Modeling of Boushehr NPP (as built) and Analysis of Large Break Loss of Coolant Accident (LB-LOCA) Using RELAP5/MOD3.2 System Code, M.Sc. Thesis Sharif University of Technology ; Vossoughi, Naser (Supervisor) ; Jafari, Jalil (Supervisor)
Abstract
In this work the large break loss of coolant accident at Boushehr Nuclear Power Plant (NPP) has been studied. At first, primary and secondary side’s components which play important role in the accident have been modeled using RELAP5/MOD3.2 GAMMA system code. The components are: reactor pressure vessel, main pipe lines, main coolant pumps, pressurizer, steam generators, steam lines, emergency core cooling accumulators, boron solution supply tanks and pumps (LP& HP) and KWU accumulators. After preparing the input file and running the code, thermal hydraulic properties such as radial distribution of temperature in fuel rods, temperature distribution in steam generator primary and secondary...
Cataloging briefModeling of Boushehr NPP (as built) and Analysis of Large Break Loss of Coolant Accident (LB-LOCA) Using RELAP5/MOD3.2 System Code, M.Sc. Thesis Sharif University of Technology ; Vossoughi, Naser (Supervisor) ; Jafari, Jalil (Supervisor)
Abstract
In this work the large break loss of coolant accident at Boushehr Nuclear Power Plant (NPP) has been studied. At first, primary and secondary side’s components which play important role in the accident have been modeled using RELAP5/MOD3.2 GAMMA system code. The components are: reactor pressure vessel, main pipe lines, main coolant pumps, pressurizer, steam generators, steam lines, emergency core cooling accumulators, boron solution supply tanks and pumps (LP& HP) and KWU accumulators. After preparing the input file and running the code, thermal hydraulic properties such as radial distribution of temperature in fuel rods, temperature distribution in steam generator primary and secondary...
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