AREVA main steam line break fully coupled methodology based on CATHARE-ARTEMIS - 15496
- 1. AREVA NP, Tour AREVA, Cedex 16, 92084 Paris La Defense (France)
Description
The CATHARE code developed since 1979 by AREVA, CEA, EDF and IRSN is one of the major thermal-hydraulic system codes worldwide. In order to have at disposal realistic methodologies based on CATHARE for the whole transient and accident analysis in Chapter 15 of Safety Reports, a coupling with the code ARTEMIS was developed. ARTEMIS is the core code in AREVA's new reactor simulator system ARCADIA, using COBRA-FLX to model the thermal-hydraulics in the core. The Fully Coupled Methodology was adapted to the CATHARE-ARTEMIS coupling to perform Main Steam Line Break studies. This methodology, originally applied to the MANTA-SMART-FLICA coupling, is dedicated to Main Steam Line Break transients at zero power. The aim of this paper is to present the coupling between CATHARE and ARTEMIS and the application of the Fully Coupled Methodology in a different code environment. (authors)
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 2036-2046
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49004999
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; COUPLING; NEUTRON TRANSPORT THEORY; REACTOR ACCIDENT SIMULATION; THERMAL HYDRAULICS; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTORS; SIMULATION; TRANSPORT THEORY
Optional Information
- Notes
- 9 refs.; This record replaces 48095394