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Information × Registration Number 0221U107187, 0119U001065 , R & D reports Title Study of thermohydraulic processes in the elements of heat removal systems for advanced nuclear engineering facilities popup.stage_title Head Pysmennyi Yevhen M, Registration Date 28-12-2021 Organization National Technical University of Ukraine "Igor Sikorsky Kyiv Polytechnic Institute" popup.description2 The aim of the work is to ensure efficient and reliable operation of heat dissipation and thermal protection systems for promising nuclear power facilities by improving the accuracy of determining and forecasting the conditions of critical heat transfer regimes, increasing the heat transfer capacity of systems and developing scientifically sound technological and circuit design solutions for their improvement. An original approach to solving the problem of using implicit empirical correlations for the characteristics of thermohydraulic processes is proposed in the paper on promising new generation nuclear reactors with coolant supercritical parameters (SCP). The issue of using turbulence models in engineering practice to predict nonlinear heat transfer is comprehensively considered, and for the first time a simple adaptation of temperature near-wall functions was proposed, which has significantly improved the forecast of deteriorating heat transfer. A simple approach to "indication" of representative temperature regimes in the context of structural strength of promising active zones has been implemented, which significantly improves the possibilities of optimizing their layout. The regularities of the influence of structural parameters on the characteristics of porous metal - fiber capillary structures (MFCS) are determined. Dependences for determining the maximum heat transfer capacity of evaporation-condensation systems (ECS) are obtained and methods for increasing their maximum heat transfer capacity are developed. Technological processes of creation and new protected solutions of passive ECS with MFCS for strengthening of barriers of safety in nuclear power are developed. Some of the research was conducted within the framework of IAEA international programs, and their results are included in IAEA reporting documents. The results of the work are the basis for research and development, development of technical documentation for heat transfer devices and systems. Product Description popup.authors Vozniuk Maksym Mikhailovich Gershuni Olexander Naumovich Nikolaenko Yuri Egorovich Nishchyk Olexander Pavlovich Pis'mennyi Eugene Mykolayovych Razumovskiy Viktor Grigorovich Filonov Vladislav Vitaliyovych popup.nrat_date 2022-03-09 Close