Uncertainty analysis for fission products transport in CANDU primary heat transport during a severe accident
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M. Apostol
Abstract
The work realized under the Severe Accident Research Network of excellence (SARNET) project has shown that the SOPHAEROS module, part of Accident Source Term Evaluation Code (ASTEC) can be fully used to simulate the fission products transport and deposition phenomena in the CANDU Primary Heat Transport (PHT) system. This paper presents an uncertainty analysis for the fission products transport in the CANDU PHT system during a severe accident to obtain the domains of the output parameters, for this study masses of Caesium, Strontium and Iodine deposited in the PHT system and its nodes, taking into account the associated input parameters uncertainties. Five uncertain parameters, the starting time for the releasing process, the duration of the releasing process, the releasing fractions for Cs, Sr and I have been chosen. To generate aleatory values for the uncertain parameters, a method and software have been developed and Monte Carlo simulations to determine uncertainties propagation through the SOPHAEROS module has been carried out.
Kurzfassung
Die im Rahmen des SARNET-Projekts durchgeführten Arbeiten haben gezeigt, dass das SOPHAEROS-Modul als ein Teil des ASTEC-Codes für die Quelltermabschätzung bei schweren Störfällen gut geeignet ist, um den Transport und die Ablagerung von Spaltprodukten im Primärkühlkreis des Reaktors CANDU zu simulieren. Dieser Beitrag stellt eine Unsicherheitsanalyse für den Transport von Spaltprodukten im Primärkühlkreislauf bei einem schweren Störfall dar, die eine Abschätzung der Ausgangsparameter unter Berücksichtigung der Unsicherheiten von Eingangsparametern, wie zum Beispiel, die Mengen an Cs, Sr und I, abgelagert im Primärkreis und seinen Verbindungsstellen, ermöglicht. Fünf Unsicherheitsparameter wurden ausgewählt: Startzeit des Freisetzungsprozesses, Dauer des Freisetzungsprozesses, Freisetzungsanteile für Cs, Sr und I. Zur Erzeugung von Zufallsvariablen für die Unsicherheitsanalyse wurde eine entsprechende Methodik und Software entwickelt und Monte-Carlo-Simulationen zur Abschätzung der Fortpflanzung der Unsicherheiten im SOPHAEROS-Modul durchgeführt.
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© 2010, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Numerical simulation on a HPLWR fuel assembly flow with one revolution of wrapped wire spacers
- Axial-power-shape induced frequency shifts in BWR stability measurements
- Numerical investigation of heat transfer in the vertical annulus between pressure tube and calandria tube of the advanced water cooled reactor
- Uncertainty analysis for fission products transport in CANDU primary heat transport during a severe accident
- Definition of conservative conditions for RIA analysis in the modernized RBMK reactor core
- Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors
- In-pile measurements of the fission gas pressure and comparison with ROFEM code results
- The time-dependent P1 model for the neutronics of multiplying systems: a review
- Efficiency of reflection coefficients in the isotropic neutron transport equation and computation of the critical-half thicknesses
- Finite differences with exponential filtering in the calculation of reactivity
- Asymptotic solution of critical thickness with direct second kind Chebyshev polynomial approximation in forward and backward scattering
- Interactions of radionuclides in solution with ions and with trace concentrations of solid phase
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Numerical simulation on a HPLWR fuel assembly flow with one revolution of wrapped wire spacers
- Axial-power-shape induced frequency shifts in BWR stability measurements
- Numerical investigation of heat transfer in the vertical annulus between pressure tube and calandria tube of the advanced water cooled reactor
- Uncertainty analysis for fission products transport in CANDU primary heat transport during a severe accident
- Definition of conservative conditions for RIA analysis in the modernized RBMK reactor core
- Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors
- In-pile measurements of the fission gas pressure and comparison with ROFEM code results
- The time-dependent P1 model for the neutronics of multiplying systems: a review
- Efficiency of reflection coefficients in the isotropic neutron transport equation and computation of the critical-half thicknesses
- Finite differences with exponential filtering in the calculation of reactivity
- Asymptotic solution of critical thickness with direct second kind Chebyshev polynomial approximation in forward and backward scattering
- Interactions of radionuclides in solution with ions and with trace concentrations of solid phase
