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Title Investigation of heat transfer crisis in steam generator tube: выпускная квалификационная работа магистра: направление 14.04.01 «Ядерная энергетика и теплофизика» ; образовательная программа 14.04.01_03 «Ядерная энергетика (международная образовательная программа) / Nuclear Power Engineering (International Educational Program)»
Creators Мурорунквере Беатрис
Scientific adviser Соколова Екатерина Андреевна
Organization Санкт-Петербургский политехнический университет Петра Великого. Институт энергетики
Imprint Санкт-Петербург, 2026
Collection Выпускные квалификационные работы ; Общая коллекция
Subjects steam generator ; critical heat flux ; departure from nucleate boiling ; dry out.
Document type Master graduation qualification work
Language Russian
Level of education Master
Speciality code (FGOS) 14.04.01
Speciality group (FGOS) 140000 - Ядерная энергетика и технологии
DOI 10.18720/SPBPU/3/2026/vr/vr26-5890
Rights Доступ по паролю из сети Интернет (чтение)
Additionally New arrival
Record key ru\spstu\vkr\44899
Record create date 9/4/2026

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Critical heat flux (CHF) relates the transition from nucleate boiling to film boiling. This transition leads to a significant decrease in heat transfer efficiency of the steam generator. Therefore, the accurate prediction of CHF is essential for the safe operation of the steam generator. In this study, numerical simulation of the critical heat flux for a single tube of the steam generator has been conducted. A two-fluid Eulerian-Eulerian multiphase model together with a wall heat flux model were used to obtain wall temperature variation in a tube. Different closure models have been assessed for the prediction of CHF location. The wall temperature predicted was compared to available experimental data. The results showed that as mass fluxes increase, wall temperature variation decreases. In addition to that, the CHF location was observed at 6m, which is in agreement with the experimental results.

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