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Park City Meeting Papers and Presentations

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	INL
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	INL
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	INL
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	Sandia National Laboratory
Breaking the Barrier Between System and Component Modeling: Coupling RELAP5-3D and FLUENT	Greg Nurnburg	FLUENT
FLUENT/RELAP5-3D Coupled Code	Richard Schultz	INL
A New Assessment of the LOFT-Wyle Blowdown Test WSB03R Using RELAP5-3D	Bernie Bandini	Bettis
A New Assessment of the Large-Tank General Electric Swell Problem Using RELAP5-3D	Bernie Bandini	Bettis
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	INL
Analysis of Transients in an Actinide Burner Reactor Cooled by Forced Convection of Lead Bismuth	Cliff Davis	INL
Performance and Safety Studies for Multi-Application, Small, Light Water Reactor	Jim Fisher	INL
RELAP5 Applications in MGR Waste Package Analysis Methods	John A. McClure	Bechtel SAIC (Yucca Mt.)
SCDAP/RELAP5-3DŠ: A State-of-the-Art Tool for Severe Accident Analyses	Darrell Knudson	INL
SCDAP/RELAP5-3DŠ-CONTAIN Linkage	Joy Rempe	INL
RELAP5-3D User Problems	Rich Riemke	INL
RELAP5 Input Builder GIUs THUMB and Pygmalion	Michael Cutforth	Idaho State University

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Last modified: October 8, 2002.