Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code

A LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8...

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Veröffentlicht in:Nuclear engineering and design 2014-04, Vol.269, p.155-159
Hauptverfasser: Kim, Tae Woon, Song, Jinho, Huong, Vo Thi, Kim, Dong Ha, Rhee, Bo Wook, Revankar, Shripad
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container_issue
container_start_page 155
container_title Nuclear engineering and design
container_volume 269
creator Kim, Tae Woon
Song, Jinho
Huong, Vo Thi
Kim, Dong Ha
Rhee, Bo Wook
Revankar, Shripad
description A LBLOCA scenario for an advanced pressurized water reactor, call APR1400, developed in Korea is analyzed in order to obtain an overall insight into a severe accident progression from an initiating event to the reactor vessel failure in detail by using the MELCOR computer code Versions 1.8.5 and 1.8.6. The present results (the amount of molten corium and vessel failure timing) would be used as input for the establishment of severe accident management strategies or for the design of a core catcher for the APR1400. The MELCOR results showed that the lower head instrumentation tube penetration failure model and internal structure in the reactor vessel had influence on the amount of corium ejected and the timing of reactor vessel failure.
doi_str_mv 10.1016/j.nucengdes.2013.08.022
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subjects Accident analysis
Accidents
Failure
Nuclear reactor components
Nuclear reactors
Pressurized water reactors
Progressions
Time measurements
title Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code
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