Published October 25, 1982 | Version v1
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Calculations with the COROX-Code for Comparison with the DSNP-HTR Simulation Program

Creators

  • 1. Kernforschungsanlage Jülich GmbH, Jülich, Germany

Description

[Automatically extracted and translated] This report describes the calculations made with the COROX code for comparison with the DSNP-HTR simulation program. The calculations were carried out for a gas-cooled High Temperature Reactor concept PNP-500. For the test calculations, the transients in the primary circuit were considered for three arbitrary cases in which an increase of power, of bypass flow and after heat conditions had been assumed with no further protective actions. Due to the large heat capacity of the graphite components and the behaviour of the single-phase coolant helium, very slow changes in temperature and pressure transients occurred for long periods in the primary circuit in these theoretical cases. In the analysed time scale the ratio of computer time and problem time was less than 1:50 for the KFA Jülich's IBM computer.

Abstract (German)

[Automatisch extrahiert und übersetzt] Dieser Bericht beschreibt die mit dem COROX-Code durchgeführten Berechnungen zum Vergleich mit dem DSNP-HTR-Simulationsprogramm. Die Berechnungen wurden für ein gasgekühltes Hochtemperaturreaktorkonzept PNP-500 durchgeführt. Für die Testberechnungen wurden die Transienten im Primärkreislauf für drei willkürliche Fälle betrachtet, in denen eine Leistungssteigerung, eine Bypass-Durchflusssteigerung und Nachwärmebedingungen ohne weitere Schutzmaßnahmen angenommen wurden. Aufgrund der großen Wärmekapazität der Graphitkomponenten und des Verhaltens des einphasigen Kühlmittels Helium traten in diesen theoretischen Fällen über lange Zeiträume sehr langsame Änderungen der Temperatur- und Drucktransienten im Primärkreislauf auf. Im analysierten Zeitmaßstab lag das Verhältnis von Computerzeit zu Problemzeit bei weniger als 1:50 für den IBM-Computer der KFA Jülich.

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ISF_IB_1982-14_Rehm-Calculations with COROX-Code for Comparison with DSNP-HTR.pdf

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Additional details

Additional titles

Original title (German)
Berechnungen mit dem COROX-Code zum Vergleich mit dem DSNP-HTR-Simulationsprogramm

Publishing Information

Report number
KFA-ISF-IB-14/1982

INIS

Country of Publication
Germany
Country of Input or Organization
International Atomic Energy Agency (IAEA)
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; EXCURSIONS; F CODES; FEDERAL REPUBLIC OF GERMANY; GAS FLOW; GRAPHITE; HELIUM; HTGR TYPE REACTORS; HTR REACTOR; HTR-10 REACTOR; P CODES; PRIMARY COOLANT CIRCUITS; SPECIFIC HEAT; TRANSIENTS
Descriptors DEC
ACCIDENTS; CARBON; COMPUTER CODES; COOLING SYSTEMS; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EUROPE; EVALUATION; EXPERIMENTAL REACTORS; FLUID FLOW; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MINERALS; NONMETALS; PHYSICAL PROPERTIES; POOL TYPE REACTORS; RARE GASES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Proposed descriptors and Free-text terms
FEDERAL REPUBLIC OF GERMANY; FORSCHUNGSZENTRUM JUELICH; HTGR TYPE REACTORS;

Optional Information

Notes
Document from Juelich Preservation Project