On the possibility of using uranium-beryllium oxide fuel in a VVER reactor
Journal Article
·
· Physics of Atomic Nuclei
- National Research Center Kurchatov Institute (Russian Federation)
The possibility of using UO{sub 2}-BeO fuel in a VVER reactor is considered with allowance for the thermophysical properties of this fuel. Neutron characteristics of VVER fuel assemblies with UO{sub 2}-BeO fuel pellets are estimated.
- OSTI ID:
- 22314713
- Journal Information:
- Physics of Atomic Nuclei, Vol. 77, Issue 14; Other Information: Copyright (c) 2014 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA); ISSN 1063-7788
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of weapons grade MOX fuel performance in light water reactors using Comethe computer code
Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE
Enhanced Thermal Conductivity UO{sub 2}-BeO and UO{sub 2}-SiC Fuels Behavior
Conference
·
Wed Sep 15 00:00:00 EDT 1999
·
OSTI ID:22314713
+1 more
Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE
Technical Report
·
Sat Oct 01 00:00:00 EDT 2011
·
OSTI ID:22314713
Enhanced Thermal Conductivity UO{sub 2}-BeO and UO{sub 2}-SiC Fuels Behavior
Journal Article
·
Wed Jun 15 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:22314713