The Thermal Hydraulics of Tube Support Fouling in Nuclear Steam Generators

Particulate Fouling and its Effect on U-Tube Steam Generator Thermal Performance

A multiple-node SIMULINK model of a U-tube steam generator (UTSG) has been developed so as to simulate the UTSG dynamics or responses to various defects, including fouling. UTSG responses to different events, such as reduced heat transfer area, change in heat transfer coefficient at different axial nodes, change in tube material conductivity, and the change of steam valve coefficients have been...

Wavelet network controller for nuclear steam generators

Poor control of steam generator water level is the main cause of unexpected shutdowns in nuclear power plants. Particularly at low powers, it is a difficult task due to shrink and swell phenomena and flow measurement errors. In addition, the steam generator is a highly complex, nonlinear and time-varying system and its parameters vary with operating conditions. Therefore, it seems that design o...

Development of Eddy-Current Probes for the Evaluation of Magnetite in the Support-Plate Crevices of Nuclear Steam Generators

Eddy current technique has played an important role in the understanding of the corrosion behavior of steam generator components. Until recently, its role has been primarily in the evaluation of the condition of the heat exchanger tubes. Recent developments have led to the use of this technique for detecting corrosion of the carbon steel plates supporting the tubes. The detection and quantifica...

Steam Generators and Steam Distribution Networks

Thermal Hydraulics Design Limits

The following discussion of PWR steady state and transient design limits is extracted from the theses of Carter Shuffler and Jarrod Trant while the BWR discussion is extracted from Paolo Ferroni's thesis (covers steady state only). These limits are a simplified and narrower discussion than the relevant NRC standard review plan you will also be referred to. All materials are directly extracted f...