The decomposition analysis of void reactivity coefficient for innovative BWR assemblies is presented in this paper. The innovative assemblies were loaded with high enrichment UO2 and MOX fuels. Additionally the impact of the moderation enhancement on the void reactivity coefficient through a full fuel burnup discharge interval was investigated for the innovative assembly with MOX fuel. For the numerical analysis the TRITON functional module of SCALE code with ENDF/B-VI cross section library was applied. The obtained results indicate the influence of the most important isotopes to the void reactivity behaviour over a fuel burnup interval of 70 GWd/t for both UO2 and MOX fuels. From the neutronic safety concern positive void reactivity coeffi...
This paper presents a coolant void reactivity analysis of CANDU-6 and ACR-700 fuel lattices using Mo...
Calculations have been performed to assess the neutronic behavior of pins of Fully-Ceramic Micro-enc...
The reactivity loss of PWR fuel with burnup has been investigated experimentally by measuring the re...
In the past few years, the use of MOX fuel in commercial nuclear power stations has been considered ...
The current focus of the Deep Burn Project is on once-through burning of transuranice (TRU) in light...
AbstractThis study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6...
One of proposed Accident Tolerant Fuel (ATF) concept is fully ceramic micro-encapsulated fuel (FCMF)...
As part of Fissile Materials Disposition Program (FMDP) physics support was given to the design of a...
As part of Fissile Materials Disposition Program (FMDP) physics support was given to the design of a...
AbstractTo fulfill safety of fast sodium reactors in a beyond design-basis accident (BDBA) like unpr...
There has been a trend by the utilities to extend the operating cycle of their power reactors in the...
A denatured (U-233/Th)O/sub 2/ fuel assembly has been designed which is energy equivalent to and har...
The objective of this thesis is to study and understand the behavior of the reactivity coefficients ...
The current focus of the Deep Burn Project is on once-through burning of transuranics (TRU) in light...
A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the...
This paper presents a coolant void reactivity analysis of CANDU-6 and ACR-700 fuel lattices using Mo...
Calculations have been performed to assess the neutronic behavior of pins of Fully-Ceramic Micro-enc...
The reactivity loss of PWR fuel with burnup has been investigated experimentally by measuring the re...
In the past few years, the use of MOX fuel in commercial nuclear power stations has been considered ...
The current focus of the Deep Burn Project is on once-through burning of transuranice (TRU) in light...
AbstractThis study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6...
One of proposed Accident Tolerant Fuel (ATF) concept is fully ceramic micro-encapsulated fuel (FCMF)...
As part of Fissile Materials Disposition Program (FMDP) physics support was given to the design of a...
As part of Fissile Materials Disposition Program (FMDP) physics support was given to the design of a...
AbstractTo fulfill safety of fast sodium reactors in a beyond design-basis accident (BDBA) like unpr...
There has been a trend by the utilities to extend the operating cycle of their power reactors in the...
A denatured (U-233/Th)O/sub 2/ fuel assembly has been designed which is energy equivalent to and har...
The objective of this thesis is to study and understand the behavior of the reactivity coefficients ...
The current focus of the Deep Burn Project is on once-through burning of transuranics (TRU) in light...
A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the...
This paper presents a coolant void reactivity analysis of CANDU-6 and ACR-700 fuel lattices using Mo...
Calculations have been performed to assess the neutronic behavior of pins of Fully-Ceramic Micro-enc...
The reactivity loss of PWR fuel with burnup has been investigated experimentally by measuring the re...