Mass flow rate sensitivity and uncertainty analysis in natural circulation boiling water reactor core from Monte Carlo simulations
- 31 May 2010
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 240 (5) , 1050-1062
Abstract
No abstract availableKeywords
This publication has 14 references indexed in Scilit:
- Analytical evaluation on dynamical response characteristics of reduced-moderation water reactor with tight-lattice core under natural circulation core coolingAnnals of Nuclear Energy, 2009
- Methodology for the reliability evaluation of a passive system and its integration into a Probabilistic Safety AssessmentNuclear Engineering and Design, 2005
- Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 ReactorAtomic Energy, 2004
- Reliability evaluation of a natural circulation systemNuclear Engineering and Design, 2003
- Passive System Reliability Analysis: A Study on the Isolation CondenserNuclear Technology, 2002
- Mersenne twisterACM Transactions on Modeling and Computer Simulation, 1998
- SBWR, a simplified boiling water reactorNuclear Engineering and Design, 1988
- An analytical study of the thermally induced two-phase flow instabilities including the effect of thermal non-equilibriumInternational Journal of Heat and Mass Transfer, 1978
- RANDOM NUMBERS FALL MAINLY IN THE PLANESProceedings of the National Academy of Sciences, 1968
- A Convenient Method for Generating Normal VariablesSIAM Review, 1964