Search Results - "Zabudko, L.M."

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  1. 1

    Results of irradiation of (U0.55Pu0.45)N and (U0.4Pu0.6)N fuels in BOR-60 up to ∼12at.% burn-up by Rogozkin, B.D., Stepennova, N.M., Fedorov, Yu.Ye, Shishkov, M.G., Kryukov, F.N., Kuzmin, S.V., Nikitin, O.N., Belyaeva, A.V., Zabudko, L.M.

    Published in Journal of nuclear materials (01-09-2013)
    “…In the article presented are the results of post-irradiation tests of helium bonded fuel pins with mixed mononitride fuel (U0.55Pu0.45)N and (U0.4Pu0.6)N…”
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    Journal Article
  2. 2

    Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel by Grachev, A. F., Zabud’ko, L. M., Skupov, M. V., Kryukov, F. N., Teplov, V. G., Marinenko, E. E., Porollo, S. I.

    Published in Atomic energy (New York, N.Y.) (01-12-2020)
    “…The results of an investigation of fission gas release from mixed nitride fuel after irradiation to maximum burnup 7.5% h. a. in 10 experimental FA in BN-600…”
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    Journal Article
  3. 3

    Results of post-irradiation examinations of mixed nitride pins with gas and liquid metal sub-layers by Kryukov, F.N., Belyaeva, A.V., Skupov, M.V., Zabudko, L.M., Mochalov, Yu.S.

    Published in Nuclear engineering and design (01-12-2021)
    “…•Materials, irradiation parameters and research methods.•Fuel pins with nitride fuel irradiated in the BN-600 reactor.•Fuel pins with nitride fuel irradiated…”
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    Journal Article
  4. 4

    Status on performance study of mixed nitride fuel pins of BREST reactor type by Zabudko, L.M., Grachev, A.F., Zherebtsov, A.A., Lachkanov, E.V., Mochalov, Yu.S., Skupov, M.V., Ivanov, Yu.A., Kryukov, F.N., Zvir, E.A.

    Published in Nuclear engineering and design (01-12-2021)
    “…•Experimental research of out-of-pile properties of the mixed nitride.•Reactor tests.•Post-irradiation examinations.•Development of methods, codes and criteria…”
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  5. 5

    Development of technologies for production of fuel with minor actinides by Skupov, M.V., Glushenkov, A.E., Tarasov, B.A., Abramov, S.V., Kuzin, M.A., Nikitin, O.N., Zabudko, L.M., Grachev, A.F., Zherebtsov, A.A., Mochalov, Yu.S.

    Published in Nuclear engineering and design (01-10-2021)
    “…•The full use of the energy potential of uranium raw materials.•R&D program to involve MA in mixed nitride.•Production of mixed nitride fuel with MA –…”
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    Journal Article
  6. 6

    Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding by Porollo, S. I., Marinenko, E. E., Kryukov, F. N., Nikitin, O. N., Gilmutdinov, I. F., Zabudko, L. M., Grachev, A. F., Tarasov, B. A.

    Published in Atomic energy (New York, N.Y.) (01-12-2022)
    “…Post-reactor studies of experimental fuel pins with mixed nitride uranium-plutonium fuel and EP823-Sh, ChS68-ID kh.d., and EK164-ID kh.d. steel cladding, which…”
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    Journal Article
  7. 7

    Post-Reactor Studies of Fuel Rods with Uranium-Plutonium Nitride Fuel with Gas and Liquid-Metal Sublayer by Grachev, A. F., Zabudko, L. M., Mochalov, Yu. S., Belyaeva, A. V., Kryukov, F. N., Gilmutdinov, I. F., Skupov, M. V., Ivanov, Yu. A.

    Published in Atomic energy (New York, N.Y.) (01-04-2021)
    “…ETVS fuel assemblies containing nitride fuel rods with different structural implementation and cladding made of different materials are tested in the cores of…”
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    Journal Article
  8. 8
  9. 9

    Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer by Adamov, E. O., Zabud’ko, L. M., Mochalov, Yu. S., Rachkov, V. I., Khomyakov, Yu. S., Kryukov, F. N., Skupov, M. V.

    Published in Atomic energy (New York, N.Y.) (01-03-2020)
    “…The status of development work on fuel pins with fast-reactor nitride fuel and a liquid-metal sublayer, which is being considered in Project Breakthrough…”
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    Journal Article
  10. 10

    Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600 by Grachev, A. F., Zherebtsov, A. A., Zabud’ko, L. M., Zvir, E. A., Kryukov, F. N., Nikitin, O. N., Skupov, M. V., Ivanov, Yu. A., Porollo, S. I.

    Published in Atomic energy (New York, N.Y.) (01-03-2019)
    “…The complex program of computational and experimental validation of dense fuel for fast reactors in Project Breakthrough provides for testing of fuel rods with…”
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    Journal Article
  11. 11

    Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor by Porollo, S. I., Ivanov, S. N., Marinenko, E. E., Zabud’ko, L. M.

