In this document issued according to Work Release 02. P. 99-lb the results of neutronics studies of <<100%Pu>> MOX LTA design are presented. The parametric studies of infinite MOX-UOX grids, MOX-UOX core fragments and of VVER-1000 core with 3 MOX LTAs are performed. The neutronics parameters of MOX fueled core have been performed for the chosen design MOX LTA using the Russian 3D code BIPR-7A and 2D code PERMAK-A with the constants prepared by the cell spectrum code TVS-M
As part of the effort for the benchmarking neutronic codes for plutonium utilization, the determinis...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
This work uses the 2-D C5G7 benchmark to verify the accuracy and efficiency of the MOCUM code, a par...
In this document the results of neutronics studies of <<100%Pu>> MOX LTA design are pres...
The present work is a part of Joint U.S./Russian Project with Weapons-Grade Plutonium Disposition in...
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...
The parametric studies of MOX LTA design have been executed to choose plutonium content in assembly ...
Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of...
A series of unit pin-cell benchmark problems have been analyzed related to irradiation of mixed oxid...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
The MPACT code, jointly developed by Oak Ridge National Laboratory and University of Michigan, is de...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
This work uses the 2-D C5G7 benchmark to verify the accuracy of the MOCUM code, a parallel neutronic...
Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of...
As part of the effort for the benchmarking neutronic codes for plutonium utilization, the determinis...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
This work uses the 2-D C5G7 benchmark to verify the accuracy and efficiency of the MOCUM code, a par...
In this document the results of neutronics studies of <<100%Pu>> MOX LTA design are pres...
The present work is a part of Joint U.S./Russian Project with Weapons-Grade Plutonium Disposition in...
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...
The parametric studies of MOX LTA design have been executed to choose plutonium content in assembly ...
Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of...
A series of unit pin-cell benchmark problems have been analyzed related to irradiation of mixed oxid...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
The MPACT code, jointly developed by Oak Ridge National Laboratory and University of Michigan, is de...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
This work uses the 2-D C5G7 benchmark to verify the accuracy of the MOCUM code, a parallel neutronic...
Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of...
As part of the effort for the benchmarking neutronic codes for plutonium utilization, the determinis...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
This work uses the 2-D C5G7 benchmark to verify the accuracy and efficiency of the MOCUM code, a par...
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