magistrsko delo magistrskega študijskega programa II. stopnje Strojništvo
Oton Strgulec (Author), Mihael Sekavčnik (Mentor)

Abstract

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.

Keywords

magistrske naloge;jedrske elektrarne;jedrska elektrarna Krško;hladilni sistemi;cevno-plaščni prenosniki toplote;tehnološke in varnostne komponente;erozivna korozija;

Data

Language: Slovenian
Year of publishing:
Typology: 2.09 - Master's Thesis
Organization: UL FS - Faculty of Mechanical Engineering
Publisher: [O. Strgulec]
UDC: 621.311.25:621.039.534(043.2)
COBISS: 39091971 Link will open in a new window
Views: 408
Downloads: 126
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Other data

Secondary language: English
Secondary title: Component Cooling System in Nuclear Power Plant
Secondary 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.
Secondary keywords: master thesis;nuclear power plants;Nuclear power plant Krško;cooling systems;shell-tube heat exchangers;component cooling system;erosion corrosion;
Type (COBISS): Master's thesis/paper
Study programme: 0
Embargo end date (OpenAIRE): 1970-01-01
Thesis comment: Univ. Ljubljana, Fak. za strojništvo
Pages: XVIII, 132 str.
ID: 12114462