Published June 28, 2002 | Version v1
Report

ECORA - Evaluation of Computational Methods for Reactor Safety Analysis

  • 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS), mbH, Forschungsgelaende, D-85748 Garching (Germany)

Description

There were three motivations behind the ECORA Project: - the shortcomings of 0-D system codes in the simulation of 3-D, local flow and heat transfer phenomena, - increased interest in the application of 3-D CFD software as supplement to system codes, - high safety requirements in the nuclear industry required consistent standards for the use and assessment of CFD software. The purpose of ECORA was therefore: - to establish performance criteria for the assessment of CFD software, - to establish Best Practice Guidelines for application and use of CFD software, with the following objectives: - assessment of CFD applications in reactor safety: flows in containment (PANDA experiments) and flows in primary system (UPTF experiments) - Best Practice Guidelines for reactor safety: starting point (ERCOFTAC Best Practice Guidelines), adaptation to CFD application for nuclear safety, extension to assessment of experimental data - recommendations for improvements of CFD software, - network of European 'Centres of Competence for CFD Applications in Reactor Safety'. Currently, there were twelve partners in the ECORA Project, representing nine European countries. The Project was scheduled to last until September 2004. Ms Scheuerer then described the work programme and project structure, the Best Practice Guidelines for CFD simulations, the procedures for quantifying errors, applications of Best Practice Guidelines, Best Practice Guidelines for experimental data, applications to primary system, UPTF and PANDA data. Her conclusions were the following: - the Project had led to the improvement of the quality of CFD calculations in reactor safety, through: the ECORA Best Practice Guidelines, the assessment of shortcomings and the improvement of mathematical models. - It had also led to higher acceptance of CFD in reactor safety. - The next step was the establishment of European 'Centres of Competence for CFD Applications in reactor Safety'

Part of:
Proceedings of the exploratory meeting of experts to define an action plan on the application of computational fluid dynamics (CFD) codes to nuclear reactor safety problems

Additional details

Publishing Information

Imprint Title
Proceedings of the exploratory meeting of experts to define an action plan on the application of computational fluid dynamics (CFD) codes to nuclear reactor safety problems
Imprint Pagination
180 p.
Journal Page Range
p. 171-180
Report number
NEA-CSNI-R--2002-16

Conference

Title
Exploratory meeting of experts to define an action plan on the application of computational fluid dynamics (CFD) codes to nuclear reactor safety problems
Dates
15-16 May 2002
Place
Aix-en-Provence (France)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39090900
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; CONTAINMENT; ERRORS; EVALUATION; HEAT TRANSFER; MATHEMATICAL MODELS; NUCLEAR INDUSTRY; PERFORMANCE; RADIATION PROTECTION; REACTOR SAFETY; RECOMMENDATIONS; SIMULATION; STANDARDS
Descriptors DEC
ENERGY TRANSFER; INDUSTRY; SAFETY

Optional Information