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    Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor

    Source: Journal of Nuclear Engineering and Radiation Science:;2025:;volume( 011 ):;issue: 003::page 31301-1
    Author:
    Nava Dominguez, A.
    ,
    Huang, Xianmin
    ,
    Gaudet, Michel
    ,
    Khumsa-Ang, Kittima
    ,
    Mendoza España, Alberto D'Ansi
    ,
    Chow, Jimmy
    ,
    Roubtsov, Danila
    ,
    Namburi, Hygreeva
    DOI: 10.1115/1.4068326
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The supercritical water-cooled reactor (SCWR) is one of the six concepts selected by the generation-IV international forum (GIF) for future research. This technology is a natural evolutionary step of the current water-cooled reactors. Canada is a participant of the GIF, and under this international endeavor developed the Canadian SCWR, which is a 1200 MWe concept. However, due to high capital cost associated with building large units, the nuclear industry rekindled an old concept: Small reactors (SRs), and now small modular reactors (SMRs). These reactors are poised to reduce the financial risks associated with large units, and also potentially offer more flexibility as modules can be prefabricated and transported to the construction site for assembly. As a result, numerous domestic and international programs were established to support the development and deployment of SMRs. The ECC-SMART project was proposed to develop a supercritical water-cooled SMR. Canada joined this collaboration, and under this project alongside the GIF SCWR and IAEA CRP platforms, a new Canadian supercritical water-cooled small modular reactor (SCW-SMR) was proposed and developed. This concept is based on the experience and lessons learned during the development of the Canadian SCWR. An overview of a multidisciplinary approach that led to the concept is presented in this paper, consisting of a market study, thermodynamics and energy conversion, reactor physics, thermal hydraulics, materials and chemistry, and safety assessments.
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      Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor

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    contributor authorNava Dominguez, A.
    contributor authorHuang, Xianmin
    contributor authorGaudet, Michel
    contributor authorKhumsa-Ang, Kittima
    contributor authorMendoza España, Alberto D'Ansi
    contributor authorChow, Jimmy
    contributor authorRoubtsov, Danila
    contributor authorNamburi, Hygreeva
    date accessioned2025-08-20T09:22:25Z
    date available2025-08-20T09:22:25Z
    date copyright5/8/2025 12:00:00 AM
    date issued2025
    identifier issn2332-8983
    identifier otherners_011_03_031301.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4308170
    description abstractThe supercritical water-cooled reactor (SCWR) is one of the six concepts selected by the generation-IV international forum (GIF) for future research. This technology is a natural evolutionary step of the current water-cooled reactors. Canada is a participant of the GIF, and under this international endeavor developed the Canadian SCWR, which is a 1200 MWe concept. However, due to high capital cost associated with building large units, the nuclear industry rekindled an old concept: Small reactors (SRs), and now small modular reactors (SMRs). These reactors are poised to reduce the financial risks associated with large units, and also potentially offer more flexibility as modules can be prefabricated and transported to the construction site for assembly. As a result, numerous domestic and international programs were established to support the development and deployment of SMRs. The ECC-SMART project was proposed to develop a supercritical water-cooled SMR. Canada joined this collaboration, and under this project alongside the GIF SCWR and IAEA CRP platforms, a new Canadian supercritical water-cooled small modular reactor (SCW-SMR) was proposed and developed. This concept is based on the experience and lessons learned during the development of the Canadian SCWR. An overview of a multidisciplinary approach that led to the concept is presented in this paper, consisting of a market study, thermodynamics and energy conversion, reactor physics, thermal hydraulics, materials and chemistry, and safety assessments.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleProgress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
    typeJournal Paper
    journal volume11
    journal issue3
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4068326
    journal fristpage31301-1
    journal lastpage31301-20
    page20
    treeJournal of Nuclear Engineering and Radiation Science:;2025:;volume( 011 ):;issue: 003
    contenttypeFulltext
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