Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2

► RELAP5 Code is used to analyze the REA in a VVER-1000. ► A 58mm break is considered in the upper head of the reactor pressure vessel. ► Reactor shut-down occurred in 1.7–5.4s. ► The studied accident is not categorized among level 1 accidents. ► Results are consistent with VVER-1000 FSAR data. In t...

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Bibliographic Details
Published in:Annals of nuclear energy 2012-07, Vol.45, p.106-114
Main Authors: Tabadar, Z., Hadad, K., Nematollahi, M.R., Jabbari, M., Khaleghi, M., Hashemi-Tilehnoee, M.
Format: Article
Language:English
Subjects:
FSAR
RELAP5
Rod ejection accident (REA)
VVER-1000
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Summary:► RELAP5 Code is used to analyze the REA in a VVER-1000. ► A 58mm break is considered in the upper head of the reactor pressure vessel. ► Reactor shut-down occurred in 1.7–5.4s. ► The studied accident is not categorized among level 1 accidents. ► Results are consistent with VVER-1000 FSAR data. In this study, the RELAP5 Mod3.2 code has been used to analyze the REA in a VVER-1000 reactor. For a conservative simulation, a 58mm break is considered in the upper head of the reactor pressure vessel due to the impact of an ejected rod. Four cases, 104% of nominal power and 0.45$ of inserted reactivity, 71% of nominal power and 0.47$ of inserted reactivity, 54% of nominal power and 0.6$ of inserted reactivity, and 1% of nominal power and 0.9$ of inserted reactivity are the initial conditions. The relative power, pressure in the pressurizer, mass flow rate via break point, BRU-A performance, and fuel surface temperature are the investigated parameters. The results of the RELAP5 code are consistent with VVER-1000 FSAR data.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2012.02.018