This research is focused on the Large Break Loss of Coolant Accident (LBLOCA) analysis of the Maanshan power plant by TRACE-DAKOTA code. In the acceptance criteria for Loss of Coolant Accidents (LOCAs), there are two accepted analysis methods: conservative methodology and best estimate methodology. Compared with conservative methodology, the best estimate and realistic input data with uncertainties to quantify the limiting values i.e., Peak Cladding Temperature (PCT) for LOCAs analysis. By the conservative methodology, the PCTCM (PCT calculated by conservative methodology) of Maanshan power plant LBLOCA calculated is 1422K. On the other hand, there are six key parameters taken into account in the uncertainty analysis in this study. In PCT95/95 (PCT of 95/95 confidence level and probability) calculation, the PCT95/95 is 1369K lower than the PCTCM (1422K). In addition, the partial rank correlation coefficients between input parameters and PCT indicate that accumulator pressure is the most sensitive parameter in this study.
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4593-6
PROCEEDINGS PAPER
Best Estimate Analysis of Maanshan PWR LBLOCA by TRACE Coupling With DAKOTA
Jung-Hua Yang,
Jung-Hua Yang
National Tsing Hua University, HsinChu, Taiwan
Search for other works by this author on:
Jong-Rong Wang,
Jong-Rong Wang
Atomic Energy Council, Taoyuan, Taiwan
Search for other works by this author on:
Hao-Tzu Lin,
Hao-Tzu Lin
Atomic Energy Council, Taoyuan, Taiwan
Search for other works by this author on:
Chunkuan Shih
Chunkuan Shih
National Tsing Hua University, HsinChu, Taiwan
Search for other works by this author on:
Jung-Hua Yang
National Tsing Hua University, HsinChu, Taiwan
Jong-Rong Wang
Atomic Energy Council, Taoyuan, Taiwan
Hao-Tzu Lin
Atomic Energy Council, Taoyuan, Taiwan
Chunkuan Shih
National Tsing Hua University, HsinChu, Taiwan
Paper No:
ICONE22-30817, V003T06A033; 7 pages
Published Online:
November 17, 2014
Citation
Yang, J, Wang, J, Lin, H, & Shih, C. "Best Estimate Analysis of Maanshan PWR LBLOCA by TRACE Coupling With DAKOTA." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T06A033. ASME. https://doi.org/10.1115/ICONE22-30817
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model
ASME J of Nuclear Rad Sci (April,2016)
External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
ASME J of Nuclear Rad Sci (April,2020)
Assessment of the Code “PTCREEP” for IPHWR Pressure Tube Ballooning Study
J. Pressure Vessel Technol (February,2011)
Related Chapters
LOCA Frequencies Estimated from Operating Experience (PSAM-0282)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)