Thermal analytical model for MoO3 ampoules irradiated in a high neutron flux
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A. Abd-El-Hady
Abstract
A one dimensional steady state thermal analytical model has been developed to study the heat transfer and temperature distributions in a quartz ampoule filled with MoO3 powder. The source heat generation inside the ampoule is released from the high neutron flux (1.4 × 1014 neutrons/cm2s) interaction with MoO3. Natural and forced convections heat transfer boundary conditions are adopted during the irradiation process. The peak temperatures in MoO3 powder and quartz are calculated and compared with their melting temperatures to ensure the irradiation safety criteria.
Kurzfassung
Thermoanalytisches Modell für die Bestrahlung von MoO3 Ampullen mit hohem Neutronenfluss. Ein eindimensionales thermoanalytisches Modell für stationäre Zustände wurde entwickelt zur Untersuchung des Wärmetransfers und der Temperaturverteilung in einer mit MoO3 Pulver gefüllten Quarzampulle. Die Wärmeerzeugung im Innern der Ampulle erfolgt durch die Wechselwirkung des hohen Neutronenflusses (1.4 × 1014 neutrons/cm2s) mit dem MoO3 Pulver. Während des Bestrahlungsprozesses werden Randbedingungen mit natürlichen und erzwungenen Wärmetransferkonvektionen angenommen. Die Temperatur-Peaks im MoO3 Pulver und im Quarz werden berechnet und verglichen mit den jeweiligen Schmelztemperaturen, um so die Sicherheitskriterien bei der Bestrahlung zu gewährleisten.
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© 2009, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- AVR prototype pebble bed reactor: a safety re-evaluation of its operation and consequences for future reactors
- Design Concept of the High Performance Light Water Reactor
- Behavior of CANDU fuel under power pulse conditions at the TRIGA reactor of INR Pitesti
- Plate heat exchanger – inertia flywheel performance in loss of flow transient
- Performance analyses of the communication networks of a modern supervision and control system of research reactors
- Thermal analytical model for MoO3 ampoules irradiated in a high neutron flux
- Effect of using various grades of plutonium in the protective liquid wall of an IFE type fusion reactor
- A discrete ordinates scheme for void fraction evaluation with nonstandard reflective conditions and weakly divergent beams
- Application of the Laplace transform method for the albedo boundary conditions in multigroup neutron diffusion eigenvalue problems in slab geometry
- Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses
- Optimizing the dynamic response of the H. B. Robinson nuclear plant using multiobjective particle swarm optimization
- Assessment for inside building dispersion of aerosol from an outdoor radiological release
- Technical Notes/Technische Mitteilungen
- Analysis of a steam generator tube rupture under realistic initial and boundary conditions
