Introducing non-linearities in a homogeneous modeling of a PWR core
Creators
- 1. Ecole Centrale de Lyon (France). Mechanic Lab.
- 2. Electricite de France, Villeurbanne (France). Basic Design Dept.
Description
This article focuses upon a model of a periodic diphasic medium: a periodic beam array in a fluid; this can represent a nuclear reactor core. First, to understand the phenomena involved, the authors study the two sub-systems: a row of beams and a section of a row of beams. Then, they validate a simple fluid model which allows them to determine the important parameters of the fluid-structure interaction: the confinement parameter and of course, the fluid density. Then a homogenization technique is used to model the beam array. Thus, the number of degrees of freedom obtained being sufficiently small, it is possible to perform simulations of this complex system. This model is capable of allowing for beam bending, together with any shocks incurred during important excitations
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1784-9
- Imprint Title
- Fluid-structure interaction -- 1996. PVP-Volume 337
- Imprint Pagination
- 285 p.
- Journal Page Range
- p. 121-127.
Conference
- Title
- American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 21-26 Jul 1996.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28019027
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FINITE ELEMENT METHOD; FLUID-STRUCTURE INTERACTIONS; HOMOGENIZATION METHODS; MATHEMATICAL MODELS; NONLINEAR PROBLEMS; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-960706--.