Browse > Article
http://dx.doi.org/10.1016/j.net.2021.04.018

The detection and diagnosis model for small scale MSLB accident  

Wang, Meng (College of Nuclear Science and Technology, Naval University of Engineering)
Chen, Wenzhen (College of Nuclear Science and Technology, Naval University of Engineering)
Publication Information
Nuclear Engineering and Technology / v.53, no.10, 2021 , pp. 3256-3263 More about this Journal
Abstract
The main steam line break accident is an essential initiating event of the pressurized water reactor. In present work, the fuzzy set theory and the signal-based fault detection method has been used to detect the occurrence and diagnosis of the location and break area for the small scale MSLB. The models are validated by the AP1000 accident simulator based on MAAP5. From the test results it can be seen that the proposed approach has a rapid and proper response on accident detection and location diagnosis. The method proposed to evaluate the break area shows good performances for small scale MSLB with the relative deviation within ±3%.
Keywords
MSLB; Diagnosis; Break area; Location;
Citations & Related Records
연도 인용수 순위
  • Reference
1 J. Raines, R. Hammersley, R. Henry, J. Blaisdel, M. Bonaca, Y. Khalil, MARS-An accident management tool, in: Specialist Meeting on Severe Accident Management and Training, Norvay, Halden, 1993.
2 M. Marseguerra, E. Enrico Zio, P. Piero Baraldi, A fuzzy modeling approach to the identification of transients in nuclear components, Ann. Nucl. Energy 31 (2004) 2093-2112.   DOI
3 G. Vayssier, P. Fantoni, L. Borondo, R. Martinez, B. Krajnc, N. Dessars, J. Husarcek, J. Bahna, A perspective on computerized severe accident management operator support SAMOS, in: ANS Annual Meeting, Nevada, Reno, 2006.
4 B. Foad, A. Yamamoto, T. Endo, Uncertainty and regression analysis of the MSLB accident in PWR based on unscented transformation and low rank approximation, Ann. Nucl. Energy 143 (2020) 107493.   DOI
5 T. Taminami, R. Kubota, T. Fujiwara, N. Yamane, Y. Takizawa, Development of emergency response support system for accident management, in: Second OECD Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2), France, Lyon, 1997.
6 M.J. Zavisca, M. Khatib-Rahbar, H. Esmaili, R. Schulz, ADAM: an accident diagnostic, analysis and management SystemdApplications to severe accident simulation and management, in: 10th International Conference on Nuclear Engineering, American Society of Mechanical Engineers, USA, Arlington, 2002.
7 M. Khatib-Rahbar, M. Zavisca, H. Esmaili, E. Cazzoli, U. Schmocker, G. Schoen, R. Schulz, Accident diagnostic, analysis and management (ADAM) system applications to severe accident management, in: OECD/NEA Severe Accident Management (SAM) Workshop on Operator Training and Instrumentation Capabilities, France, Lyon, 2001.
8 K.H. Yoo, J.H. Back, M.G. Na, S. Hur, H. Kim, Smart support system for diagnosing severe accidents in nuclear power plants, Nucl. Eng. Tech. 50 (2018) 562-569.   DOI
9 R.M. Sanda, M.P. Veira, European Clearinghouse: Report on Leaks and Cracks of Reactor Coolant Pressure Boundary, Join Research Center, 2014, ISBN 978-92-79-44422-7.
10 L.H. Chiang, E.L. Russell, R.D. Braatz, Fault Detection and Diagnosis in Industrial Systems, Springer, New York, 2001.
11 M. Negnevitsky, Artificial Intelligence: a Guide to Intelligent Systems, Pearson Education, 2005.
12 P. Smith, R.W. Zappe, Valve Selection Handbook, in: Engineering Fundamentals for Selecting the Right Valve Design for Every Industrial Flow Application, fifth ed., Gulf Professional Publishing, 2004.
13 M. Wang, W.Z. Chen, Y.Y. Tao, MAAP5 simulation of AP1000 severe accident induced by pressurizer safety valve stuck-open, Ann. Nucl. Energy 152 (2021) 107991.   DOI
14 P.F. Fantoni, A. Sorensen, G. Mayer, CAMS: a computerised accident management system for operator support during normal and abnormal conditions in nuclear power plants, in: Second OECD Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2), France, Lyon, 1997.
15 S.Y. Park, K.I. Ahn, SAMEX: a severe accident management support expert, Ann. Nucl. Energy 37 (2010) 1067-1075.   DOI
16 L.C. Dai, Y.S. Chen, Y.R. Yuann, Short-term pressure and temperature MSLB response analyses for large dry containment of the Maanshan nuclear power station, Nucl. Eng. Des. 280 (2014) 86-93.   DOI
17 J.W. Hines, E. Davis, Lessons learned from the U.S. nuclear power plant online monitoring programs, Prog. Nucl. Energy 46 (2005) 176-189.   DOI
18 S. Melliani, O. Oscar Castillo, Recent Advances in Intuitionistic Fuzzy Logic Systems: Theoretical Aspects and Applications, Springer International Publishing, 2019.
19 American Petroleum Institute, Sizing, Selection, and Installation of Pressure-Relieving Devices-Part 1: Sizing and Selection, seventh ed., API Publishing Service, 2000.