Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor von Vityuk, V. A., Vurim, A. D., Kotov, V. M., Pakhnits, A. V.

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Development Of Scenarios For Controlling The Fuel Campaign Of The Ivg.1M Reactor With Leu-Fuel von Zhanbolatov, O. M., Vurim, A. D., Surayev, A. S., Irkimbekov, R. A.

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Neutronics Model of the IVG.1M Reactor: Development and Critical-State Verification von Irkimbekov, R. A., Zhagiparova, L. K., Kotov, V. M., Vurim, A. D., Gnyrya, V. S.

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Work Safety During Purification of Irradiated Beryllium by Chlorination von Baklanova, Yu Yu, Vurim, A D, Kotov, VM, Surayev, A S, Prozorova, I V

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Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor von Kaplienko, A. V., Lemekhov, V. V., Cherepnin, Yu. S., Moiseyev, A. V., Zhirnov, A. P., Ivanyuta, A. N., Rozhdestvenskiy, I. M., Loginov, D. Yu, Mezhina, Ye. R., Izhutov, A. L., Zvir, Ye. A., Shevlyakov, G. V., Volkova, I. N., Batyrbekov, Ye. G., Baklanov, V. V., Korovikov, A. G., Kotlyar, A. N., Miller, A. A., Irkimbekov, R. A., Vurim, A. D.

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Identification of the fuel parts of research reactors von Gorin, N. V., Churikov, Yu. I., Shcherbina, A. N., Bobylev, A. I., Rovnyi, S. I., Arkhangel’skii, N. V., Komkov, O. V., Pavshuk, V. A., Vurim, A. D., Gaidaichuk, V. A.

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Feasibility study mixed oxide fuel tests in the impulse graphite reactor von Vityuk, G. A., Vityuk, V. A., Vurim, A. D., Skakov, M. K., Gradoboyev, A. V.

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Experimental studies on the upward fuel discharge for elimination of severe recriticality during core-disruptive accidents in sodium-cooled fast reactors von Kamiyama, Kenji, Konishi, Kensuke, Sato, Ikken, Toyooka, Jun-ichi, Matsuba, Ken-ichi, Zuyev, Vladimir A., Pakhnits, Alexander V., Vityuk, Vladimir A., Vurim, Alexander D., Gaidaichuk, Valery A., Kolodeshnikov, Alexander A., Vassiliev, Yuri S.

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Investigation of the neutron field in the central channel of a pulse graphite reactor when the neutron absorber moves von GORIN, N. V, KANDIEV, Yu. Z, SKIVKA, A. S, KOZYBAEV, R. M, RUKAVISHNIKOV, G. V, VASILIEV, A. P, VURIM, A. D, GAIDAICHUK, V. A, KAZ'MIN, Yu. M, KOLTYSHEV, S. M, PAKHNITS, V. A

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Identification of the fuel parts of research reactors von GORIN, N. V, CHURIKOV, Yu. I, SHCHERBINA, A. N, BOBYLEV, A. I, ROVNYI, S. I, ARKHANGEL'SKII, N. V, KOMKOV, O. V, PAVSHUK, V. A, VURIM, A. D, GAIDAICHUK, V. A

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Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel von Irkimbekov, Ruslan А., Surayev, Artur S., Vityuk, Galina А., Zhanbolatov, Olzhas M., Kozhabaev, Zamanbek B., Bedenko, Sergey V., Ghal-Eh, Nima, Vurim, Alexander D.

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Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel von Ruslan А. Irkimbekov, Artur S. Surayev, Galina А. Vityuk, Olzhas M. Zhanbolatov, Zamanbek B. Kozhabaev, Sergey V. Bedenko, Nima Ghal-Eh, Alexander D. Vurim

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Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel von Irkimbekov, Ruslan А., Vurim, Alexander D., Bedenko, Sergey V., Vlaskin, Gennady N., Surayev, Artur S., Vityuk, Galina А., Vega-Carrillo, Hector R.

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Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor von Irkimbekov, Ruslan A., Vurim, Aleksandr D., Bedenko, Sergey V., Surayev, Artur S., Vityuk, Galina A.

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Temperature Dependence of Thermophysical Properties of Full-Scale Corium of Fast Energy Reactor von Deryavko, Ilya I., Vurim, Alexander D., Mukhamedov, Nurzhan Ye, Skakov, Mazhyn K.

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The result of a wall failure in-pile experiment under the EAGLE project von Konishi, Kensuke, Toyooka, Jun-Ichi, Kamiyama, Kenji, Sato, Ikken, Kubo, Shigenobu, Kotake, Shoji, Koyama, Kazuya, Vurim, Alexander D., Gaidaichuk, Valery A., Pakhnits, Alexander V., Vassiliev, Yuri S.

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