    Published in Atomic energy (New York, N.Y.) (01-04-2017)
    “…The results of an investigation of gas release and swelling of uranium mononitride fuel after irradiation in standard and experimental fuel assemblies in the…”
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    Journal Article
  12. 12

    Investigations of Mixed Uranium-Plutonium Nitride Fuel in Project Breakthrough by Grachev, A. F., Zabud’ko, L. M., Glushenkov, A. E., Ivanov, Yu. A., Kireev, G. A., Skupov, M. V., Gil’mutdinov, I. F., Grin’, P. I., Zvir, E. A., Kryukov, F. N., Nikitin, O. N.

    Published in Atomic energy (New York, N.Y.) (01-07-2017)
    “…Mixed uranium-plutonium nitride fuel is seen as a promising fuel for fast reactors with a closed fuel cycle. A complex program of computational and…”
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  13. 13

    Prospects for Using Nitride Fuel in Fast Reactors with a Closed Nuclear Fuel Cycle by Troyanov, V. M., Grachev, A. F., Zabud’ko, L. M., Skupov, M. V.

    Published in Atomic energy (New York, N.Y.) (01-12-2014)
    “…The present status of research on dense nitride fuel for liquid-metal cooled fast reactors is examined. It is noted that within the framework of project Proryv…”
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  14. 14

    Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors by Troyanov, V. M., Grachev, A. F., Zabud’ko, L. M., Skupov, M. V., Zozulya, D. V.

    Published in Atomic energy (New York, N.Y.) (01-06-2015)
    “…In the Proryv project, mixed uranium-plutonium nitride fuel is to be used in the future nuclear power with fast reactors with sodium coolant (BN-1200) and with…”
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  15. 15

    Results of [U.sub.0.55][Pu.sub.0.45]N and [U.sub.0.4][Pu.sub.0.6]N mixed mononitride fuel tests in a BOR-60 reactor to burnup 12% h.a by Rogozkin, B.D, Stepennova, N.M, Fedorov, Yu. E, Shishkov, M.G, Kryukov, F.N, Kuzmin, S.V, Nikitin, O.N, Belyaeva, A.V, Zabudko, L.M

    Published in Atomic energy (New York, N.Y.) (01-10-2011)
    “…The results of post-reactor studies of [U.sub.0.55][Pu.sub.0.45]N and [U.sub.0.4][Pu.sub.0.6]N mixed mononitride fuel elements (density 85% of the theoretical…”
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  16. 16

    Post-reactor studies of plutonium mononitride and oxide fuel with an inert matrix and burnup of about 19% h.a. in BOR-60 by Rogozkin, B. D., Stepennova, N. M., Fedorov, Yu. E., Shishkov, M. G., Kryukov, F. N., Kuzmin, S. V., Nikitin, O. N., Kurina, I. S., Zabudko, L. M., Noirot, J., Bejaoui, S.

    Published in Atomic energy (New York, N.Y.) (01-04-2011)
    “…An experiment investigating the behavior of different fuel compositions with high content of plutonium for the conditions of a BOR-60 reactor was performed in…”
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  17. 17

    Fuel for advanced sodium-cooled fast reactors: current status and plans by Poplavskii, V. M., Zabudko, L. M., Shkabura, I. A., Skupov, M. V., Bychkov, A. V., Kislyi, V. A., Kryukov, F. N., Vasiliev, B. A.

    Published in Atomic energy (New York, N.Y.) (01-08-2010)
    “…Different fuel compositions have been irradiated in the BR-10, BOR-60, BN-350, and BN-600 reactors and investigated: PuO 2 , UC, UN, UPuN, UO 2 , UPuO 2 ,…”
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  18. 18

    Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation by Grachev, A. F., Zabud’ko, L. M., Leont’eva-Smirnova, M. V., Naumenko, I. A., Kryukov, F. N., Chertopyatov, E. V., Marinenko, E. E., Porollo, S. I.

    Published in Atomic energy (New York, N.Y.) (01-10-2021)
    “…Irradiation of experimental fuel assemblies with uranium-plutonium nitride fuel and shells made of ferritic- martensitic steel EP823-Sh is conducted in order…”
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  19. 19

    Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer by Grachev, A. F., Zabud’ko, L. M., Belyaeva, A. V., Kryukov, F. N., Nikitin, O. N., Gil’mutdinov, I. F., Kozolup, A. N., Sagalov, S. S., Skupov, M. V., Ivanov, Yu. A.

    Published in Atomic energy (New York, N.Y.) (01-03-2021)
    “…Experimental fuel rods with mixed uranium-plutonium nitride fuel are being tested in the BOR-60 reactor as part of collapsible irradiation devices, which are…”
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  20. 20

    Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding by Grachev, A. F., Zabud’ko, L. M., Ivanov, Yu. A., Skupov, M. V., Zvir, E. A., Kryukov, F. N., Nikitin, O. N., Marinenko, E. E., Porollo, S. I.

    Published in Atomic energy (New York, N.Y.) (01-07-2019)
    “…Reactor tests in BN-600 and post-reactor studies of experimental FA of fuel rods with mixed nitride fuel and different cladding are being conducted in Project…”
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    Journal Article