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Uncertainty Analyses Applied to the UAMTMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDFB-VII.1 Covariance Data
Joint Authors
Hernández-Solís, Augusto
Ekberg, Christian
Demazière, Christophe
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2013, Issue 2013 (31 Dec. 2013), pp.1-21, 21 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2013-02-10
Country of Publication
Egypt
No. of Pages
21
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
The OECD/NEA Uncertainty Analysis in Modeling (UAM) expert group organized and launched the UAM benchmark.
Its main objective is to perform uncertainty analysis in light water reactor (LWR) predictions at all modeling stages.
In this paper, multigroup microscopic cross-sectional uncertainties are propagated through the DRAGON (version 4.05) lattice code in order to perform uncertainty analysis on k∞ and 2-group homogenized macroscopic cross-sections.
The chosen test case corresponds to the Three Mile Island-1 (TMI-1) lattice, which is a 15 × 15 pressurized water reactor (PWR) fuel assembly segment with poison and at full power conditions.
A statistical methodology is employed for the uncertainty assessment, where cross-sections of certain isotopes of various elements belonging to the 172-group DRAGLIB library format are considered as normal random variables.
Two libraries were created for such purposes, one based on JENDL-4 data and the other one based on the recently released ENDF/B-VII.1 data.
Therefore, multigroup uncertainties based on both nuclear data libraries needed to be computed for the different isotopic reactions by means of ERRORJ.
The uncertainty assessment performed on k∞ and macroscopic cross-sections, that is based on JENDL-4 data, was much higher than the assessment based on ENDF/B-VII.1 data.
It was found that the computed Uranium 235 fission covariance matrix based on JENDL-4 is much larger at the thermal and resonant regions than, for instance, the covariance matrix based on ENDF/B-VII.1 data.
This can be the main cause of significant discrepancies between different uncertainty assessments.
American Psychological Association (APA)
Hernández-Solís, Augusto& Demazière, Christophe& Ekberg, Christian. 2013. Uncertainty Analyses Applied to the UAMTMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDFB-VII.1 Covariance Data. Science and Technology of Nuclear Installations،Vol. 2013, no. 2013, pp.1-21.
https://search.emarefa.net/detail/BIM-472300
Modern Language Association (MLA)
Hernández-Solís, Augusto…[et al.]. Uncertainty Analyses Applied to the UAMTMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDFB-VII.1 Covariance Data. Science and Technology of Nuclear Installations No. 2013 (2013), pp.1-21.
https://search.emarefa.net/detail/BIM-472300
American Medical Association (AMA)
Hernández-Solís, Augusto& Demazière, Christophe& Ekberg, Christian. Uncertainty Analyses Applied to the UAMTMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDFB-VII.1 Covariance Data. Science and Technology of Nuclear Installations. 2013. Vol. 2013, no. 2013, pp.1-21.
https://search.emarefa.net/detail/BIM-472300
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-472300