Nuclear Data and Fuel/Assembly Manufacturing Uncertainties Analysis and Preliminary Validation of SUACL
JiaYi Xu, Xu Bo Ma, Fan Lu, Yi Xue Chen

TL;DR
This paper analyzes the uncertainties in nuclear data and manufacturing parameters affecting reactor performance, validating the SUACL method and highlighting the importance of covariance libraries and manufacturing parameters in uncertainty assessment.
Contribution
It introduces a comprehensive uncertainty analysis framework for nuclear data and manufacturing parameters, with validation against reference codes and comparison of covariance libraries.
Findings
SUACL results align with reference codes
Uncertainty in Keff is influenced by specific isotopes
Covariance library choice significantly affects uncertainty estimates
Abstract
As the sensitivity and uncertainty analysis of nuclear system can provide more confident bounds for the Best-estimate Prediction used to assess the performance and safety of nuclear plant, the uncertainty and sensitivity analysis has been a component of analysis of nuclear system. Both the cross section uncertainty and the uncertainty of parameters of fuel/assembly manufacturing are analyzed in this paper. All results of SUACL were found in accordance with the results of reference codes.238U and 235U play an important role in determining the uncertainty of Keff in TMI-1 cell. The uncertainty of Keff in MOX is mainly affected by 239Pu and 238U. It is obvious that the uncertainty mostly depends on the covariance library and insensitivities to cross section library. The uncertainties based on the covariance library obtained from ENDF/B-VII.1 differ from the result of JENDL4.0, which…
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Taxonomy
TopicsNuclear reactor physics and engineering · Nuclear and radioactivity studies · Probabilistic and Robust Engineering Design
