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1
Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel
Published 1999“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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2
Modification of IPSN's SCANAIR fuel rod transient code for high burnup VVER fuel
Published 1999“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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3
Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma by Vinogradov, V. A.
Published 2002“…Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut."…”
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4
Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA by Vinogradov, V. A.
Published 2001“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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5
Experimental study on the combustion behavior of hydrogen-air mixtures with turbulent jet ignition at large scale
Published 1993“…Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut."…”
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6
Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 by Vinogradov, V. A.
Published 1999“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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7
Analysis of pin-by-pin effects for LWR rod ejection accident by Avvakumov, A.
Published 2000“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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8
Assessment study of RELAP5/MOD3.2 based on the Kalinin NPP unit-1 stop of feedwater supply to the steam generator no. 4 by Pylev, S. S. (Stanislav Semenovich)
Published 1999“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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9
Assessment of RELAP5/MOD3.2 for thermohydraulic processes in heated rod bundles with tight lattice at CKTI Test Facility by Devkin, A. S.
Published 1999“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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10
Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions
Published 1999“…Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut."…”
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11
Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding
Published 2003“…Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut."…”
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12
Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding procedures and results of low temperature biaxial burst tests and axial tensile tests /
Published 2001“…(Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut")…”
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Related Subjects
Computer simulation
Nuclear fuel rods
Nuclear fuel claddings
Thermal properties
Computer programs
Loss of coolant
Nuclear reactor accidents
Pressurized water reactors
Testing
Accidents
Analysis
Combustion, Spontaneous
Effect of radiation on
Experiments
Exponential measurements
Fuel burnup (Nuclear engineering)
Heavy water reactors
Hydrodynamics
Hydrogen
Light water reactors
Niobium alloys
Niobium-zirconium alloys
Nuclear fuel elements
Nuclear fuels
Safety measures
Steam generating heavy water reactors
Transition flow
Zirconium alloys