Streamlined best estimate plus uncertainty analysis of a GEN III + BWR for a bottom drain line small break LOCA
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference56 articles.
1. Development of good practice guidance for quantification of thermal-hydraulic code model input uncertainty;Baccou;Nucl. Eng. Des.,2019
2. SAPIUM: a generic framework for a practical and transparent quantification of thermal-hydraulic code model input uncertainty;Baccou;Nucl. Sci. Eng.,2020
3. Simplified boiling water reactor thermal-hydraulic performance: a RELAP5/MOD2 model simulation;Barbucci;Nucl. Technol.,1995
4. Post-Test Analysis of PIPER-ONE PO-IC-2 Experiment by RELAP5/MOD3 Codes;Bovalini,1996
5. Quantifying reactor safety margins part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology;Boyack;Nucl. Eng. Des.,1990
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