Abstract
Information on the VVER-440 has been used for testing the agreement between the actual and design operation conditions, for evaluating in case of a disturbance of design operation mode as well as for testing and adjustment of design programs for the calculation of the energy-release field distribution over the core. Activation measurements on operating reactors form the basis of a library of neutron-flux distributions with core height which gives an idea of the variation of these distributions with changes of the heat power, of control-element position, of the fuel burnup, and of the boric acid concentration. A figure shows a cartogram of the first fuel charging of the VVER-440 reactor with dry channel arrangement. Examples of the relative distribution of the copper-wire activity on the first block are given. Safety and control systems were improved, and an extended operational in-reactor monitor was provided. The interrogation, amplification, conversion, and input of signals from in-reactor monitoring sensors to the computer are performed with the use of equipment built in conformity with the ''Vector'' standard.
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