Analysis of mechanical HCDA consequences in the coolant loops for demonstration of primary containment integrity in SNR 300
Creators
- 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.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10430274
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; DEFORMATION; EQUATIONS OF MOTION; HYDRODYNAMICS; MATHEMATICAL MODELS; NUMERICAL SOLUTION; PIPES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; SNR REACTOR; STRAINS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CONTAINMENT; COOLING SYSTEMS; DIFFERENTIAL EQUATIONS; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS