Bushehr Nuclear Power Plant (BNPP) originally designed by German KWU and then modified by Russian companies is approaching commissioning. In this paper, the reliability of Emergency Core Cooling System (ECCS) of the new design is compared with the older one using both deterministic and probabilistic methods. The reliability of both systems is calculated in case of occurrence of Large Loss of Coolant Accident (Large LOCA). The new Russian design is based on the original KWU Convoy design and the applied modifications have improved its reliability. To perform the reliability analysis the event tree/fault tree method is used and the calculations are done by IAEA computer code PSAPACK. The results show that the applied modifications such as, increase of redundancy from 4 × 50% to 4 × 100%, change of cool down route, fuel storage pool cooling in all four trains have reduced the ECCS unavailability from 5.9 E−4 to 1.7 E−4. Furthermore, based on the results it is shown that both designs comply well with the IAEA recommendations on Probabilistic Safety Criteria (PSC) and INSAG-3 requirements.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Assessment of Reliability of Emergency Core Cooling System (ECCS) of Bushehr Nuclear Power Plant
Mohammad Sotoudeh,
Mohammad Sotoudeh
Amirkabir University of Technology, Tehran, Iran
Search for other works by this author on:
Kamran Sepanloo
Kamran Sepanloo
Atomic Energy Organization of Iran, Tehran, Iran
Search for other works by this author on:
Mohammad Sotoudeh
Amirkabir University of Technology, Tehran, Iran
Kamran Sepanloo
Atomic Energy Organization of Iran, Tehran, Iran
Paper No:
ICONE17-75931, pp. 729-733; 5 pages
Published Online:
February 25, 2010
Citation
Sotoudeh, M, & Sepanloo, K. "Assessment of Reliability of Emergency Core Cooling System (ECCS) of Bushehr Nuclear Power Plant." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 729-733. ASME. https://doi.org/10.1115/ICONE17-75931
Download citation file:
12
Views
Related Proceedings Papers
Related Articles
A Reliability-Based Optimization Framework for Planning Operational Profiles for Unmanned Systems
J. Mech. Des (May,2024)
Reliability Analysis by Mean-Value Second-Order Expansion
J. Mech. Des (June,2012)
Reliability Analysis of Offshore Production Facilities Under Arctic Conditions Using Reliability Data From Other Areas
J. Offshore Mech. Arct. Eng (May,2014)
Related Chapters
Application of PRA Methodology to ECCS Suction Strainers Blockage Issue (PSAM-0152)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Nuclear Reactor Safety Systems
Nuclear Reactor Thermal-Hydraulics: Past, Present and Future
Reliability Analysis and Evaluation of Gas Supply System
International Conference on Mechanical and Electrical Technology 2009 (ICMET 2009)