Advanced numerical methods for thermalhydraulics
Creators
- 1. CEA Centre d'Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique
Description
New applications have been found for advanced best estimate codes, due to the needs for industrial studies and safety studies, and due also to the appearance of new generations of computers, as powerful work stations. Thus developments have been focused on the optimization of the numerical performance of thermal-hydraulics codes based on two-fluid six equation model. The first field of investigation is to minimize the computing time. Comparisons of existing methods demonstrate that a fully implicit scheme is suitable to be optimized. The second field of investigation is to develop powerful three-dimensional module with advanced numerical method, as multistep method, conjugate gradient method for the solver and in future non-structured meshing. (authors). 6 tabs., 8 refs
Additional details
Publishing Information
- Publisher
- Centre d'Etudes de Cadarache.
- Imprint Place
- Saint-Paul-lez-Durance (France)
- ISBN
- 2-72-72-0157-5
- Imprint Title
- Transient two-phase flow: ''Current issues in system thermal-hydraulics''
- Imprint Pagination
- 609 p.
- Journal Page Range
- p. 189-200.
Conference
- Title
- CSNI specialist meeting on transient two-phase flow.
- Dates
- 6-8 Apr 1992.
- Place
- Aix-en-Provence (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 26053150
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; C CODES; HYDRAULICS; LOSS OF COOLANT; OPTIMIZATION; PWR TYPE REACTORS; REACTOR SAFETY; REWETTING; THERMODYNAMICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS