Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
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B. Foad
Abstract
The purpose of this work is to study the feasibility of the Thorium/Uranium fuel cycle in heterogeneous Pressurized Water Reactors (PWR) core design. This paper focuses on the neutronic and burn-up analysis of the Thorium/Uranium fuel using the computer codes MCNPX and WIMS. The design is based on the Whole Assembly Seed and Blanket (WASB) concept, in which the individual seed (Uranium) and blanket (Thorium-Uranium) units occupy one full-size PWR assembly in a checkerboard core configuration. The results of the present models were compared with the solution of benchmark problems and satisfactory agreement was found.
Kurzfassung
Zweck dieser Arbeit ist eine Machbarkeitsstudie zum Thorium/Uran Brennstoffkreislaufs in Druckwasserreaktoren. Die Arbeit konzentriert sich auf Neutronen- und Abbrandberechnungen von Thorium/Uran Brennstoff mit Hilfe der Computer Codes MCNPX and WIMS. Der Aufbau basiert auf dem Whole Assembly Seed and Blanket (WASB) Konzept, bei dem die einzelnen Seed-(Uranium) und Blanket-(Thorium-Uran) Einheiten eine volle PWR Anordnung in einer vertikal versetzten Kernkonfiguration besetzen. Die Ergebnisse der derzeitigen Modelle wurden verglichen mit der Lösung von Benchmark-Problemen mit befriedigender Übereinstimmung.
References
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© 2010, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Integrated online condition monitoring system for nuclear power plants
- Performance analysis of 233U for fixed bed nuclear reactors
- 3D thermal hydraulic simulation of the hot channel of a typical material testing reactor under normal operation conditions
- Analysis of the processes in the target cooling system of the W7-X fusion experiment
- Nuclear model calculation on charged particle induced reactions to produce 85Sr for diagnostic and endotherapy
- Neutronic and burn-up calculations of heterogeneous Thorium/Uranium fuel in pressurized water reactors
- Research on pitting corrosion of steam generator heat transfer tubes based on acoustic emission
- Application of the Chebyshev polynomial (TN and UN) approximation to reflected slab geometry in the neutron transport equation and computation of critical half thicknesses
- UN approximation to critical slab problem for one-speed neutrons with isotropic, forward and backward scattering
- The albedo problem for pure-quadratic anisotropic scattering with İnönü scattering
- Technical Notes/Technische Mitteilungen
- Targetry of Y2O3 on a copper substrate for the non-carrier-added 89Zr production via 89Y(p, n)89Zr reaction
