Investigation of the performance parameters and temperature distribution in fuel rod dependent on operation periods and first wall loads in fusion–fission reactor …
The neutronic performance parameters, fissile breeding and temperature distribution in the
fuel rod are investigated for different coolants ('He, CO2','Li2BeF4','Li', and 'Li17Pb83') in the …
fuel rod are investigated for different coolants ('He, CO2','Li2BeF4','Li', and 'Li17Pb83') in the …
Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D–T) driven hybrid reactor system
Temperature distribution in nuclear fuel rod and variation of the neutronic performance
parameters are investigated for different coolants under various first wall loads (Pw= 2, 5, 7 …
parameters are investigated for different coolants under various first wall loads (Pw= 2, 5, 7 …
Neutronic performance of coupled hybrid blanket fueled with ThO2 and UO2
The main purpose of this study is to investigate the blanket models fueled with ThO2 and
UO2 that provide the best coupled breeding performance and neutronic behavior as a …
UO2 that provide the best coupled breeding performance and neutronic behavior as a …
Analysis of the neutronic data in infinite medium using fusion neutron source for various material compositions
O Ipek - Energy conversion and management, 2003 - Elsevier
The main purpose of this study is to calculate the integral neutronic data, which are integral
heat release, 233U and 239Pu fissile fuels breeding rate, tritium breeding ratio, integral …
heat release, 233U and 239Pu fissile fuels breeding rate, tritium breeding ratio, integral …
Investigation of the infinite medium integral neutronic data for incident fusion source neutrons
O Ipek - Annals of Nuclear Energy, 2002 - Elsevier
In the present work, the physical behavior of integral data in infinite medium has been
evaluated for incident fusion neutrons with the help to the 3-D Monte Carlo code. In a fusion …
evaluated for incident fusion neutrons with the help to the 3-D Monte Carlo code. In a fusion …
[PDF][PDF] Calculations of maximum temperature in centerline of nuclear fuel rod and fissile fuel enrichment in hybrid reactor
Behavior of nuclear fuel material and temperature distribution in fuel rods are observed over
4 years for a discrete time interval of∆ t= 15 days, different coolants, and volumetric ratio ε (ε …
4 years for a discrete time interval of∆ t= 15 days, different coolants, and volumetric ratio ε (ε …
Fuel enrichment and temperature distribution in nuclear fuel rod in (DT) driven hybrid reactor system
Y Osman - 2001 - osti.gov
In this study, melting point of the fuel rod and temperature distribution in nuclear fuel rod are
investigated for different coolants under various first wall loads (P {sub w},= 5, 6, 7, 8, 9, and …
investigated for different coolants under various first wall loads (P {sub w},= 5, 6, 7, 8, 9, and …