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scientific master's theses
Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe
Zagreb: University of Zagreb, Faculty of Electrical Engineering and Computing, 2003. urn:nbn:hr:168:508337
Bajs, Tomislav
University of Zagreb
Faculty of Electrical Engineering and Computing

Institutional repository: FER Repository

Cite this document

Bajs, T. (2003). Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe (Scientific master's theses). Zagreb: University of Zagreb, Faculty of Electrical Engineering and Computing. Retrieved from https://urn.nsk.hr/urn:nbn:hr:168:508337

Bajs, Tomislav. "Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe." Scientific master's theses, University of Zagreb, Faculty of Electrical Engineering and Computing, 2003. https://urn.nsk.hr/urn:nbn:hr:168:508337

Bajs, Tomislav. "Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe." Scientific master's theses, University of Zagreb, Faculty of Electrical Engineering and Computing, 2003. https://urn.nsk.hr/urn:nbn:hr:168:508337

Bajs, T. (2003). 'Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe', Scientific master's theses, University of Zagreb, Faculty of Electrical Engineering and Computing, accessed 19 December 2024, https://urn.nsk.hr/urn:nbn:hr:168:508337

Bajs T. Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe [Scientific master's theses]. Zagreb: University of Zagreb, Faculty of Electrical Engineering and Computing; 2003 [cited 2024 December 19] Available at: https://urn.nsk.hr/urn:nbn:hr:168:508337

T. Bajs, "Model za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe", Scientific master's theses, University of Zagreb, Faculty of Electrical Engineering and Computing, Zagreb, 2003. Available at: https://urn.nsk.hr/urn:nbn:hr:168:508337

Metadata
TitleModel za analizu prijelaznih pojava u lakovodnom reaktoru integralne izvedbe
Title (english)Model for the Transient Analysis of the Integral Reactor Concept
AuthorTomislav Bajs
MentorNikola Čavlina (mentor)
Committee memberDanilo Feretić (predsjednik povjerenstva)
Committee memberNikola Čavlina (član povjerenstva)
Committee memberŽeljko Bogdan (član povjerenstva)
Committee memberDavor Grgić (član povjerenstva)
GranterUniversity of Zagreb
Faculty of Electrical Engineering and Computing
Zagreb
Defense date and country2003, Croatia
Scientific / art field,
discipline and subdiscipline		TECHNICAL SCIENCES
Electrical Engineering
Universal decimal classification
(UDC)		621 - Mechanical engineering. Nuclear technology. Machinery
Abstract
Međunarodni konzorcij pod rukovodstvom Westighouse/BNFL-a sastavljen od industrije, sveučilišta, razvojnih i elektroprivrednih poduzeća razvija projekt modularnog, integralnog, lakovodnog reaktora srednje snage, IRIS (akronim od International Reactor Innovative and Secure – Međunarodni, inovativni i sigurni reaktor). Odlike su IRIS-a inovativna, napredna inženjerska rješenja s osloncem na dokazanu tehnologiju lakovodnih reaktora. Sistemski program za termohidrauličke proračune RELAP5/Mod3.3 odabran je za analize prijelaznih pojava u reaktoru IRIS. Razvijena je nodalizacija IRIS reaktora za program RELAP5/Mod3.3 koja uključuje osnovne kontrolne i zaštitne funkcije. Zaštitni sustavi, posebice sustav za hlađenje u nuždi i sustav za boriranje jezgre u nuždi također su ugrađeni u model. Razvijeni model kvalificiran je za stacionarno stanje. Analizirani su akcidenti loma glavnog parovoda i male izljevne nezgode. Rezultati proračuna iskorišteni su za kvalitativnu ocjenu primjenjivosti modela za analize prijelaznih pojava reaktora IRIS.
Abstract (english)
An international consortium of industry, laboratory, university and utility establishments, led by Westinghouse/BNFL, is developing a modular, integral, light water cooled, medium power reactor, the International Reactor Innovative and Secure (IRIS). IRIS features innovative, advanced engineering, but it is firmly based on the proven technology of Pressurized Water Reactors (PWR). RELAP5/Mod3.3 code has been selected as the main system code for the transient analysis of the IRIS reactor. A nodalization for the RELAP5/Mod3.3 code of the reference IRIS design has been developed with a basic set of protective functions and controls. Engineered Safety Features were also implemented, in particular the Emergency Heat Removal System and Emergency Boration Tank. Developed model has been qualified at the steady state level. The analysis of the Main Steam Line Break (MSLB) and Small Break Loss of Coolant Accident (SBLOCA) were performed. The results of the calculations were used to qualitatively evaluate applicability of the developed model for the transient analysis of the IRIS reactor.
Keywords
Keywords (english)
Languagecroatian
URN:NBNurn:nbn:hr:168:508337
Study programmeTitle: Postgraduate master programme in electrical engineering
Study programme type: university
Study level: postgraduate
Academic / professional title: Magistar znanosti elektrotehnike (Magistar znanosti elektrotehnike)
Catalog URLhttp://lib.fer.hr:8080/cgi-bin/koha/catalogue/detail.pl?biblionumber=28993
Type of resourceText
Extent83 str ; 30 cm
File originBorn digital
Access conditionsClosed access
Terms of useLicence In copyright icon
Created on2019-04-11 12:58:36