Published 1977 | Version v1
Miscellaneous Restricted

Analysis of mechanical HCDA consequences in the coolant loops for demonstration of primary containment integrity in SNR 300

  • 1. Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)

Description

The demonstration of the accomodation of the mechanical consequences of a hypothetic core disruptive accident (HCDA) within the primary system is an essential objective in the safety assessment for SNR-300. For this purpose a mathematical model has been developed, in which the pressure pulse propagation in fluid-filled piping systems is calculated. This model takes into account the compressibility of the fluid as well as the elastic-plastic deformation of the pipe walls. It is the special aim of this work to estimate the attenuation of pressure peaks by elastic-plastic response of the pipe walls and to calculate the remaining strains. The basic system of partial differential equations includes the conservation laws for mass and momentum and the equations of state for the fluid and the pipe wall material. Additionally, the equation of motion for the pipe wall is provided, which considers the inertia of structure response after the pressure loading. The stress is described in a one-dimensional way. Axial stresses and strains are neglected. The numerical solution of the differential equations is carried out by an explicit extended Lax-Wendroff difference-scheme with the help of an intermediate step. The accuracy of the implemented calculation models is examined using the results of experiments. First of all, pressure wave experiments are taken, where the rising pressure pulse is so chosen, that the response of the pipe wall material lies exclusively within the elastic region of the diagram. These investigations have been carried out by INTERATOM. The comparison between measured and calculated values shows an excellent agreement of experiment and calculation

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Additional details

Publishing Information

Imprint Pagination
E 4/5, 9 p.
Report number
INIS-mf--4592

Conference

Title
4. International conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, Calif., USA.

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
10421104
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; DEFORMATION; ELASTICITY; MATHEMATICAL MODELS; PIPES; PLASTICITY; PRESSURE DEPENDENCE; REACTOR CORE DISRUPTION; SNR REACTOR; STRAINS; TIME DEPENDENCE
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SODIUM COOLED REACTORS; TENSILE PROPERTIES