The 2006 International RELAP5 Users Seminar was held August 16-18th in West Yellowstone, Montana. Thirty participants from the U.S., Europe and Asia attended. There were 21 papers presented encompassing development, validation, and application activities using RELAP5-3D as well as other versions. The following list of presentations is in the chronological order in which they were presented at the conference. Click on one of the following titles to view the presentation.
Paper Title
Authors
Organization
Status of RELAP5-3D Development and Applications
Gary Johnsen
INL
Modeling Compact Counter-Flow Heat Exchangers with RELAP5-3D
Dave Aumiller
Bettis
Enhancements to the RELAP5-3D Conduction Model
Walt Weaver
FORTRAN 90 Conversion of RELAP5-3D
George Mesina
Restructuring RELAP5-3D
Joshua Hykes
RELAP5 Analysis of Operator’s Response to Nuclear Power Station Blackout
Alex Matev
ESKOM
Status of NGNP Methods R&D
Richard Schultz
Status of the activities related to the use of RELAP5-3D at the Technical University of Catalonia
Lluis Batet
U. of Catalonia
SNAP Graphical User Interface
Ken Jones
APT
Development of a Gas Cooled Fast Reactor RELAP5-3D thermal-hydraulic model
Carlos Parisi
U. of Pisa
Modeling EBR-II LOFWS and LOHSWS using RELAP5-3D
Cliff Davis
Applicability of RELAP5-3D for Thermal-Hydraulic Analyses of a Sodium-Cooled Actinide Burner Test Reactor
RELAP5-3D Coolability Calculation for Irradiated, Dried Np/Pu Targets in Proposed Storage Rack Configuration
Jim Fisher
Licensing Analysis of RPV and BOP Blowdown with RELAP5-3D/K for Lungmen ABWR Containment Design
Thomas Liang
INER
Use of RELAP5-3D for Dynamic Analysis of Closed-Loop Brayton Cycle Coupled to A Nuclear Reactor
Larry McCann
The use of RELAP5-3D code in the OECD/NEA VVER-1000 CT-1 and CT-2 Benchmark
Performance Assessment of the Two-Phase Pump Degradation Model in RELAP5-3D
RELAP5 Modeling of the INL-OSU GRTS Facility
Brian Jackson
Oregon State University
AREVA’s Activities Related to VHTR Thermal-Hydraulic Analysis Using RELAP5-3D
Bob Martin
Areva NP
The use of RELAP5-3D code in the OECD/NEA BFBT Benchmark
Development of a 3D Neutron Kinetic-Thermal-hydraulic model for an RBMK reactor by RELAP5-3D code.
