[en] The invention refers to the process monitoring which requires a high standard of efficiency and reliability. It particularly concerns the monitoring of the vital processes of the nuclear reactor system for generating electric energy. Apart from the nuclear reactor, such reactor systems include auxiliary appliances such as steam generators, pressurizing systems, feed water heaters, turbines, etc. The invention applies totally to the monitoring of nuclear reactor systems and, with a view to facilitating the understanding of this invention by dealing with the concrete monitoring difficulties, this submission is, to a large extent, restricted to the monitoring difficulties of the operating processes of nuclear reactor systems

[en] By the use of a procedure for on-site testing of nuclear reactor instruments it should be possible to judge their ability to guarantee the reactor safety and availability at the moment of divergence or during operation. Such a procedure must therefore be created as a work implement for the quick and reliable installation of electronic devices necessary for nuclear reactor control and supervision. A standard document is proposed for this purpose, allowing a ''test programme'' to be set up before the equipment is installed on the site

No abstract available

No abstract available

[en] Many technical solutions have been proposed for controlling the neutron flux in a reactor, among them, controlling by means of channels filled with neutron absorbers in various states of aggregation. The present paper considers the possibility of employing channels filled with layered structures of neutron-transparent and neutron-absorbing substances whose content is determined by the constant of a two-phase equilibrium reaction which is temperature-dependent. 12 refs

[en] The attention of manufacturers of control and monitoring materials is attracted on the possible improvements to be effected in control board reading using a more rational arrangement of monitoring stations

No abstract available

[en] One primary concern for design of safety systems for reactors is the time response of external detectors to changes in the core. This paper describes a way to estimate the time delay between the core power production and the external detector response using Monte Carlo calculations and suggests a technique to measure the time delay. The Monte Carlo code KENO-NR was used to determine the time delay between the core power production and the external detector response for a conceptual design of the Advanced Neutron Source (ANS) reactor. The Monte Carlo estimated time delay was determined to be about 10 ms for this conceptual design of the ANS reactor

[en] This report presents a review of the basic techniques developed over the recent years for the optimum supervision and detection/location of failures in dynamic technological systems such as nuclear reactors, aircrafts, etc. Regarding the optimum supervision problem the following policies are considered: optimum selection of supervision frequency, optimum supervision policies, optimum selection of sequential tests, and finally the effect of supervision capability upon the system availability. Regarding the optimum detection/location/identification of failures the following techniques are briefly presented: majority technique, failure sensitive filter technique, generalized maximum likelihood technique, output estimation error technique, dynamic redundancy technique with Luenberger observer, and finally jump processes technique. Some examples and comments on open problems for further research are also presented. (author)

[en] Among other Westinghouse three-loop plants, the Tihange plant has the highest linear power density. Severe control systems have thus been developed. The reactivity control system, power distribution control and axial power distribution monitoring system are described