3D-non-linear dynamic analysis of PWR reactor vessel internal with SYSTUS - formulation of a new friction element
Creators
- 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Paris-la-Defense (France)
Description
A 3D structural dynamic analysis of PWR internals, and vessel under a loss of coolant accident loading (LOCA) has been performed with FRAMATOME's FEM code 'SYSTUS'. The structural response is computed by using the non linear modal superposition method. It consists of analysing a highly non-linear system including unidirectional impacts, concentric impacts and friction elements. (45 geometric non-linearities). A COULOMB friction element has been developped to take into account the relative behaviour between rods and the frame of fuel assemblies. The theoretical description of friction element is described in annex. Friction modelization has a high level influence on results because of the important mass of rods (1/3 of reactor). Extension to a 3D modal gives a more realistic motion of internals and vessel. Results show a good agreement with a previous 2D calculation using direct integration method. (orig.)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-763-8
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. B
- Imprint Pagination
- 637 p.
- Journal Page Range
- p. 407-413.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19028827
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EQUATIONS OF MOTION; FINITE ELEMENT METHOD; FLUID-STRUCTURE INTERACTIONS; FRICTION; LOSS OF COOLANT; PWR TYPE REACTORS; RESPONSE FUNCTIONS; S CODES; STRUCTURAL MODELS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; FUNCTIONS; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS