Published 2015 | Version v1
Book

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)

Part of:
ICAPP 2015 Proceedings

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