High-temperature Mechanical Analysis of Discharge Pipeline of Pressurizer
DOI:
https://doi.org/10.54097/hset.v71i.12369Keywords:
Supercharger, piping, mechanical analysis.Abstract
The severe accident is the beyond basis design accident due to several initial faults. The discharge pipeline of pressurizer is mainly used for pressure relief and evacuation of hydrogen in the primary circuit in severe accident. It can reduce the possibility of high-pressure core melt and the explosion of hydrogen. But in severe accident, the highest temperature of gas in the pipeline can reach 1200℃, which far exceeds the design temperature of pressurized water reactor. So it may cause the buckling or rupture of the pipeline. The pipeline may loss its discharge function. In this passage, we study the resistance of the discharge pipeline to high temperature in severe accident from the aspects of severe accident situation, high-temperature mechanical properties of pipeline material, the temperature field and stress of the pipeline, the evaluation of the stress and so on. In order to demonstrate the function of a certain nuclear power plant discharge pipeline, RCC-MR which is suitable for the high-temperature evaluation, is choose to evaluate the stress, the creep and the buckling of the pipeline. The results of the evaluation show that the discharge pipeline in this nuclear power plant can meet the functional requirements in the severe accidents.
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References
MAO Qing, WANG Wei. The Stress Analysis Evaluation and Pipe Support Layout for Pressurizer Discharge System, Nuclear Power Engineering, 21 (2000) 117-120.
Liu Tao, Yu Yu, Tong Jiejuan, et. Severe Accident Sequence Screening Criteria for Nuclear Power Plant, Science & Technology Review, 27 (2009) 24-27.
Santos J F D, Garzón C M, Tschiptschin A P. Improvement of the cavitation erosion resistance of an AISI 304L austenitic stainless steel by high temperature gas nitriding, Materials Science & Engineering A, 382 (2004) 378–386.
Kilian R. Materials Reliability Program: Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water (MRP-137), Office of Scientific & Technical Information Technical Reports, 2004:139-151.
Sun Jining. ANSYS CFX convective heat transfer numerical simulation basic application tutorial [M]. National Defense Industry Press, 2010.
Zhang Jingzhou, Chang Haiping. Heat transfer science [M]. Science Press, 2015.RCC-MR design and construction rules for mechanical components of FBR nuclear lands. Paris, AFCEN, 2007.
ASME Boiler and Pressure Vessel Code, Section III, Subsection NH, 2007.
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