Published 1977 | Version v1
Book

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 consequances 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. (Auth.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85062 7
Imprint Title
Structural mechanics in reactor technology
Journal Page Range
v. E p. E4/5 1-9.

Conference

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