Diagnostics of the critical heat flux state of a VVER reactor based on a channel steaming model

• Main Author: Svetlana A. Kachur
• Format: Article
• Language: English
• Published: National Research Nuclear University (MEPhI) 2019-06-01
• Series: Nuclear Energy and Technology
• Subjects: Nuclear reactor; critical heat f
• Online Access: https://nucet.pensoft.net/article/36475/download/pdf/

The purpose of the study is to develop a model for predicting the process of a critical heat flux state with the VVER reactor core channel steaming. The model describes the dynamics of the nuclear reactor behavior in conditions of uncertainty, which are typical of abnormal situations, based on information on the process of heat exchange in the core process channels. The use of the proposed model leads to an increase in the speed of response due to a simplified procedure to calculate the parameters of the heat exchange process in the reactor core. The quality of the reactor state assessment is improved through the prediction of the heat exchange process parameters and determination of the critical heat flux parameters in the core prior to the onset of surface boiling the potentiality of which is not predicted in modern VVER in-core monitoring systems. A modification of the mathematical model has been proposed which offers the simplest possible way of using the advantages of neural networks in diagnostics. The model can be used to develop systems for diagnostics of in-core anomalies and systems for adaptive control of the VVER-type reactor thermal power.