Improvements and Validation of the System Code TRACE for Lead and Lead-Alloy Cooled Fast Reactors Safety-Related Investigations (NUREG/IA-0421)
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Publication Information
Manuscript Completed: January 2013
Date Published: February 2013
Prepared by:
Wadim Jaeger, Victor Hugo Sanchez Espinoza
Karlsruher Institute of Technology (KIT)
Institute for Neutron Physics and Reactor Technology (INR)
Hermann-von-Helmholtz-Platz 1
76344, Eggenstein-Leopoldshafen, Germany
A. Calvo, NRC Project Manager
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)
Published by:
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Availability Notice
Abstract
This report deals with the validation of the system code TRACE related to lead and lead-alloy cooled nuclear systems. This validation process made in necessary to revise routines of the TRACE source code in order to make lead as a coolant available, and to add functions for heat transfer in bundles cooled with liquid metals. Several experimental as well as theoretical benchmarks were selected to test, on the one hand side, the existing physical models related to liquid metals, and, on the other hand side, the new implemented functions and routines. The results for the different investigations are in good agreement to the experimental data or the other codes. The present analysis showed that the revision of the TRACE models was necessary and that the changes yield better results.
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