scholarly journals Comparison of calculated and experimental neutron spectra from the LLL pulsed sphere program using the TART Monte Carlo code and the LLL Evaluated Nuclear Data Library

1972 ◽  
Author(s):  
R.J. Howerton
Keyword(s):  
Monte Carlo ◽  
Nuclear Data ◽  
Monte Carlo Code ◽  
Neutron Spectra ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

scholarly journals Calculation and experimental analysis of benchmark experiments with a fast neutron spectrum and models of sodium and lead cooled fast reactors using different evaluated nuclear data libraries

2021 ◽  
Vol 7 (2) ◽  
pp. 103-109
Author(s):  
Olga N. Andrianova ◽  
Yury Ye. Golovko ◽  
Gleb B. Lomakov ◽  
Yevgeniya S. Teplukhina ◽  
Gennady M. Zherdev
Keyword(s):  
Nuclear Data ◽  
Monte Carlo Code ◽  
Fast Reactors ◽  
Neutron Data ◽  
Critical Configurations ◽  
Nuclear Data Library ◽  
Data Libraries ◽  
Nuclear Data Libraries ◽  
Data Library ◽  
Evaluated Nuclear Data

The paper presents the results of a comparative analysis of criticality calculations using a Monte-Carlo code with the BNAB-93 and BNAB-RF neutron group constants, as well as with evaluated neutron data files from the Russian ROSFOND evaluated nuclear data library and other evaluated nuclear data libraries (ENDF, JEFF, JENDL) from different years. A set of integral experiments on BFS critical assemblies carried out in different years at the Institute of Physics and Power Engineering (60 different critical configurations) was analyzed. The considered integral experiments are included in the database of evaluated experimental neutronic data used to justify the neutronic performance of sodium and lead cooled fast reactors, to verify codes and nuclear data as well as to estimate uncertainties in neutronic parameters due to the nuclear data uncertainties. It has been shown that the ROSFOND evaluated nuclear data library is a library that minimizes the calculation and experimental discrepancies for the considered set of integral experiments. The paper also presents the results of criticality calculations for models of sodium and lead cooled fast reactors based on different evaluated neutron data libraries and provides estimates for the uncertainty in criticality associated with nuclear data.

scholarly journals CENDL project, the chinese evaluated nuclear data library

2017 ◽  
Vol 146 ◽  
pp. 02002 ◽  
Author(s):  
Zhigang Ge ◽  
Haicheng Wu ◽  
Guochang Chen ◽  
Ruirui Xu
Keyword(s):  
Nuclear Data ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

The Updated Vversion of Chinese Evaluated Nuclear Data Library (CENDL-3.1)

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1052-1056 ◽  
Author(s):  
Z. G. Ge ◽  
Z. X. Zhao ◽  
H. H. Xia ◽  
Y. X. Zhuang ◽  
T. J. Liu ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data

scholarly journals Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

2016 ◽  
Vol 182 (2) ◽  
pp. 135-150
Author(s):  
G. Noguere ◽  
D. Bernard ◽  
P. Blaise ◽  
O. Bouland ◽  
L. Leal ◽  
...  
Keyword(s):  
Mixed Oxide ◽  
Nuclear Data ◽  
Oxide Fuel ◽  
Mixed Oxide Fuel ◽  
Nuclear Data Library ◽  
Data Library ◽  
Evaluated Nuclear Data
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