In this paper, multi-group microscopic cross-section uncertainty is propagated through the DRAGON (Version 4) lattice code, in order to perform uncertainty analysis on k_inf and 2-group homogenized macroscopic cross-sections predictions. A statistical methodology is employed for such purposes, where cross-sections of certain isotopes of various elements belonging to the 172 groups DRAGLIB library format, are considered as normal random variables. This library is based on JENDL-4 data, because JENDL-4 contains the largest amount of isotopic covariance matrixes among the different major nuclear data libraries. The aim is to propagate multi-group nuclide uncertainty by running the DRAGONv4 code 500 times, and to assess the output uncertainty o...
Best-Estimation Plus Uncertainty (BEPU) analysis method can provide more information to improve the ...
The probability table method is an important method to treat the self-shielding effect in the unreso...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...
In this paper, multi-group microscopic cross-section uncertainty is propagated through the DRAGON (V...
In this paper, multi-group microscopic cross-section uncertainties are propagated through the DRAGON...
The OECD/NEA Uncertainty Analysis in Modeling (UAM) expert group organized andlaunched the UAM bench...
Copyright © 2013 Augusto Hernández-Solís et al. is is an open access article distributed under the C...
TENDL evaluate files have been processed with NJOY and different libraries have been created and pro...
This paper concerns estimating uncertainties of the core neutronics design parameters of power react...
The topic of this paper is the development of sensitivity and uncertainty analysis capability to the...
This paper concerns estimating uncertainties of the core neutronics design parameters of power react...
Uncertainty quantification has been extensively applied to nuclear criticality analyses for many yea...
International audienceThe development of tools for nuclear data uncertainty propagation in lattice c...
This paper reports on the development and testing of a comprehensive few-group cross section input u...
In this paper, we present an uncertainty methodology based on a statistical approach, for assessing ...
Best-Estimation Plus Uncertainty (BEPU) analysis method can provide more information to improve the ...
The probability table method is an important method to treat the self-shielding effect in the unreso...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...
In this paper, multi-group microscopic cross-section uncertainty is propagated through the DRAGON (V...
In this paper, multi-group microscopic cross-section uncertainties are propagated through the DRAGON...
The OECD/NEA Uncertainty Analysis in Modeling (UAM) expert group organized andlaunched the UAM bench...
Copyright © 2013 Augusto Hernández-Solís et al. is is an open access article distributed under the C...
TENDL evaluate files have been processed with NJOY and different libraries have been created and pro...
This paper concerns estimating uncertainties of the core neutronics design parameters of power react...
The topic of this paper is the development of sensitivity and uncertainty analysis capability to the...
This paper concerns estimating uncertainties of the core neutronics design parameters of power react...
Uncertainty quantification has been extensively applied to nuclear criticality analyses for many yea...
International audienceThe development of tools for nuclear data uncertainty propagation in lattice c...
This paper reports on the development and testing of a comprehensive few-group cross section input u...
In this paper, we present an uncertainty methodology based on a statistical approach, for assessing ...
Best-Estimation Plus Uncertainty (BEPU) analysis method can provide more information to improve the ...
The probability table method is an important method to treat the self-shielding effect in the unreso...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...