Hladilni sistem za hlajenje tehnoloških komponent v jedrski elektrarni

Strgulec, Oton (author), Sekavčnik, Mihael (mentor)

Osrednja naprava hladilnega sistema za hlajenje tehnoloških in varnostnih komponent jedrskih elektrarn je CC (angl. Component Cooling) prenosnik toplote, s katerim odvajamo odvečno toploto iz tehnološkega postrojenja v vseh režimih delovanja jedrske elektrarne. V nalogi obravnavamo določevanje osnovnih tehničnih karakteristik prenosnika toplote na podlagi štirih različnih metod, ki temeljijo na a) termodinamičnem, b) hidravličnem popisu prenosnika toplote z empiričnimi nastavki in c) prostorskih zahtev obstoječega stanja v jedrski elektrarni. Rezultati vseh metod kažejo, da izbira gradiva cevi v prenosniku toplote nima velikega vpliva na preneseni toplotni tok (prehod toplote). Izračunani prehod toplote U je z menjavo gradiva cevi znotraj prenosnika toplote, med metodami v povprečju manjši za 1,4 % glede na obstoječe stanje.

• Language: Slovenian
• Keywords: jedrske elektrarne, jedrska elektrarna Krško, hladilni sistemi, cevno-plaščni prenosniki toplote, tehnološke in varnostne komponente, erozivna korozija
• Work type: Master's thesis/paper
• Typology: 2.09 - Master's Thesis
• Organization: FS - Faculty of Mechanical Engineering
• Place of publishing: Ljubljana
• Publisher: [O. Strgulec]
• Year: 2020
• Number of pages: XVIII, 132 str.
• PID: 20.500.12556/RUL-121802
• UDC: 621.311.25:621.039.534(043.2)
• COBISS.SI-ID: 39091971
• Publication date in RUL: 30.10.2020

STRGULEC, Oton, 2020, Hladilni sistem za hlajenje tehnoloških komponent v jedrski elektrarni [online]. Master’s thesis. Ljubljana : O. Strgulec. [Accessed 17 March 2025]. Retrieved from: https://repozitorij.uni-lj.si/IzpisGradiva.php?lang=eng&id=121802

Secondary language

• Language: English
• Title: Component Cooling System in Nuclear Power Plant

Abstract

The main component of the Component Cooling System in Nuclear Power Plants is the heat exchanger, which dissipates excessive heat from the system amid all the power plant operating regimes. In this thesis there are basic technical characteristics of the heat exchanger determined, based on 4 different methods, which are founded on a) the thermodynamic b) hydraulic definition of the heat exchanger and c) spatial requirements of the existing state in the Nuclear Power Plant. The results of all the methods indicate, that the selection of the tube material inside the heat exchanger does not affect drastically on the total heat transferred. Calculated coefficient of total heat transfer U is within each method on average smaller for 1,4 %, according to the present state of the heat exchanger, due to switching relevant materials.

• Keywords: nuclear power plants, nuclear power plant Krško, cooling systems, shell-tube heat exchangers, component cooling systems, erosion corrosion