Abstract
The replacement of steam generators in a pressurised water reactor (PWR) requires an adaptation of the normal operating conditions imposed by modified characteristics of the replaced steam generators (RSGs). To cover the cost of steam generator replacement, plant uprate is often considered. This is made possible by a significant improvement of the heat exchange characteristics of the SGs, and also by modification of the position of the turbine control valve. The present paper discusses the methodology that has been developed by Tractebel to solve this problem for most of the up-to-date PWRs that are limited by the departure from nucleate boiling (DNB) phenomenon (boiling crisis). A code has been developed, validated and applied to two units in Belgium, respectively Doel 3 and Tihange 1, for which it has been decided to replace the steam generators. This code is founded on the basic principle that for most DNB-limiting class-2 accidents, the maximum reactor power and reactor inlet temperature may not violate either the overpower limit (currently 118% of nominal power), or the DNB-ratio criterion in the course of this accident. The code allows the designer to assess the influence on the operating conditions of the various key safety parameters, as well as of the basic assumptions that are necessary to conduct the thermalhydraulic design work. Examples of such investigations are given in this paper. Special emphasis is put on the thermal-hydraulic (TH) design procedure, the plant principal TH key parameters, as well as the features of the new SGs. The development of the DNBOPT code was also motivated by the wish to perform audit and sensitivity calculations, as well as to confirm calculations performed by the SG supplier.
Published Version
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