The 2002 International RELAP5 Users Seminar was held September 4-6 in Park City Utah at the Park City Marriott Hotel. Thirty-eight people attended representing five countries, with twenty four papers presented encompassing development, validation, and application activities using RELAP5-3D as well as other versions. Of particular interest this year was the emphasis on coupling RELAP5 to other codes and analyses of Generation IV nuclear reactor designs. Click on one of the following titles to view a paper or presentation.
Paper Title
Presenter
Organization
Status of RELAP5-3D Development and Application Status
Gary Johnsen
INL
A Mass and Energy Conserving Form of Explicit Coupling For Use With RELAP5-3D
Walt Weaver
Incorporation of COBRA-TF in an Integrated Code System with RELAP5-3D Using Semi-Implicit Coupling
David Aumiller
Bettis
Extensions of SCDAP/RELAP5-3D for Analyses of Advanced LWRs and HTGRs
Larry Siefken
Adaptive Modeling of Thermal Non-Equilibrium in Two-Phase Flow Simulation Systems
Kurt Schneider
Framatome ANP
The Generation IV R&D Roadmap Overview
Ralph Bennett
Coupling of MELCOR to Other Codes under an Executive Program using PVM Message Exchange
Randy Cole
Sandia National Laboratory
Using the Coupled MELCOR/RELAP5 Codes for Simulation of the Edward's Pipe
Sal Rodriguez
Breaking the Barrier Between System and Component Modeling: Coupling RELAP5-3D and FLUENT
Greg Nurnburg
FLUENT
FLUENT/RELAP5-3D Coupled Code
Richard Schultz
A New Assessment of the LOFT-Wyle Blowdown Test WSB03R Using RELAP5-3D
Bernie Bandini
A New Assessment of the Large-Tank General Electric Swell Problem Using RELAP5-3D
RELAP5/MOD3.2 Analysis of INSC Standard Problem INSCSP-R7: Void Fraction Distribution over RBMK Fuel Channel Height for Experiments Performed in the ENTEK BM Test Facility
Pat Garner
Argonne National Laboratory
Thermal-hydraulic code assessment activities of the Technical University of Catalonia
Lluis Batet
Technical University of Catalonia (Spain)
RBMK SP-2 Validation Results (KS PH Rupture Simulation)
Bruce Schmitt
PNNL
Development and Assessment of Appendix K Version of RELAP5-3D for LOCA Licensing Analysis
Thomas Liang
INER
RELAP5-3D Conversion to FORTRAN 90
George Mesina
Analysis of Transients in an Actinide Burner Reactor Cooled by Forced Convection of Lead Bismuth
Cliff Davis
Performance and Safety Studies for Multi-Application, Small, Light Water Reactor
Jim Fisher
RELAP5 Applications in MGR Waste Package Analysis Methods
John A. McClure
Bechtel SAIC (Yucca Mt.)
SCDAP/RELAP5-3D©: A State-of-the-Art Tool for Severe Accident Analyses
Darrell Knudson
SCDAP/RELAP5-3D©-CONTAIN Linkage
Joy Rempe
RELAP5-3D User Problems
Rich Riemke
RELAP5 Input Builder GIUs THUMB and Pygmalion
Michael Cutforth
Idaho State University
