Search Results - "Skupov, M.V."

Thermogravimetric study of mixed uranium-plutonium fuel for prospective generation IV reactors by Krivov, M.P., Kireev, G.A., Tenishev, A.V., Davydov, A.V., Skupov, M.V., Solomatin, I.D., Mosunova, N.A., Usov, E.V., Chukhno, V.I.

“…The analysis of the accidental regime of the MNIT fuel reactor facility has indicated a possible scenario of decomposition of the fuel composition with the…”
Get full text

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.

“…•Materials, irradiation parameters and research methods.•Fuel pins with nitride fuel irradiated in the BN-600 reactor.•Fuel pins with nitride fuel irradiated…”
Get full text

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.

“…•Experimental research of out-of-pile properties of the mixed nitride.•Reactor tests.•Post-irradiation examinations.•Development of methods, codes and criteria…”
Get full text

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.

“…•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 –…”
Get full text

Technologies of Np, Am Afterburning in Fast Reactors with Mixed Uranium-Plutonium Nitride Fuel by Khomyakov, Yu.S., Mochalov, Yu.S., Zherebtsov, A. A., Egorov, A. V., Vidanov, V. L., Vlaskin, G. N., Skupov, M. V., Shadrin, A. Yu

“…The danger of the wastes from the reprocessing of spent nuclear fuel is largely determined by the presence in them of long-lived actinides, first of all,…”
Get full text

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.

“…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…”
Get full text

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.

“…ETVS fuel assemblies containing nitride fuel rods with different structural implementation and cladding made of different materials are tested in the cores of…”
Get full text

Key Outcomes of Comprehensive Computational and Experimental Validation of Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel for the BN-1200 and Brest Reactors by Adamov, E. O., Grachev, A. F., Zabudko, L. M., Lachkanov, E. V., Mochalov, Yu. S., Belyaeva, A. V., Kryukov, F. N., Ivanov, Yu. A., Skupov, M. V., Marinenko, E. E., Porollo, S. I.

“…The purpose of the program was to validate the resource dependability of fuel rods with mixed uranium-plutonium nitride fuel, the consistency of the…”
Get full text

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.

“…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…”
Get full text

Some Thermodynamic Features of Uranium–Plutonium Nitride Fuel in the Course of Burnup by Rusinkevich, A. A., Ivanov, A. S., Belov, G. V., Skupov, M. V.

“…Calculation studies on the effect of carbon and oxygen impurities on the chemical and phase compositions of nitride uranium–plutonium fuel in the course of…”
Get full text

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.

“…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…”
Get full text

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.

“…The complex program of computational and experimental validation of dense fuel for fast reactors in Project Breakthrough provides for testing of fuel rods with…”
Get full text

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.

“…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…”
Get full text

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.

“…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…”
Get full text

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.

“…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…”
Get full text

Comparison of Closed Nuclear Fuel Cycle Technologies by Shadrin, A. Yu, Ivanov, V. B., Skupov, M. V., Troyanov, V. M., Zherebtsov, A. A.

“…The aim of this work is to compare different approaches to nuclear fuel cycle closure from the standpoint of plutonium utilization, fuel type, and reprocessing…”
Get full text

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.

“…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…”
Get full text

Program and Some Results of Pre-Reactor Studies of Mixed Uranium-Plutonium Nitride Fuel for Fast Reactors by Troyanov, V. M., Grachev, A. F., Zabud’ko, L. M., Skupov, M. V., Kireev, G. A.

“…For future nuclear power with fast reactors with sodium (BN-1200) and lead (BREST) as coolants, plans are being made to use mixed uranium-plutonium nitride…”
Get full text

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.

“…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 ,…”
Get full text