1. Steam Generation 1.1. General Characteristics 1.2. Circulation in Boiling Water Reactors 1.3. Steam Generation in CANDU Reactors 1.4. Steam Generators 1.5. Steam Generator for PWR and CANDU Systems 1.6. Heat Transfer 2. Steam Generator Operation 2.1. Swelling and Shrinking 2.1.1. Steady State Swelling and Shrinking 2.1.2. Transient Swelling and Shrinking 2.2. Level Control 2.3. Carryover 2.4...

One of the actual problems of safe and reliable operation of NPP units with pressurized reactors is the development of tube plugging criterion for steam generator tubing. The basis for plugging criterion development is associated with existence of flaws with critical sizes at steam generator tubes. For effective application of this criterion the conditions of flaw instability should be analyzed...

Poor control of the nuclear steam generator (SG) water level of pressurized Water Reactor can lead to frequent reactor shutdowns. In addition, the steam generator is a highly complex, nonlinear and time-varying system and its parameters vary with operating conditions. The dynamics of a nuclear steam generator is very different according to the power levels and changes as time goes on. Therefore...

in this paper, first a sensitivity analysis of parameters affecting the performance of the steam generator is performed. this process includes the pinch temperature difference and the gas velocity (width of the hrsg) as the operating parameter and geometrical parameters (fin’s thickness, fin’s height, number of fins in each inch, tube transverse pitch) for each pressure parts is carried out, an...

In early February 2000, primary-to-secondary tube leakage ranging from one to four gallons per day (gpd) was detected in steam generator (SG) No. 24. On February 15, 2000, while the unit was operating at 99% power, SG leakage rapidly increased from 4 gpd to greater than 75 gallons per minute (gpm). The reactor was manually tripped 13 minutes later, and the faulted steam generator was isolated o...

The paper is devoted to solution of some problems in nuclear power station generating unit intellectual control systems using genetic algorithms on the basis of control system model development, optimizations methods of their direct quality indices and improved integral quadratic estimates. Some mathematical vector models were obtained for control system multicriterion quality indices with due ...

Nuclear energy is one of the most important clean energy on earth presently. The steam generator secondary side is the key device of nuclear power station. As an important branch of special robot, nuclear robot is the most convenient and effective mean to inspect the steam generator. This paper describes one robot system which could help users inspecting tubes and locating the robot inside the ...

This report describes our investigation of steam generator behavior during a postulated tube rupture accident. Our study was performed using the steam generator, thermal-hydraulic analysis code THERMIT-UTSG. The purpose of our work was to provide an independent assessment of the Los Alamos National Laboratory system code TRAC-PF1 with respect to steam generator tube rupture analysis. Results of...

A steam generator is the major component of a nuclear power plant and its integrity is crucial for the nuclear safety. Steam generator tube eddy current bobbin inspections are periodically performed for utility to detect tube degradation. Scaled deposits on the steam generator tubes cause the performance degradation problem and the thickness of the outer diameter tube surface can be measured us...

the paper is devoted to solution of some problems in nuclear power station generating unit intellectual control systems using genetic algorithms on the basis of control system model development, optimizations methods of their direct quality indices and improved integral quadratic estimates. some mathematical vector models were obtained for control system multicriterion quality indices with due ...