An attempt to describe the swelling of U3Si 2 fuel by a simple formula
-
G. Sauer
Abstract
Fuel swelling is a key parameter to be studied in the process of qualifying a fuel for use in reactors. Generally, test irradiations are performed to quantify the swelling. However, all reactor conditions can often not be simulated in tests. This situation occurs, for example, when a fuel shall be used in a new reactor where the fission rate is higher than in existing reactors available for the qualification tests. The swelling under the conditions of the new reactor must be predicted based on the data found under these test conditions. For this prediction a formula is required. Such a formula is derived for one of the most popular fuels for high flux reactors: U3Si2.
Abstract
Eines der bei der Qualifizierung eines Brennstoffes für den Reaktoreinsatz zu untersuchenden Phänomene ist das Schwellen des Brennstoffs. In der Regel werden zur Quantifizierung des Schwellens Testbestrahlungen durchgeführt. Oft ist es jedoch nicht möglich, alle Reaktorbedingungen in diesen Tests zu simulieren. Diese Situation ergibt sich z. B., wenn der Brennstoff in einem neuen Reaktor eingesetzt werden soll, in dem die Spaltungsrate größer ist als in den Reaktoren, die für die Tests zur Verfügung stehen. Das Schwellen unter den Bedingungen des neuen Reaktors muß auf der Grundlage der unter den Testbedingungen ermittelten Daten prognostiziert werden. Für diese Prognose wird eine Formel benötigt. Eine solche Formel wird für einen der meistverwendeten Brennstoffe für Hochflußreaktoren, U3Si2 abgeleitet.
Symbols
- f
Fission density [fissions/cm3
- ḟ
Fission rate [fissions/cm3s]
- i
Index characterising the state before bubble coalescence
- i+1
Index characterising the state after bubble coalescence
- m
Gas mass in a bubble
- p
Gas pressure in a bubble
- r
Radius of a bubble
- R
Specific gas constant
- s
Swelling, s = ΔV/V
- t
Thickness of load carrying wall of a spherical cavity
- T
Temperature [K]
- V
Volume of fuel grain
- Vo
Volume of fuel grain at begin of irradiation
- AV
Volume increase during irradiation
- γ
Surface tension
- σ
Hoop stress in a spherical bubble
- τ
Time
References
1 Hofmann, G. L. and Snelgrove, J. L.: Dispersion Fuels. In: Materials Science and Technology, ed. by Chan, R. W.; Haasen, P.; Kramer, E. J.. Volume 10 A, Nuclear Materials, Volume Editor: Frost B. R. T.. VCH Verlagsgesellschaft mbH, Weinheim, 1994Search in Google Scholar
2 Copeland, G. L.: Fuel qualificaton plan for the advanced neutron source reactor. ORNL/M-4324, July 199510.2172/113994Search in Google Scholar
3 Hofman, G. L. and Ryu, W. S.: Detailed analysis of uranium silicide dispersion fuel swelling. Proceedings of the XIIth International Meeting: Reduced Enrichement for Research and Test Reactors, Berlin, 1989, edited by Forschungszentrum Jülich GmbH.Search in Google Scholar
4 NRC: Safety Evaluation Report related to the evaluation of low-enriched uranium silicide-aluminium dispersion fuel for use in nonpower reactors. U. S. Nuclear Regulatory Commission, NUREG-1313, July 1988Search in Google Scholar
5 Olander, D. R.: Fundamental aspects of nuclear reactor fuel elements. Technical Information Center, Energy Research and Development Administration, 197610.2172/7343826Search in Google Scholar
© 2001 Carl Hanser Verlag, München
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Articles in the same Issue
- Frontmatter
- Calendar of Events
- Calendar of Events • Veranstaltungskalender
- Summaries
- Summaries/Kurzfassungen
- Notes
- Richtlinie VDI 3783 Blatt 12. Umweltmeteorologie – Physikalische Modellierung von Strömungs- und Ausbreitungsvorgängen in der atmosphärischen Grenzschicht – Windkanalanwendungen; Hrsg.: VDI Verein Deutscher Ingenieure, Kommission Reinhaltung der Luft (KRdl im VDI und DIN-Normenausschuss), Dezember 2000; 107,60 DM
- Comparison of plant efficiencies of various power conversion systems for high-temperature reactor modules
- Studies on the behaviour of a passive containment cooling system for the Indian Advanced Heavy Water Reactor
- Detonation waves in melt-coolant interaction
- Experimental study of the transient characteristics of a natural circulation loop under SBLOCA
- Calculation of the higher order eigenvalues for a homogeneous sphere using the FN method
- Books
- Safe Management of the Operating Lifetimes of Nuclear Power Plants
- Study of the possibility of high accuracy flow measurements with the pulsed neutron activation method
- The astrophysical S-factor for dd-reactions at keV-energy range
- Books
- Books • Bücher
- Monte Carlo analysis of accelerator-driven systems: Studies on spallation neutron yield and energy gain
- Subcritical nuclear systems and their stability against changes in the geometrical set-up
- Technical Notes
- An energy amplifier fluidized bed nuclear reactor concept
- An attempt to describe the swelling of U3Si 2 fuel by a simple formula
- European Commission initiative to promote technical harmonisation on risk-based decision making
- Patent
- Notes
- Note • Mitteilung
