Published April 1976 | Version v1
Report Restricted

Experimental investigations of the LWR fuel rod behaviour in loss-of-coolant accidents

Creators

  • 1. Kraftwerk Union A.G., Erlangen (F.R. Germany)

Description

The following investigations were made in experimental parameter studies: 1) Under which conditions does a fuel can burst, and 2) what is the interdependence between the fuel can expansion before bursting and the fuel rod loads of the emergency cooling system. The maximum expansions, in particular, were determined at given pressure, temperature, heat-up rate, and residence time. (HP)

Abstract (German)

In experimentellen Parameterstudien wurde untersucht 1) unter welchen Bedingungen das Huellrohr birst und 2) wie die Huellrohrdehnung vor dem Bersten von den Brennstabbelastungen der Notkuehlung abhaengt. Insbesondere wurden die maximalen Dehnungen bestimmt bei vorgegebenem Druck, Temperatur, Aufheizrate und Standzeit. (HP)

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Original title (German)
Experimentelle Untersuchungen zum LWR-Brennstabverhalten beim Kuehlmittelverlust-Stoerfall

Publishing Information

Imprint Title
Safety aspects of LWR fuel rods
Imprint Pagination
p. 25-53.
Report number
AED-Conf--75-773-000

Conference

Title
Technical meeting of the Fachgruppe 'Brennelemente' of the KTG.
Dates
14 Nov 1975.
Place
Erlangen, F.R. Germany.

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
7279207
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CREEP; DEFORMATION; EXPANSION; FUEL CANS; FUEL RODS; HEATING; LOSS OF COOLANT; PRESSURE DEPENDENCE; PWR TYPE REACTORS; RUPTURES; SIMULATION; TEMPERATURE DEPENDENCE
Descriptors DEC
ACCIDENTS; FAILURES; FUEL ELEMENTS; MECHANICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
18 figs.; 7 refs. Imprint:Sicherheitsaspekte beim LWR-Brennstab.
Secondary number(s)
AED-Conf--75-773-002.