Effect of changes in the nonuniformity of energy evolution in the fuel of thermal reactors on the temperature distribution in the fuel elements

1974 ◽  
Vol 36 (4) ◽  
pp. 341-344
Author(s):  
V. S. Yamnikov ◽  
L. L. Malanchenko ◽  
V. I. Solyanyi
Keyword(s):  
Temperature Distribution ◽  
Energy Evolution ◽  
Fuel Elements

The temperature distribution in liquid metal cooled fuel elements

1967 ◽  
Vol 22 (5) ◽  
pp. 468-474 ◽  
Author(s):  
V. I. Subbotin ◽  
P. A. Ushakov ◽  
A. V. Zhukov ◽  
V. A. Talanov
Keyword(s):  
Temperature Distribution ◽  
Liquid Metal ◽  
Fuel Elements

Temperature distribution in UO2 fuel elements

1962 ◽  
Vol 7 (3) ◽  
pp. 225-262 ◽  
Author(s):  
J.A.L. Robertson ◽  
A.M. Ross ◽  
M.J.F. Notley ◽  
J.R. MacEwan
Keyword(s):  
Temperature Distribution ◽  
Fuel Elements

Nonuniformity in the accumulation of plutonium over the radius of the VVÉR-1000 reactor fuel elements and influence of the nonuniformity upon the temperature distribution in the fuel

1990 ◽  
Vol 68 (6) ◽  
pp. 461-465 ◽  
Author(s):  
T. S. Zaritskaya ◽  
L. L. Malanchenko ◽  
L. V. Matveev ◽  
V. Yu Rogozhkin ◽  
A. P. Rudik ◽  
...  
Keyword(s):  
Temperature Distribution ◽  
Reactor Fuel ◽  
Fuel Elements

scholarly journals EFFECT OF PERMEABILITY OF PEBLE BED ON HEAT TRANSFER IN THE CORE OF NUCLEAR REACTOR WITH HELIUM COOLANT

2017 ◽  
Vol 39 (4) ◽  
pp. 55-60
Author(s):  
A. A. Avramenko ◽  
N. P. Dmitrenko ◽  
М. M. Kovetskaya ◽  
Yu. Yu. Kovetskaya
Keyword(s):  
Heat Transfer ◽  
Mass Transfer ◽  
Temperature Distribution ◽  
Heat And Mass Transfer ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Geometric Parameters ◽  
The Core ◽  
Fuel Elements ◽  
Helium Coolant

Heat and mass transfer in a model of the core of a nuclear reactor with spherical fuel elements and a helium coolant was studied. The effect of permeability of the pebble bed zone and geometric parameters on the temperature distribution of the coolant in the reactor core is analyzed.  

scholarly journals Study of Neutronic and Temperature Distribution During Enrichment Reduction for BN-350 Reactor

2018 ◽  
Vol 26 (8) ◽  
pp. 151-156
Author(s):  
Jamal Mohammed Rashid Abda
Keyword(s):  
Steady State ◽  
Temperature Distribution ◽  
Transient Response ◽  
Coolant Flow ◽  
Uranium Fuel ◽  
Flow Loss ◽  
High Enrichment ◽  
Enriched Uranium ◽  
Fuel Elements

      This paper represents the neutronic and thermal-hydraulic calculations for the conversion of BN-350 from 27% to 7% enriched Uranium fuel elements. Mixed enrichment cores have been studied where low enrichment uranium (LEU) cores fresh fuel elements substitute gradually the high enrichment uranium (HEU) depleted fuel elements in the equilibrium core.     Thermal-hydraulic calculations have been carried out to determine changes in the characteristics of the converted reactor during steady-state conditions and transient response to a coolant flow loss.   

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