In this document 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
A series of unit pin-cell benchmark problems have been analyzed related to irradiation of mixed oxid...
Reducing the number of actinide separation streams in a spent fuel recovery process would reduce the...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
In this document issued according to Work Release 02. P. 99-lb the results of neutronics studies of ...
The parametric studies of MOX LTA design have been executed to choose plutonium content in assembly ...
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 present work is a part of Joint U.S./Russian Project with Weapons-Grade Plutonium Disposition in...
Among various versions of excess weapons-grade plutonium handling the most preferred in Russia is it...
One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...
In the 1970s at the Battelle Pacific Northwest Laboratory (PNL), a series of critical experiments us...
This project was a collaborative effort involving researchers from Oak Ridge National Laboratory and...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
In the past few years, the use of MOX fuel in commercial nuclear power stations has been considered ...
A series of unit pin-cell benchmark problems have been analyzed related to irradiation of mixed oxid...
Reducing the number of actinide separation streams in a spent fuel recovery process would reduce the...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
In this document issued according to Work Release 02. P. 99-lb the results of neutronics studies of ...
The parametric studies of MOX LTA design have been executed to choose plutonium content in assembly ...
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 present work is a part of Joint U.S./Russian Project with Weapons-Grade Plutonium Disposition in...
Among various versions of excess weapons-grade plutonium handling the most preferred in Russia is it...
One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...
In the 1970s at the Battelle Pacific Northwest Laboratory (PNL), a series of critical experiments us...
This project was a collaborative effort involving researchers from Oak Ridge National Laboratory and...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
In the past few years, the use of MOX fuel in commercial nuclear power stations has been considered ...
A series of unit pin-cell benchmark problems have been analyzed related to irradiation of mixed oxid...
Reducing the number of actinide separation streams in a spent fuel recovery process would reduce the...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
DOI
Add to ORKG