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Search Results - Tebus, V.N.
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Prospects and problems using vanadium alloys as a structural material of the first wall and blanket of fusion reactors
by
Votinov, S.N.
,
Solonin, M.I.
,
Kazennov, Yu.I.
,
Kondratjev, V.P.
,
Nikulin, A.D.
,
Tebus, V.N.
,
Adamov, E.O.
,
Bougaenko, S.E.
,
Strebkov, Yu.S.
,
Sidorenkov, A.V.
,
Ivanov, V.B.
,
Kazakov, V.A.
,
Evtikhin, V.A.
,
Lyublinski, I.E.
,
Trojanov, V.M.
,
Rusanov, A.E.
,
Chernov, V.M.
,
Birgevoj, G.A.
Published in
Journal of nuclear materials
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Initial tritium waste management criteria and assessment for ITER
by
Ionesyan, I.A.
,
Kapychev, V.K.
,
Tebus, V.N.
,
Frolov, V.N.
Published in
Fusion Engineering and Design
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Hydrogen isotope interaction with V-alloys
by
Zaluzhnyi, A.G.
,
Tebus, V.N.
,
Riazantseva, N.N.
,
Kopytin, V.N.
,
Voloshin, L.A.
,
Torubarov, D.I.
,
Cherednichenko-Alchevski, M.V.
Published in
Fusion engineering and design
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Influence of irradiation on structure and properties of lithium-lead eutectic — Possible material for ITER reactor blanket
by
Tebus, V.N.
,
Sokursky, Yu.N.
,
Lukashin, S.V.
,
Panteleev, L.D.
,
Ovechkin, V.V.
,
Bylkin, B.I.
,
Filin, V.M.
,
Bochvar, A.A.
Published in
Fusion engineering and design
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