Published September 1977
| Version v1
Report
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Development of the analytical design of strongly loaded fuel rods with zircaloy claddings for advanced pressurized water reactors
Creators
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.)
Description
The computer program CARO describing the in pile behaviour of fuel rods, is used in the design of fuel rods of pressurized water reactors. For the improvement of CARO several computational methods and models have been developed, particularly models for the description of the following mechanisms: heat transfer in the fuel-cladding gap, fission gas release, changes in fuel density due to high temperature restructuring, irradiation induced densification and swelling. In this report these models and the computer program CARO are described. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Bei der Auslegung von Brennstaeben fuer Druckwasserreaktoren wird das Rechenprogramm CARO eingesetzt, das das Brennstabverhalten waehrend der Einsatzzeit im Reaktor beschreibt. Zur Weiterentwicklung von CARO wurde eine Reihe von Rechenmethoden und Modellen erarbeitet. Insbesondere wurden Modelle zur Beschreibung folgender Mechanismen entwickelt: Waermeuebergang im Spalt zwischen Brennstoff und Huellrohr, Spaltgasfreisetzung, Brennstoffdichteaenderung durch Hochtemperatur-Verdichtung, strahlungsinduziertes Nachsintern und Schwellen. Im vorliegenden Bericht werden die genannten Modelle und das Programm CARO beschrieben. (orig.)
Files
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Additional titles
- Original title (German)
- Weiterentwicklung der analytischen Auslegung von hochbelasteten Brennstaeben mit Zircaloy-Huellrohren fuer fortgechrittene Druckwasserreaktoren
Publishing Information
- Imprint Pagination
- 36 p.
- Report number
- BMFT-FB-K--78-02
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 9395838
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; DENSITY; FISSION PRODUCT RELEASE; FUEL DENSIFICATION; FUEL RODS; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; M CODES; OPTIMIZATION; PLANNING; PWR TYPE REACTORS; SWELLING
- Descriptors DEC
- COMPUTER CODES; DEFORMATION; ENERGY TRANSFER; FUEL ELEMENTS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 19 figs.; 1 tab.; 6 refs.