивертор и оседать на углеродных элементах внутренней стороны дивертора. Измерения на токамаке JET показали, что атомное отношение Ве/С в плёнках, переосаждённых на эти пластины, иногда превышает 3. Образование таких бериллиево-углеродных плёнок может уменьшить химическую эрозию углеродных элементов дивертора и удержание трития при его соосаждении с образующейся углеродной пылью. При температуре более 900 К возможно образование карбида бериллия, что чревато заметным увеличением термического сопротивления обращённых к плазме элементов дивертора и возможностью образования метана и ацетилена при некоторых авариях. Ключевые слова: бериллий, углерод, карбид бериллия, окисление, образование водорода. CARBON-BERYLLIUM INTERACTION AND ITS POSSIBLE CONSEQUENCES. B.N. KOLBASOV, D.A. DAVYDOV, O.V. KHOLOPOVA. Beryllium dust will be formed during operation of the International Thermonuclear Experimental Reactor (ITER), resulting from the interaction of plasma with the first wall. This dust will migrate into divertor and deposit on carbon tiles of inner divertor side. Measurements in JET revealed that atomic ratio Be/C in the films re-deposited on these tiles exceeds 3. Formation of such Be-C-films can decrease chemical erosion of carbon tiles and tritium retention at its co-deposition with carbon dust. At temperature above 900 K formation of beryllium carbide is possible. It leads to the increase of thermal resistance of plasma facing elements and to the possibility of methane and acetylene formation at some accidents.

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Constitution of Beryllium and Its Alloys

Aldinger¹,

Petzow²

1979

Beryllium Science and Technology

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Preparation and Examination of Beryllium Carbide

Cited by 20 publications

References 1 publication

An investigation progress toward Be-based ablator materials for the inertial confinement fusion

An investigation progress toward Be-based ablator materials for the inertial confinement fusion

Carbon — Beryllium Interaction and Its Possible Consequences

Constitution of Beryllium and Its Alloys

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