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    Various Design Aspects of the Canadian Supercritical Water Cooled Reactor Core

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001::page 11007
    Author:
    Yetisir, Metin
    ,
    Xu, Rui
    ,
    Gaudet, Michel
    ,
    Movassat, Mohammad
    ,
    Hamilton, Holly
    ,
    Nimrouzi, Mohammedhossein
    ,
    Goldak, John A.
    DOI: 10.1115/1.4031247
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Canadian Supercritical WaterCooled Reactor (SCWR) is a 1200آ MW(e) channeltype nuclear reactor. The reactor core includes 336 vertical pressurized fuel channels immersed in a lowpressure heavy water moderator and calandria vessel containment. The supercritical water (SCW) coolant flows into the fuel channels through a common inlet plenum and exits through a common outlet header. One of the main features of the Canadian SCWR concept is the highpressure (25آ MPa) and hightemperature (350آ°C at the inlet, 625آ°C at the outlet) operating conditions that result in an estimated thermal efficiency of 48%. This is significantly higher than the thermal efficiency of the present light water reactors, which is about 33%. This paper presents a description of the Canadian SCWR core design concept; various numerical analyses performed to understand the temperature, flow, and stress distributions of various core components; and how the analyses results provided input for improved concept development.
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      Various Design Aspects of the Canadian Supercritical Water Cooled Reactor Core

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    http://yetl.yabesh.ir/yetl1/handle/yetl/162191
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    • Journal of Nuclear Engineering and Radiation Science

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    contributor authorYetisir, Metin
    contributor authorXu, Rui
    contributor authorGaudet, Michel
    contributor authorMovassat, Mohammad
    contributor authorHamilton, Holly
    contributor authorNimrouzi, Mohammedhossein
    contributor authorGoldak, John A.
    date accessioned2017-05-09T01:32:11Z
    date available2017-05-09T01:32:11Z
    date issued2016
    identifier issn2332-8983
    identifier otherNERS_2_1_011007.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/162191
    description abstractThe Canadian Supercritical WaterCooled Reactor (SCWR) is a 1200آ MW(e) channeltype nuclear reactor. The reactor core includes 336 vertical pressurized fuel channels immersed in a lowpressure heavy water moderator and calandria vessel containment. The supercritical water (SCW) coolant flows into the fuel channels through a common inlet plenum and exits through a common outlet header. One of the main features of the Canadian SCWR concept is the highpressure (25آ MPa) and hightemperature (350آ°C at the inlet, 625آ°C at the outlet) operating conditions that result in an estimated thermal efficiency of 48%. This is significantly higher than the thermal efficiency of the present light water reactors, which is about 33%. This paper presents a description of the Canadian SCWR core design concept; various numerical analyses performed to understand the temperature, flow, and stress distributions of various core components; and how the analyses results provided input for improved concept development.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleVarious Design Aspects of the Canadian Supercritical Water Cooled Reactor Core
    typeJournal Paper
    journal volume2
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4031247
    journal fristpage11007
    journal lastpage11007
    treeJournal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 001
    contenttypeFulltext
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