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    Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 001::page 11401-1
    Author:
    Prošek, Andrej
    DOI: 10.1115/1.4063009
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In Europe, the design extension conditions (DEC) were introduced after the Fukushima Dai-ichi accident as preferred method for giving due consideration to the complex sequences and severe accidents without including them in the design basis conditions. The objective of the study is to determine available elapsed time before core uncovery and needed DEC safety features for total loss of all feedwater (TLOFW) in a two-loop pressurized water reactor. RELAP5/MOD3.3 computer code has been used for calculations. The initiating event for TLOFW is multiple failures in which, in addition to the loss of main feedwater, the auxiliary feedwater is also lost. The scenarios without DEC safety features and the scenarios with DEC safety feature assumed have been simulated. The results showed that after TLOFW event initiation, it is very important to trip the reactor as soon as possible. In case of loss of offsite power, the reactor coolant pumps stop, and the reactor very quickly trips on low reactor coolant pump flow. When normal operation systems are assumed, the reactor trip occurs on low-low steam generator narrow level few tens of seconds after accident initiation, resulting in less time available before core uncovery occurence. The results for TLOFW scenarios with normal operation systems and DEC safety features assumed demonstrated that secondary side bleed and feed can prevent core uncovery in case when no operator actions are credited in the first 30 min of event. When primary side bleed and feed is used, less time is available for operator actions.
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      Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5

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    contributor authorProšek, Andrej
    date accessioned2024-04-24T22:42:42Z
    date available2024-04-24T22:42:42Z
    date copyright10/20/2023 12:00:00 AM
    date issued2023
    identifier issn2332-8983
    identifier otherners_010_01_011401.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295731
    description abstractIn Europe, the design extension conditions (DEC) were introduced after the Fukushima Dai-ichi accident as preferred method for giving due consideration to the complex sequences and severe accidents without including them in the design basis conditions. The objective of the study is to determine available elapsed time before core uncovery and needed DEC safety features for total loss of all feedwater (TLOFW) in a two-loop pressurized water reactor. RELAP5/MOD3.3 computer code has been used for calculations. The initiating event for TLOFW is multiple failures in which, in addition to the loss of main feedwater, the auxiliary feedwater is also lost. The scenarios without DEC safety features and the scenarios with DEC safety feature assumed have been simulated. The results showed that after TLOFW event initiation, it is very important to trip the reactor as soon as possible. In case of loss of offsite power, the reactor coolant pumps stop, and the reactor very quickly trips on low reactor coolant pump flow. When normal operation systems are assumed, the reactor trip occurs on low-low steam generator narrow level few tens of seconds after accident initiation, resulting in less time available before core uncovery occurence. The results for TLOFW scenarios with normal operation systems and DEC safety features assumed demonstrated that secondary side bleed and feed can prevent core uncovery in case when no operator actions are credited in the first 30 min of event. When primary side bleed and feed is used, less time is available for operator actions.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleTotal Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5
    typeJournal Paper
    journal volume10
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4063009
    journal fristpage11401-1
    journal lastpage11401-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 010 ):;issue: 001
    contenttypeFulltext
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