The paper presents the results of a computational analysis of the OECD/NEA benchmark conducted to estimate the accuracy of the critical safety parameters of multiplying MOX-fueled systems. The computational test is a set of 15 spherical multiplying systems that differ in their compositions and geometries. According to the test conditions, the keff values of the analyzed systems are unknown in advance. As part of the computational analysis of the test involving national codes and nuclear data libraries, along with the keff calculations, it is also necessary to estimate the a priori (due to the accuracy of the nuclear data used) and a posteriori (based on the accumulated experimental information) errors in the calculated keff values. Based on...
Traditionally, nuclear data evaluations have been performed in support of the analysis and design of...
The need for building mutually self-agreed computational models for high-precision and engineering n...
VALMOX, an acronym for validation of nuclear data for high burn-up MOX fuels, is one of the projects...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
A target accuracy assessment of the effective neutron multiplication factor, keff, for MYRRHA (Multi...
This paper presents the validation of the MCS code for critical safety analysis with burnup credit f...
The US is currently evaluating the use of MOX fuel in commercial LWR's for reducing weapons grade Pu...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
Investigations of fuel behavior are carried out in close connection with experimental research, ope...
The paper presents the results of a comparative analysis of criticality calculations using a Monte-C...
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the...
The applicability of proposed critical experiments for the criticality code validation of a series o...
To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cor...
Traditionally, nuclear data evaluations have been performed in support of the analysis and design of...
The need for building mutually self-agreed computational models for high-precision and engineering n...
VALMOX, an acronym for validation of nuclear data for high burn-up MOX fuels, is one of the projects...
International audienceThe use of mixed oxide (MOx) fuels in commercial Light Water Reactors is affec...
A series of experiments referred to as BFS/MOX was conducted in the BFS-1 experimental facility at I...
The paper presents calculation results for experiments performed to address needs of the MOX fuel ma...
A target accuracy assessment of the effective neutron multiplication factor, keff, for MYRRHA (Multi...
This paper presents the validation of the MCS code for critical safety analysis with burnup credit f...
The US is currently evaluating the use of MOX fuel in commercial LWR's for reducing weapons grade Pu...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
Investigations of fuel behavior are carried out in close connection with experimental research, ope...
The paper presents the results of a comparative analysis of criticality calculations using a Monte-C...
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the...
The applicability of proposed critical experiments for the criticality code validation of a series o...
To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cor...
Traditionally, nuclear data evaluations have been performed in support of the analysis and design of...
The need for building mutually self-agreed computational models for high-precision and engineering n...
VALMOX, an acronym for validation of nuclear data for high burn-up MOX fuels, is one of the projects...