The plant dynamics and the interactions of plant systems and operator with the random evolution of parameters led to the development of dynamic reliability methodologies. The present paper approaches a dynamic PSA methodology by making use of the thermal–hydraulic model of CANDU 6 reactor, implemented in RELAP5 Mod.3.3, and of IDDA code. IDDA (Integrated Dynamic Decision Analysis) is a software code that with the help of enhanced dynamic event tree methodology provides results in terms of system unavailability. The coupling of the two above mentioned codes allows a full representation of the plant operational states, as well as of all the possible occurrence patterns that complete the spectrum of possible probability-consequence conditions. The plant transient considered for the CANDU 6 thermal–hydraulic model is the total Loss of Feed Water (LOFW) supply to the secondary side of steam generators. That is followed by depletion of water inventory and subsequent cool down via Emergency Water System (EWS). The present dynamic PSA approach reveals those situations where the correct intervention of protective equipment could bring to unexpected events. This allows taking the most appropriate decisions for the given plant configuration.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4931-6
PROCEEDINGS PAPER
Approaching Dynamic PSA Within CANDU 6 NPPs
D. Mazzini
D. Mazzini
ACTA SRL, Pisa, Italy
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M. Lontos
University of Pisa, Pisa, Italy
M. Mazzini
University of Pisa, Pisa, Italy
D. Mazzini
ACTA SRL, Pisa, Italy
Paper No:
ICONE18-29473, pp. 451-460; 10 pages
Published Online:
April 8, 2011
Citation
Lontos, M, Mazzini, M, & Mazzini, D. "Approaching Dynamic PSA Within CANDU 6 NPPs." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 3. Xi’an, China. May 17–21, 2010. pp. 451-460. ASME. https://doi.org/10.1115/ICONE18-29473
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