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Verification of the EUCLID/V2 Code Based on Experiments Involving Destruction of a Liquid Metal Cooled Reactor’s Core Components
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Lobanov P., Mosunova N., Sorokin A., Strizhov V., Usov E., Chukhno V.
Topical Problems Concerned with the Thermophysical Characteristics of New-Generation Light Water Reactors: Comprehensive Study Results
Sorokin A., Kuzina Y., Trufanov A., Loshchinin V., Levchenko Y., Morozov A.
Estimation of thermal loads on the VVER vessel under conditions of inversion of the stratified molten pool in a severe accident
Loktionov V., Mukhtarov E.
Thermodynamic Simulation of Equilibrium Composition of Reaction Products at Dehydration of a Technological Channel in a Uranium-Graphite Reactor
Pavliuk A., Zagumennov V., Kotlyarevskiy S., Bespala E.
Analysis and selection of high pressure heaters design for a new generation of NPP with BN-1200 reactor plant
Yurchenko A., Sukhorukov Y., Trifonov N., Grigor’eva E., Esin S., Svyatkin F., Nikolaenkova E., Prikhod’ko P., Nazarov V.
The EUCLID/V2 Code Physical Models for Calculating Fuel Rod and Core Failures in a Liquid Metal Cooled Reactor
Butov A., Zhdanov V., Klimonov I., Kudashov I., Kutlimetov A., Mosunova N., Strizhov V., Sorokin A., Frolov S., Usov E., Chukhno V.
New Technological Platform for the National Nuclear Energy Strategy Development
Adamov E., Rachkov V.
Procedure of calculation of the spatial distribution of temperatures and heat fluxes in the steam generator of a nuclear power installation with an RBEC fast-neutron reactor
Frolov A., Sedov A.
Cross-Verification of 1D and 3D Models for a VVER-1000 Reactor’s Pressure Chamber Simulated by the KORSAR/CFD Computation Code in the Modes with Asymmetric Loop Operation
Yudov Y., Petkevich I., Artemov V.
Experimental investigation of a new method for advanced fast reactor shutdown cooling
Pakholkov V., Kandaurov A., Potseluev A., Rogozhkin S., Sergeev D., Troitskaya Y., Shepelev S.
Experimental studies of local coolant hydrodynamics using a scaled model of cassette-type fuel assembly of a KLT-40S reactor
Dmitriev S., Barinov A., Varentsov A., Doronkov D., Solntsev D., Khrobostov A.
Three-Dimensional Simulation of a VVER-1000 Reactor’s Pressure Chamber in the Modes with Asymmetrical Loop Operation Using a KORSAR/CFD Computation Code
Yudov Y., Petkevich I., Artemov V., Kasterin D., Rumyantsev S.
On the Question of “Decisive Advantages” of Thermionic Conversion for Space Power Systems
Koroteev A.
Fast reactor: an experimental study of thermohydraulic processes in different operating regimes
Opanasenko A., Sorokin A., Zaryugin D., Trufanov A.
Modeling the transport of nitrogen in an NPP-2006 reactor circuit
Stepanov O., Galkin I., Sledkov R., Melekh S., Strebnev N.
Simulation of Heat and Mass Transfer in an Organic Compound Pyrolysis Reactor
Zroichikov N., Fadeev S., Kaverin A., Pai A.
The Challenging Thermophysical Issues of Fast Reactors
Sorokin A., Kuzina Y., Trufanov A., Kamaev A., Orlov Y., Alekseev V., Grabezhnaya V., Zagorul’ko Y.
Development of a thermal scheme for a cogeneration combined-cycle unit with an SVBR-100 reactor
Kasilov V., Dudolin A., Krasheninnikov S.
Purification of liquid metal systems with sodium coolant from oxygen using getters
Kozlov F., Konovalov M., Sorokin A.
Numerical Investigation of a Class of Accidents in the Generation IV Brest Reactor Involving the Formation of a Solid Phase in the Lead Coolant
Chistov A., Savikhin O., Ovchinnikov V., Kiryushina E.
The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification
Alipchenkov V., Boldyrev A., Veprev D., Zeigarnik Y., Kolobaeva P., Moiseenko E., Mosunova N., Seleznev E., Strizhov V., Usov E., Osipov S., Gorbunov V., Afremov D., Semchenkov A.
Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor
Khafizov R., Poplavskii V., Rachkov V., Sorokin A., Trufanov A., Ashurko Y., Volkov A., Ivanov E., Privezentsev V.
Modeling of corrosion product migration in the secondary circuit of nuclear power plants with WWER-1200
Kritskii V., Berezina I., Gavrilov A., Motkova E., Zelenina E., Prokhorov N., Gorbatenko S., Tsitser A.
Achieving More Efficient Removal of α-Emitting Radionuclides from the Primary Coolant in Propulsion Reactors
Orlov S., Zmitrodan A., Mysik S.
The Impact of Design Deviations on Dynamic Characteristics of a Flexible Multispan Rotor on Complete Electromagnetic Suspension
Ovchinnikov V., Nikolaev M., Litvinov V., Kodochigov N., Drumov I.
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