Neutron multiplication in source driven subcritical nuclear systems
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A. Göksu
Abstract
In this work the neutron multiplication in a source driven subcritical nuclear system is studied for a particular physical model of symmetrical slab geometry. On both sides of a central spallation source region, bare fissile blankets are placed. The neutronics of the system is represented in terms of two-group diffusion equations. We elaborate on the development and evaluation of the multiplication factors for source and fission neutrons (and). The results are compared with the conventional multiplication factor of the fissile system. In the present static context, is important only from the safety point of view, whereas the other two factors are figures of merit measuring the effectiveness of a source neutron to start a fission chain and that of any one fission neutron to maintain a fading chain which further contributes to source multiplication.
Kurzfassung
In der vorliegenden Arbeit wird die Neutronenmultiplikation in einem quellenbetriebenen subkritischen System untersucht für ein bestimmtes physikalisches Modell in symmetrischer Stabgeometrie. Auf beiden Seiten einer zentralen Spallationsquelle werden freiliegende Spaltzonen plaziert. Das Neutronenverhalten des Systems wird dargestellt in Form von Zwei-Gruppen-Diffusionsgleichungen. Arbeiten an der Entwicklung und Bewertung von Multiplikationsfaktoren für Quellen- und Spaltneutronen (und) werden weitergeführt. Die Ergebnisse werden verglichen mit dem konventionellen Multiplikationsfaktor des Spaltsystems. In dem jetzigen stationären Zusammenhang ist nur im Hinblick auf die Sicherheit wichtig, während die beiden anderen Faktoren Leistungszahlen sind für die Messung der Fähigkeit eines Quellenneutrons eine Spaltkette zu starten und der Fähigkeit eines jeden Spaltneutrons eine nachlassende Kette zu erhalten, was weiter zur Multiplikation beiträgt.
References
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© 2011, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
