Atomic Energy
ISSN 1063-4258 (Print)
ISSN 1573-8205 (Online)
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Keywords
Benchmark Experiment
Beryllium
Emergency Protection
Fuel Assembly
Fuel Element
Heat Transfer
Heavy Water
Irradiation Dose Rate
Moscow Engineer Physics Institute
National Research Center Kurchatov Institute
Neutron Spectrum
Normal Operating Condition
Plutonium
Radionuclide
Radon
Spend Fuel
Spend Nuclear Fuel
Steam Generator
Tritium
Uranium
Uranium Dioxide
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Keywords
Benchmark Experiment
Beryllium
Emergency Protection
Fuel Assembly
Fuel Element
Heat Transfer
Heavy Water
Irradiation Dose Rate
Moscow Engineer Physics Institute
National Research Center Kurchatov Institute
Neutron Spectrum
Normal Operating Condition
Plutonium
Radionuclide
Radon
Spend Fuel
Spend Nuclear Fuel
Steam Generator
Tritium
Uranium
Uranium Dioxide
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Author Details
Author Details
Butov, A. A.
Issue
Section
Title
File
Vol 122, No 5 (2017)
Article
HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600 Experiments
Vol 124, No 3 (2018)
Article
Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code
Vol 124, No 4 (2018)
Article
SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident
Vol 124, No 5 (2018)
Article
Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor
Vol 124, No 6 (2018)
Article
Verification of Analytical Test Based Thermohydraulic Systems Codes for One- and Two-Phase Liquid-Metal Flows
Vol 127, No 1 (2019)
Article
3D EVKLID/V2 Code Aided Simulation of Severe Accidents
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