Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients
- 28 February 2005
- journal article
- Published by Elsevier BV in Nuclear Engineering and Design
- Vol. 235 (2-4), 521-540
- https://doi.org/10.1016/j.nucengdes.2004.09.003
Abstract
No abstract availableKeywords
This publication has 5 references indexed in Scilit:
- Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facilityNuclear Engineering and Design, 2005
- Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 2: Analysis of a VVER-440 transient (Loviisa-1)Annals of Nuclear Energy, 2002
- Validation of coupled neutron kinetic/thermal–hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4)Annals of Nuclear Energy, 2001
- Sensitivity analysis in the context of uncertainty analysis for computationally intensive modelsComputer Physics Communications, 1999
- Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodologyNuclear Engineering and Design, 1990