Published July 1, 1991 | Version v1
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FRESCO-II: Program for Calculating Fission Product Release from an HTR Spherical Fuel Element under Normal Operation and Core Heat-Up Accident - User Manual

Creators

  • 1. Institut für Sicherheitsforschung und Reaktortechnik

Description

[Automatically extracted and translated] The FRESCO-II program calculates the behavior of fission products in an HTR spherical fuel element under normal operation and core heat-up accident conditions. It numerically solves the Fick's diffusion equation, considering factors like temperature-dependent particle defects and sorption at the graphite-coolant interface.

Abstract (German)

[Automatisch extrahiert und übersetzt] Das Rechenprogramm FRESCO-II beschreibt das Spaltproduktverhalten in einem kugelförmigen HTR-Brennelement im Normalbetrieb sowie im Falle einer Kernaufheizung. Es löst numerisch die Fick'sche Diffusionsgleichung unter Berücksichtigung von temperaturabhängigen Partikeldefekten und Sorption an der Grenzfläche zwischen Graphit und Kühlgas.

Files

ISR_IB_1991-04a_Verfondern-FRESCO-II Spaltproduktfreisetzung aus Kugelbrennelement - Benutzerhandbuch.pdf

Files (15.0 MB)

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Additional details

Additional titles

Original title (German)
FRESCO-II: Programm zur Berechnung der Spaltproduktfreisetzung aus einem HTR-Kugelbrennelement im Normalbetrieb und Kernaufheizstörfall - Benutzerhandbuch

Publishing Information

Report number
KFA-ISR-IB-04/1991

INIS

Country of Publication
Germany
Country of Input or Organization
International Atomic Energy Agency (IAEA)
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Descriptors DEI
AFTER-HEAT; COOLANTS; DIFFUSION EQUATIONS; FEDERAL REPUBLIC OF GERMANY; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL ELEMENTS; FUEL PARTICLES; GRAPHITE; HTGR TYPE REACTORS; HTR REACTOR; HTR-10 REACTOR; REACTOR OPERATION; SORPTION; SPHERICAL CONFIGURATION; TEMPERATURE DEPENDENCE
Proposed descriptors and Free-text terms
FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; HTGR TYPE REACTORS;

Optional Information

Notes
Document from Juelich Preservation Project