Development of a Dynamic Event Tree for a Pressurized Water Reactor Steam Generator Tube Rupture Event

2000 ◽  
Vol 130 (1) ◽  
pp. 27-38 ◽  
Author(s):  
Chun-Chang Chao ◽  
Chin-Jang Chang
Keyword(s):  
Steam Generator ◽  
Event Tree ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Steam Generator Tube ◽  
Water Reactor ◽  
Dynamic Event

Simulation of Small Steam Generator Tube Break (SSGTB) in a Small Pressurized Water Reactor (SPWR)

2017 ◽  
Author(s):  
Huasong Cao
Keyword(s):  
Steam Generator ◽  
System Response ◽  
Outlet Temperature ◽  
Pressurized Water Reactor ◽  
Reactor Model ◽  
Design Data ◽  
Pressurized Water ◽  
Coolant Pump ◽  
Steam Generator Tube ◽  
Water Reactor

Lots of efforts have been made to Research & Development of Small pressurized water reactors (SPWRs). Steam generator tube break occurs due to wear and corrosion frequently in the reactor. Among the breaks, Small Steam Generator Tube Break (SSGTB) is difficult to detect. Therefore, it is necessary to investigate the features of SSGTB. A small pressurized water reactor model has been established in this paper by Relap5. The model includes reactor core, pressurizer, steam generator, main coolant pump and auxiliary safety system. The core flow, pressure of pressurizer, core outlet temperature and secondary outlet steam temperature obtained based on steady-state calculation is compared with design data to verify the model correct. SSGTB is simulated by introducing a small break in the steam generator tube. The important parameters of reactor are recorded and analyzed. The procedure of SSGTB is analyzed and the system response features are summarized.

Characteristics of steam generator tube deposits in an operating pressurized water reactor

2018 ◽  
Vol 507 ◽  
pp. 371-380 ◽  
Author(s):  
Soon-Hyeok Jeon ◽  
Seokmin Hong ◽  
Hyuk-Chul Kwon ◽  
Do Haeng Hur
Keyword(s):  
Steam Generator ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Steam Generator Tube ◽  
Water Reactor

CFD Predictions of Severe Accident Steam Generator Flows in a 1/7th Scale Pressurized Water Reactor

2002 ◽  
Author(s):  
Christopher Boyd ◽  
Kelly Hardesty
Keyword(s):  
Steam Generator ◽  
Natural Circulation ◽  
Severe Accident ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Steam Generator Tube ◽  
Flow Phenomena ◽  
Experimental Values ◽  
High Degree ◽  
Side Flow

Computational Fluid Dynamics (CFD) is applied to steam generator inlet plenum mixing as part of a larger plan covering steam generator tube integrity. The technique is verified by comparing predicted results with severe accident natural circulation data [1] from a 1/7th scale Westinghouse facility. This exercise demonstrates that the technique can predict the natural circulation and mixing phenomena relevant to steam generator tube integrity issues. The model includes primary side flow paths for a single hot leg and steam generator. Qualitatively, the experimentally observed flow phenomena are predicted. The paths of the natural circulation flows and the relative flow proportions are correctly predicted. Quantitatively, comparisons are made with temperatures, mass flows, and other parameters. All predictions are generally within 10% of the experimental values. Overall, there is a high degree of confidence in the CFD technique for prediction of the relevant flow phenomena associated with this type of severe accident sequence.

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