Search Results - "Zabudko, L.M."
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Results of irradiation of (U0.55Pu0.45)N and (U0.4Pu0.6)N fuels in BOR-60 up to ∼12at.% burn-up
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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Fission Gas Release from Irradiated Uranium-Plutonium Nitride Fuel
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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Results of post-irradiation examinations of mixed nitride pins with gas and liquid metal sub-layers
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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Status on performance study of mixed nitride fuel pins of BREST reactor type
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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Development of technologies for production of fuel with minor actinides
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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Nitriding and Carburization of a Mixed Nitride Uranium-Plutonium Fuel Pin Cladding
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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Post-Reactor Studies of Fuel Rods with Uranium-Plutonium Nitride Fuel with Gas and Liquid-Metal Sublayer
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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Key Outcomes of Comprehensive Computational and Experimental Validation of Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel for the BN-1200 and Brest Reactors
Published in Atomic energy (New York, N.Y.) (01-03-2022)“…The purpose of the program was to validate the resource dependability of fuel rods with mixed uranium-plutonium nitride fuel, the consistency of the…”
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Development of Fuel Pin with Uranium-Plutonium Nitride Fuel and Liquid-Metal Sublayer
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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Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600
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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Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor
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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Investigations of Mixed Uranium-Plutonium Nitride Fuel in Project Breakthrough
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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Prospects for Using Nitride Fuel in Fast Reactors with a Closed Nuclear Fuel Cycle
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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Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors
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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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
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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Post-reactor studies of plutonium mononitride and oxide fuel with an inert matrix and burnup of about 19% h.a. in BOR-60
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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Fuel for advanced sodium-cooled fast reactors: current status and plans
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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Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation
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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Features of Radiation Swelling of Uranium-Plutonium Nitride Fuel in Experimental Fuel Rods with Helium and Lead Sublayer
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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Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding
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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