The RELAP5-3D1 program solves a complex system of governing, closure and special process equations to model the underlying physics of nuclear power plants. For SQA (software quality assurance), the code must be verified and validated (V&V) to ensure proper performance before release to users. The physical models are validated against data from experiments and plants and verified against specifications for the computer code. In addition to physics, programs such as RELAP5-3D perform numerous other functions and processes that should also be checked to guarantee correct results. Functions include input, output, data management, and user interaction, while processes include restart, time-step backup, code coupling, and multi-case processing. Previous articles have covered the verification of the physical models, restart, and backup through extremely accurate and automated sequential verification applied on a comprehensive suite of test cases to ensure that code changes produced no unintended consequences. New developments have enabled the verification of multi-case and multi-deck processing. These features are frequently used in parameter and code sensitivity studies and therefore must be verified as working correctly. Both theory and application are presented.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5003-9
PROCEEDINGS PAPER
Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies Available to Purchase
George L. Mesina,
George L. Mesina
Idaho National Laboratory, Idaho Falls, ID
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Nolan Anderson
Nolan Anderson
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
George L. Mesina
Idaho National Laboratory, Idaho Falls, ID
Nolan Anderson
Idaho National Laboratory, Idaho Falls, ID
Paper No:
ICONE24-61040, V003T09A084; 7 pages
Published Online:
October 25, 2016
Citation
Mesina, GL, & Anderson, N. "Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 3: Thermal-Hydraulics. Charlotte, North Carolina, USA. June 26–30, 2016. V003T09A084. ASME. https://doi.org/10.1115/ICONE24-61040
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