Published July 1993 | Version v1
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Treatment of the decay heat production in the reactor dynamics program TINTE

Creators

Description

The TINTE code system deals with the nuclear and the thermal transient behaviour of the primary circuit of an HTGR taking into consideration the mutual feedback effects in two-dimensional r-z-geometry. An update of the treatment of delayed heat production is presented. It is based on the German norm DIN 25485, the rules of which had to be adjusted for use in a dynamics code. For the description of the fuel element power history a substitute-histogram has been constructed from local burnup and optionally from information about shuffling of the fuel balls. As an example the depressurisation accident of a MODUL-HTR is calculated. The results obtained are very similiar to others previously reported. (orig./HP)

Availability note (English)

MF available from INIS under the Report Number.

Abstract (German)

Der Code TINTE beschreibt das nukleare und das thermische transiente Verhalten des Primaerkreises eines HTR unter Beruecksichtigung der gegenseitigen Rueckkopplungseffekte in zweidimensionaler R-Z-Geometrie. Eine Ueberarbeitung der Behandlung der Nachwaermeproduktion wird dargestellt. Dabei wird von der Deutschen Norm DIN 25485 ausgegangen, deren Vorschriften fuer die Anwendung in einem Dynamikprogramm angepasst werden mussten. Zur Beschreibung der Brennelementeleistungsgeschichte wurde ein Ersatzhistogramm aus dem lokalen Abbrand und optional aus Informationen ueber das Shuffling kugelfoermiger Brennelemente konstruiert. Als Anwendungsbeispiel wird der Druckentlastungsstoerfall beim MODUL-HTR berechnet. Die Ergebnisse sind den anderweitig bekannten sehr aehnlich. (orig./HP)

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Additional details

Additional titles

Original title (German)
Die Behandlung der Nachzerfallswaerme im Reaktordynamikprogramm TINTE

Publishing Information

Imprint Pagination
38 p.
ISSN
0944-2952
Report number
Juel--2791

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
25022743
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AFTER-HEAT; COMPUTERIZED SIMULATION; DEPRESSURIZATION; HTGR TYPE REACTORS; MODULAR STRUCTURES; PEBBLE BED REACTORS; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; RESIDUAL POWER; TRANSIENTS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; NUCLEAR POWER; POWER; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS