HEMERA: a 3D computational chain for PWR safety analysis
Creators
- 1. Institut de Radioprotection et de Surete Nucleaire, BP 17 - 92262 Fontenay-aux-Roses Cedex (France)
- 2. Commissariat a l'energie atomique, Nuclear Energy Division, Systems and structures modelling department, Reactors studies and applied mathematic service, Centre de Saclay, 91 191 Gif sur Yvette Cedex (France)
Description
In the framework of their collaboration to develop a system to study reactor transients in 'safety-representative conditions', IRSN and CEA have launched the development of a fully coupled 3D computational chain, called HEMERA (Highly Evolutionary Methods for Extensive Reactor Analyses), based on the French SAPHYR code system, composed by APOLLO2, CRONOS2 and FLICA4 codes, and the system code CATHARE. It includes cross sections generation, steady-state, depletion and transient computation capabilities in a consistent approach. Multi-level and multi-dimensional models are developed to account for neutronics, core thermal-hydraulics, fuel thermal analysis and system thermal-hydraulics, dedicated to best-estimate simulations and sensitivity analysis. Currently Control Rod Ejection (REA) and Main Steam Line Break (MSLB) accidents are investigated. The HEMERA system is presently applied to French PWR. The present paper outlines the main physical phenomena to be accounted for in such a coupled computational chain with significant time and space effects. A selection of results is presented along with a comparison of the available levels of simulation 3D, ranging from assembly-wise to pin-wise in the core. (authors)
Additional details
Publishing Information
- Publisher
- Paul Scherrer Institut - PSI
- Imprint Place
- Villigen PSI (Switzerland)
- ISBN
- 978-3-9521409-5-6
- Imprint Pagination
- 8 p.
Conference
- Title
- International Conference on the Physics of Reactors 'Nuclear Power: A Sustainable Resource'
- Acronym
- PHYSOR'08
- Dates
- 14-19 Sep 2008
- Place
- Interlaken (Switzerland)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- France
- INIS RN
- 41116033
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; CALCULATION METHODS; CONTROL ELEMENTS; CROSS SECTIONS; PWR TYPE REACTORS; SAFETY; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; SIMULATION; STEADY-STATE CONDITIONS; STEAM LINES; THERMAL ANALYSIS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; PIPELINES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.; proceedings are available as a CD-ROM on request to info'at'physor08.ch