SG (steam generator) is one of the most important equipment in fast reactors, the experience in design and operation of fast reactor worldwide show that failures of SG occurred frequently and often caused serious consequences, therefore it’s necessary to conduct reliability analysis on SG in design phase. FMEA (Failure Mode Effect Analysis) is used to identify all potential failure modes and filter out main failure modes. Then, qualitative analysis and quantitative calculation are carried out to evaluate main failure modes. Next, reliability of SG can be obtained by conducting Latin Hypercube Sampling. Analysis results show that the leakage probability of SG in 20 years is 0.130 219, and the most sensitive factor is the quality of weld in the junction of tubes and tube plate, and the SG meet its reliability requirement.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5143-2
PROCEEDINGS PAPER
Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor
Huang Yi,
Huang Yi
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Zhang Tian-yi,
Zhang Tian-yi
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Wang Jun,
Wang Jun
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Yuan Yu-chen,
Yuan Yu-chen
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Dong Xin
Dong Xin
Dongfang Electric, Cheng Du, China
Search for other works by this author on:
Huang Yi
China Institute of Atomic Energy, Beijing, China
Zhang Tian-yi
China Institute of Atomic Energy, Beijing, China
Wang Jun
China Institute of Atomic Energy, Beijing, China
Yuan Yu-chen
China Institute of Atomic Energy, Beijing, China
Dong Xin
Dongfang Electric, Cheng Du, China
Paper No:
ICONE26-81183, V001T01A002; 5 pages
Published Online:
October 24, 2018
Citation
Yi, H, Tian-yi, Z, Jun, W, Yu-chen, Y, & Xin, D. "Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor." Proceedings of the 2018 26th International Conference on Nuclear Engineering. London, England. July 22–26, 2018. V001T01A002. ASME. https://doi.org/10.1115/ICONE26-81183
Download citation file:
31
Views
Related Proceedings Papers
Related Articles
Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
J. Pressure Vessel Technol (April,2012)
An Efficient Methodology for the Reliability Analysis of Corroding Pipelines
J. Pressure Vessel Technol (August,2014)
SFTA-Based Approach for Safety/Reliability Analysis of Operational Use-Cases in Cyber-Physical Systems
J. Comput. Inf. Sci. Eng (September,2017)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Reliability Analysis and Evaluation of Gas Supply System
International Conference on Mechanical and Electrical Technology 2009 (ICMET 2009)