Analysis of Reliability of Automatic Core Protection Function of the Reactor v-412 in Response to Local Parameters: Maximum Linear Power, Departure From Nucleate Boiling Ratio

Abstract

The research subject is finding an engineering solution for V-412 core automatic protection during operation in both steady-state and transient conditions within ICIS using local parameters (i.e. maximum linear power, departure from nucleate boiling ratio). Such engineering solution will be implemented by safety system software-hardware (PTK-Z) on the basis of signals coming from in-core neutron flux detectors, temperature sensors, primary coolant flow and coolant pressure transducers. Calculated survey of possibility to use Kalman filters or corrective filter to eliminate time delay in SPND signals was carried out. The inaccuracy in the method of maximum linear power monitoring was determined. This work shows that the solution was found using the practice of in-core instrumentation, and ICIS designing and operation with improved metrology, reliability and time parameters and using advanced data communication technologies intended for important challenges of the world market, and as a response to standards.

Review of the Latest Opinions and Theories Regarding the Development of Technical and Agricultural Sciences

“…the pollution of zirconium components of fresh FAs with halogenide-ions (Cl -, Bror I -) could lead to increase of general corrosion of zirconium alloy E-110 and development of local types of corrosion on its (pittings, corrosion cracks). This needs the special precautionary measures to be taken during storage of fresh fuel at nuclear power plant (NPP) located in the coastal ocean region to minimize both the amount, and the possibility of getting the sea salts on fuel surface [287][288][289][290].…”

“…Among the chlorides, the basic dissolved compounds are: NaCl (27 g/L), MgCl 2 (6 g/L), KCl and CaCl 2 (1 g/L each) [283][284][285][286][287]. Namely such compounds and in such ratio are recommended to be taken for preparation of solution in climatic tests of the equipment under the conditions of sea (salt) fog [288][289][290].…”

Analysis of Calculation Model for Primary Coolant Fission Products

“…This increase in activity (the spike-effect) is caused by an additional release of gaseous and volatile fission products that are accumulated in the fuel-clad gap of leaky fuel elements. The most intensive release of fission products is observed in the course of decreasing 100 % power of the reactor (by more than 30 %) [1], [5].…”

Analysis of the effect of pollution of component surfaces as a result of possible contact of fresh nuclear fuel with sea atmosphere on corrosion

“…the pollution of zirconium components of fresh FAs with halogenide-ions (Cl -, Bror I -) could lead to increase of general corrosion of zirconium alloy E-110 and development of local types of corrosion on its (pittings, corrosion cracks). This needs the special precautionary measures to be taken during storage of fresh fuel at nuclear power plant (NPP) located in the coastal ocean region to minimize both the amount, and the possibility of getting the sea salts on fuel surface [7], [10]- [12].…”