A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at IPPE, Russia. The program was designed to provide a basis for validation of criticality calculations for MOX fuel manufacturing processes and particularly those with low-moderated MOX fissile material. An extensive experimental program was performed, including criticality and reactor-type parameter measurements. The experiments were evaluated, peer reviewed, and analyzed with various codes and cross section data. The criticality validation study was performed employing a sensitivity/uncertainty technique based on the generalized linear least squares method. This paper briefly describes the experimental program, shows different tools' performan...
The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified ...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
Thermal conductivity and melting temperature of nuclear fuel are essential for its performance under...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
Abstract – Sensitivity and uncertainty analysis methodologies under development at Oak Ridge Nationa...
International audienceIn the framework of the WPNCS Expert Group on Uncertainty Analysis for Critica...
The applicability of proposed critical experiments for the criticality code validation of a series o...
The paper presents the results of a computational analysis of the OECD/NEA benchmark conducted to es...
At the Oak Ridge National Laboratory (ORNL), sensitivity and uncertainty (S/U) analysis methods and ...
This report provides the criticality safety information needed for obtaining certification of the sh...
Critical systems which might be formed in geologic repositories as a result of long-term degradation...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4In the development of...
The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified ...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
Thermal conductivity and melting temperature of nuclear fuel are essential for its performance under...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
Abstract – Sensitivity and uncertainty analysis methodologies under development at Oak Ridge Nationa...
International audienceIn the framework of the WPNCS Expert Group on Uncertainty Analysis for Critica...
The applicability of proposed critical experiments for the criticality code validation of a series o...
The paper presents the results of a computational analysis of the OECD/NEA benchmark conducted to es...
At the Oak Ridge National Laboratory (ORNL), sensitivity and uncertainty (S/U) analysis methods and ...
This report provides the criticality safety information needed for obtaining certification of the sh...
Critical systems which might be formed in geologic repositories as a result of long-term degradation...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4In the development of...
The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified ...
This paper reports a study to confirm the applicability of the latest version of Japanese Evaluated ...
Thermal conductivity and melting temperature of nuclear fuel are essential for its performance under...