Initial tritium waste management criteria and assessment for ITER von Ionesyan, IA, Kapychev, V K, Tebus, V N, Frolov, V N

Volltext

Prospects and problems using vanadium alloys as a structural material of the first wall and blanket of fusion reactors von 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.

Volltext

Initial tritium waste management criteria and assessment for ITER von Ionesyan, I.A., Kapychev, V.K., Tebus, V.N., Frolov, V.N.

Volltext

Models of Ceramic Tritium Breeding Zones in the Blanket of a Thermonuclear Reactor von Gorokhov, V A, Gryaznov, N S, Davydov, D A, Ioltukhovskii, A G, Kazennov, Yu I, Kapyshev, V K, Medvedeva, E A, Minaev, A V, Tebus, V N, Frolov, V N, Shikov, A K, Shishkov, N V, Kovalenko, V G, Marachev, A V, Strebkov, Yu S

Volltext

Separation of tritium from lithium by nonequilibrium molecular reflux distillation von Tebus, V. N., Petrov, B. V., Klabukov, Yu. G., Voloshin, L. A.

Volltext

Hydrogen isotopes mobility and trapping in VCrTi alloys von Budylkin, N., Voloschin, L., Mironova, E., Riazantseva, N., Tebus, V.

Volltext

Hydrogen isotope interaction with V-alloys von Zaluzhnyi, A.G., Tebus, V.N., Riazantseva, N.N., Kopytin, V.N., Voloshin, L.A., Torubarov, D.I., Cherednichenko-Alchevski, M.V.

Volltext

Separation of tritium from lithium by nonequilibrium molecular reflux distillation von TEBUS, V. N, PETROV, B. V, KLABUKOV, Yu. G, VOLOSHIN, L. A

Volltext

Metallic tritium-producing materials for the iter blanket von Tebus, V. N., Petrov, B. V., Romanov, P. V., Klabukov, Yu. G., Aksenov, B. S., Shipilov, V. V.

Volltext

Influence of irradiation on structure and properties of lithium-lead eutectic — Possible material for ITER reactor blanket von Tebus, V.N., Sokursky, Yu.N., Lukashin, S.V., Panteleev, L.D., Ovechkin, V.V., Bylkin, B.I., Filin, V.M., Bochvar, A.A.

Volltext

Behavior of helium in aluminum under the conditions of hydrostatic compression von Sokurskii, Yu. N., Tebus, V. N., Zudilin, V. A., Tumanova, G. M.

Volltext

Hydrogen isotope interaction with V-alloys von Zaluzhnyi, A G, Tebus, V N, Riazantseva, N N, Kopytin, V N, Voloshin, LA, Torubarov, DI, Cherednichenkco-Alchevski, M V

Volltext

Effect of irradiation with helium ions and subsequent annealings on the crystal structure of alpha titanium von Alekseev, . F., Panteleev, L. D., Sokolov, A. D., Tebus, V. N., Chuev, V. I.

Volltext

A study of tritium release and permeability under in-pile irradiation of Li-Pb eutectic von Tebus, V. N., Demidov, V. V., Zyrianov, A. P., Zakhartsev, V. S., Antonov, A. G.

Volltext

Hydrogen isotope interaction with V-alloys von Zaluzhnyi, A G, Tebus, V N, Riazantseva, N N, Kopytin, V N, Voloshin, L A, Torubarov, D I, Cherednichenko-Alchevski, M V

Volltext

Problem of helium in the structural materials of a thermonuclear reactor von Nikiforov, A. S., Zakharov, A. P., Chuev, V. I., Zaluzhnyi, A. G., Sokurskii, Yu. N., Onufriev, V. D., Tebus, V. N., Gorodetskii, A. E., Alimov, V. Kh, Al'tovskii, I. V., Cherednichenko-Alchevskii, V. M.

Volltext

Hydrogen isotopes mobility and trapping in V Cr Ti alloys von Budylkin, N., Voloschin, L., Mironova, E., Riazantseva, N., Tebus, V.

Volltext

Initial tritium waste management criteria and assessment for ITER von IONESYAN, I. A, KAPYCHEV, V. K, TEBUS, V. N, FROLOV, V. N

Volltext

Hydrogen isotope interaction with V-alloys von ZALUZHNYI, A. G, TEBUS, V. N, RIAZANTSEVA, N. N, KOPYTIN, V. N, VOLOSHIN, L. A, TORUBAROV, D. I, CHEREDNICHENKO-ALCHEVSKI, M. V

Volltext

Models of ceramic tritium breeding zones in the blanket of a thermonuclear reactor von GOROKHOV, V. A, GRYAZNOV, N. S, SHIKOV, A. K, SHISHKOV, N. V, KOVALENKO, V. G, MARACHEV, A. V, STREBKOV, Yu. S, DAVYDOV, D. A, IOLTUKHOVSKII, A. G, KAZENNOV, Yu. I, KAPYSHEV, V. K, MEDVEDEVA, E. A, MINAEV, A. V, TEBUS, V. N, FROLOV, V. N

Volltext