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SATURN-FS 1: A computer code for thermo-mechanical fuel rod analysis

Abstract

The SATURN-FS code was written as a general revision of the SATURN-2 code. SATURN-FS is capable to perform a complete thermomechanical analysis of a fuel pin, with all thermal, mechanical and irradiation-based effects. Analysis is possible for LWR and for LMFBR fuel pins. The thermal analysis consists of calculations of the temperature profile in fuel, gap and in the cladding. Pore migration, stoichiometry change of oxide fuel, gas release and diffusion effects are taken into account. The mechanical modeling allows the non steady-state analysis of elastic and nonelastic fuel pin behaviour, such as creep, strain hardening, recovery and stress relaxation. Fuel cracking and healing is taken into account as well as contact and friction between fuel and cladding. The modeling of the irradiation effects comprises swelling and fission gas production, Pu-migration and irradiation induced creep. The code structure, the models and the requirements for running the code are described in the report. Recommendations for the application are given. Program runs for verification and typical examples of application are given in the last part of this report. (orig.) [Deutsch] SATURN-FS stellt eine Weiterentwicklung des Brennstabrechenprogramms SATURN-2 dar. Es erlaubt eine umfassende thermomechanische Brennstabanalyse unter Beruecksichtigung aller thermischer, mechanischer und bestrahlungsbedinger Effekte.  More>>
Publication Date:
Sep 01, 1993
Product Type:
Technical Report
Report Number:
KFK-5203
Reference Number:
SCA: 210100; 210200; 210500; 360100; 220900; PA: DEN-94:0F4419; EDB-94:062764; NTS-94:019430; SN: 94001185739
Resource Relation:
Other Information: PBD: Sep 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; 22 GENERAL STUDIES OF NUCLEAR REACTORS; FUEL RODS; S CODES; FUEL PINS; FUEL CANS; COMPUTER CODES; BWR TYPE REACTORS; PWR TYPE REACTORS; LMFBR TYPE REACTORS; MANUALS; MECHANICAL PROPERTIES; FISSION PRODUCT RELEASE; DIFFUSION; SWELLING; IRRADIATION; FUEL-CLADDING INTERACTIONS; 210100; 210200; 210500; 360100; 220900; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; POWER REACTORS, BREEDING; METALS AND ALLOYS; REACTOR SAFETY
OSTI ID:
10141582
Research Organizations:
Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Materialforschung; Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Nukleare Sicherheitsforschung
Country of Origin:
Germany
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 0303-4003; Other: ON: DE94758742; TRN: DE94F4419
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
DEN
Size:
236 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Ritzhaupt-Kleissl, H J, and Heck, M. SATURN-FS 1: A computer code for thermo-mechanical fuel rod analysis. Germany: N. p., 1993. Web.
Ritzhaupt-Kleissl, H J, & Heck, M. SATURN-FS 1: A computer code for thermo-mechanical fuel rod analysis. Germany.
Ritzhaupt-Kleissl, H J, and Heck, M. 1993. "SATURN-FS 1: A computer code for thermo-mechanical fuel rod analysis." Germany.
@misc{etde_10141582,
title = {SATURN-FS 1: A computer code for thermo-mechanical fuel rod analysis}
author = {Ritzhaupt-Kleissl, H J, and Heck, M}
abstractNote = {The SATURN-FS code was written as a general revision of the SATURN-2 code. SATURN-FS is capable to perform a complete thermomechanical analysis of a fuel pin, with all thermal, mechanical and irradiation-based effects. Analysis is possible for LWR and for LMFBR fuel pins. The thermal analysis consists of calculations of the temperature profile in fuel, gap and in the cladding. Pore migration, stoichiometry change of oxide fuel, gas release and diffusion effects are taken into account. The mechanical modeling allows the non steady-state analysis of elastic and nonelastic fuel pin behaviour, such as creep, strain hardening, recovery and stress relaxation. Fuel cracking and healing is taken into account as well as contact and friction between fuel and cladding. The modeling of the irradiation effects comprises swelling and fission gas production, Pu-migration and irradiation induced creep. The code structure, the models and the requirements for running the code are described in the report. Recommendations for the application are given. Program runs for verification and typical examples of application are given in the last part of this report. (orig.) [Deutsch] SATURN-FS stellt eine Weiterentwicklung des Brennstabrechenprogramms SATURN-2 dar. Es erlaubt eine umfassende thermomechanische Brennstabanalyse unter Beruecksichtigung aller thermischer, mechanischer und bestrahlungsbedinger Effekte. Es koennen sowohl LWR- als auch LMFBR-Brennstaebe analysiert werden. Die thermische Analyse umfasst die Berechnung der Temperaturprofile in Brennstoff, Spalt und Huelle sowie die Betrachtung von Porenwanderung, der Aenderung des Sauerstoff- zu Metall-Verhaeltnisses im Oxidbrennstoff, von Gasfreisetzung und bestrahlungsbedingten Diffusions-Effekten. Die mechanische Modellierung erlaubt die instationaere Analyse des elastischen und nichtelastischen Brennstabverhaltens wie Kriechen, Verfestigung, Materialerholung, Spannungsrelaxation. Aufreissen und Ausheilen des Brennstoffs sowie Kontakt- und Reibungseffekte zwischen Huelle und Brennstoff werden beschrieben. Die Modellierung der Bestrahlungseffekte umfasst Schwellen, Spaltgasproduktion und -freisetzung sowie bestrahlungsbedingtes Kriechen. Dieser Bericht beinhaltet die Beschreibung der verwendeten mathematischen Modelle, der Programmstruktur und eine Benutzeranleitung zum Gebrauch des Programms. Programmlaeufe zur Absicherung und typische Anwendungsbeispiele sind im letzten Teil dieses Handbuchs enthalten. (orig.)}
place = {Germany}
year = {1993}
month = {Sep}
}