System for Neutronic and Thermalhydraulic Diagnostics of Channel Type Reactor Parameters

Abstract

This paper presents several advances in mathematical models and computer codes intended for operational support of RBMK reactors. The primary goal of the deve1apment is to check the correctness of local changes in the flux and power distributions with time. Mathematical algorithms for diagnostics of a variety of safety related parameters were developed. A specialised diagnostic and monitoring system based on the confluent analysis of measured data and results of neutronic and thermal-hydraulic calculations of a reactor me was designed. A multi level algorithm for diagnostics is triggered if certain disagreement between parameters related to calculated and measured data is observed.