Published September 1975 | Version v1
Report Restricted

Analysis of transient overpower accidents for the SNR-300 Mark-1 and Mark-1A cores

Creators

  • 1. Societe Belge pour l'Industrie Nucleaire, Brussels
  • 2. Kernforschungszentrum Karlsruhe (F.R. Germany). Projekt Schneller Brueter

Description

This comparative study of a hypothetical ramp accident for the fresh SNR-300 Mark 1 and Mark 1A cores shows the influence of the different core design parameters on the energy stored in the fuel at the end of the disassembly phase. Calculations are performed with the CARMEN/KADIS code system and differences are carefully analysed and documented. The larger fuel inventory, the flatter power distribution and worth curves together with the more positive sodium void reactivity are mainly responsible for the more energetic excursion in the Mark 1A core disruptive accident. (orig.)

Availability note (English)

MF available from INIS under the Report Number.

Abstract (German)

Die vorliegende Studie vergleicht die Energiefreisetzung eines hypothetischen, schweren Leistungsstoerfalls mit einer 5 /sec Einleitungsrampe fuer den Mark 1 und den Mark 1A Kern des SNR-300. Mit dem CARMEN/KADIS Code-System werden die Unfallverlaeufe simuliert und die wesentlichen Entwurfsparameter, die die Energiefreisetzung beeinflussen, analysiert. Die groessere Brennstoffmasse, die flachere Leistungsverteilung und die flacheren Wertkurven sowie die hoehere Natriumvoidreaktivitaet sind die Hauptursachen fuer die Erhoehung der Energiefreisetzung beim Mark 1A core. (orig.)

Files

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Additional details

Publishing Information

Imprint Pagination
77 p.
Report number
KFK--2115

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
7241026
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
DESIGN BASIS ACCIDENTS; EXCURSIONS; POWER DENSITY; REACTIVITY COEFFICIENTS; REACTIVITY INSERTIONS; REACTOR CORES; SNR REACTOR; TRANSIENTS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTIVITY; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS

Optional Information

Notes
16 figs.; 5 tabs.; 5 refs.