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Ocena vpliva vhodnih parametrov v analizi toplotnega prehodnega pojava pod tlakom v reaktorski posodi Nuklearne elektrarne Krško v primeru majhne izlivne nezgode
Bašič, Ivica (Author), Crnjac, Peter (Author)

URLURL - Presentation file, Visit http://www.dlib.si/details/URN:NBN:SI:doc-3NIZSM9H This link opens in a new window

Abstract
V prispevku smo se osredotočili na deterministično metodo izbire mejnih primerov ohladitve reaktorske posode Nuklearne elektrarne Krško pri posredovanju sistema za zasilno hlajenje sredice med malo izlivno nezgodo. Za osnovni izračun smo izbrali malo izlivno nezgodo z zlomom velikosti ustreznega premera 50,8 mm v hladni veji in termohidravlični računalniški program RELAP5/MOD3.3. V nadaljnji študiji smo s spreminjanjem parametrov sistema za zasilno hlajenje sredice za zlom na istem mestu simulirali se tri scenarije male izlivne nezgode. Namen studije je bil oceniti, koliko so mejni izbrani vhodni parametri nevarni za toplotni prehodni pojav pod tlakom v reaktorski tlačni posodi.

Language:Slovenian
Keywords:nuclear reactor, pressure vessels, pressurized thermal chock, SB LOCA accident
Work type:Not categorized (r6)
Tipology:1.04 - Professional Article
Organization:FS - Faculty of Mechanical Engineering
Year:2006
Publisher:Association of Mechanical Engineers and Technicians of Slovenia et al.
Number of pages:str. 404-418
Numbering:Letn. 52, št. 6
UDC:621.039.577:621.039.58
ISSN on article:0039-2480
COBISS.SI-ID:9485851 Link is opened in a new window
Views:429
Downloads:128
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Record is a part of a journal

Title:Strojniški vestnik
Shortened title:Stroj. vestn.
Publisher:Zveza strojnih inženirjev in tehnikov Slovenije [et al.], = Association of Mechanical Engineers and Technicians of Slovenia [et al.]
ISSN:0039-2480
COBISS.SI-ID:762116 This link opens in a new window

Secondary language

Language:Unknown
Title:The estimated influence of the input parameters in the analysis of the PTS in the core of the PWR Krško NPP in the case of the SB LOCA
Abstract:
This paper focuses on the deterministic method of limiting cases of the Krsko Nuclear Power Plant (NPP) reactor pressure-vessel cooling by mediating the emergency core-cooling system (ECCS) during a small-break loss-of-coolant accident (SB LOCA). The SB LOCA accident with the equivalent diameter break of50.8 mm in the cold leg and the RELAP5/MOD3.3 computer code were selected for the basic calculation. In further study, by modifying the ECCS's parameters for the same break, three accidents of the SB LOCA were simulated. The purpose of our study was to estimate the potential risk of the extreme conservative input parameters for the pressurized thermal shock (PTS) in the reactor's pressure vessel.


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