IDEAS home Printed from https://ideas.repec.org/a/gam/jmathe/v10y2022i10p1779-d822005.html
   My bibliography  Save this article

Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels

Author

Listed:
  • Alvaro Rodríguez-Prieto

    (Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain
    Department of Industrial Inspection and Technical Assistance, SGS Tecnos, 28042 Madrid, Spain)

  • Manuel Callejas

    (Department of Industrial Inspection and Technical Assistance, SGS Tecnos, 28042 Madrid, Spain)

  • Ernesto Primera

    (Department of Applied Statistics, University of Delaware, 531 South College Avenue, Newark, DE 19716, USA
    Machinery and Reliability Institute (MRI), 2149 Adair Ct, Mobile, AL 36695, USA)

  • Guglielmo Lomonaco

    (GeNERG, Dipartimento di Ingegneria Meccanica, TEC Division, Energetica, Gestionale e dei Trasporti (DIME), Università di Genova (UNIGE), Via all’Opera Pia, 15A, 16145 Genoa, Italy
    Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Genova, Via Dodecaneso 33, 16146 Genoa, Italy)

  • Ana María Camacho

    (Department of Manufacturing Engineering, Universidad Nacional de Educación a Distancia (UNED), 28040 Madrid, Spain)

Abstract

The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels. This new methodology integrates a robust and regulated irradiation embrittlement prediction model such as the ASTM E-900 with the ASME Fitness-for-Service code used widely in other demanding industries, such as oil and gas, to evaluate, among others, the risk of experiencing degradation mechanisms such as the brittle fracture (generated, in this case, due to the irradiation embrittlement). This multicriteria analytical model, which is based on a new formulation of the brittle fracture criterion, allows an adequate prediction of the irradiation effect on the fracture toughness of reactor pressure-vessel steels, letting us jointly evaluate the mechanical integrity and the fitness-for-service of the vessel by using standardized limit conditions. This allows making decisions during the design, manufacturing and in-service of reactor pressure vessels. The results obtained by the application of the methodology are coherent with several historical experimental works.

Suggested Citation

  • Alvaro Rodríguez-Prieto & Manuel Callejas & Ernesto Primera & Guglielmo Lomonaco & Ana María Camacho, 2022. "Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels," Mathematics, MDPI, vol. 10(10), pages 1-17, May.
    • Handle: RePEc:gam:jmathe:v:10:y:2022:i:10:p:1779-:d:822005
    as

    Download full text from publisher

    File URL: https://www.mdpi.com/2227-7390/10/10/1779/pdf
    Download Restriction: no
    File URL: https://www.mdpi.com/2227-7390/10/10/1779/
    Download Restriction: no
    ---><---

    References listed on IDEAS

    as
    1. Alvaro Rodríguez-Prieto & Ana María Camacho & Carlos Mendoza & John Kickhofel & Guglielmo Lomonaco, 2021. "Evolution of Standardized Specifications on Materials, Manufacturing and In-Service Inspection of Nuclear Reactor Vessels," Sustainability, MDPI, vol. 13(19), pages 1-25, September.
    2. Alvaro Rodríguez-Prieto & Mariaenrica Frigione & John Kickhofel & Ana M. Camacho, 2021. "Analysis of the Technological Evolution of Materials Requirements Included in Reactor Pressure Vessel Manufacturing Codes," Sustainability, MDPI, vol. 13(10), pages 1-20, May.
    Full references (including those not matched with items on IDEAS)

    Most related items

    These are the items that most often cite the same works as this one and are cited by the same works as this one.
    1. Alvaro Rodríguez-Prieto & Ana María Camacho & Carlos Mendoza & John Kickhofel & Guglielmo Lomonaco, 2021. "Evolution of Standardized Specifications on Materials, Manufacturing and In-Service Inspection of Nuclear Reactor Vessels," Sustainability, MDPI, vol. 13(19), pages 1-25, September.
    2. Hongda Liu & Haifeng Zhao, 2022. "Upgrading models, evolutionary mechanisms and vertical cases of service-oriented manufacturing in SVC leading enterprises: Product-development and service-innovation for industry 4.0," Palgrave Communications, Palgrave Macmillan, vol. 9(1), pages 1-24, December.

    Corrections

    All material on this site has been provided by the respective publishers and authors. You can help correct errors and omissions. When requesting a correction, please mention this item's handle: RePEc:gam:jmathe:v:10:y:2022:i:10:p:1779-:d:822005. See general information about how to correct material in RePEc.

    If you have authored this item and are not yet registered with RePEc, we encourage you to do it here. This allows to link your profile to this item. It also allows you to accept potential citations to this item that we are uncertain about.

    If CitEc recognized a bibliographic reference but did not link an item in RePEc to it, you can help with this form .

    If you know of missing items citing this one, you can help us creating those links by adding the relevant references in the same way as above, for each refering item. If you are a registered author of this item, you may also want to check the "citations" tab in your RePEc Author Service profile, as there may be some citations waiting for confirmation.

    For technical questions regarding this item, or to correct its authors, title, abstract, bibliographic or download information, contact: MDPI Indexing Manager (email available below). General contact details of provider: https://www.mdpi.com .

    Please note that corrections may take a couple of weeks to filter through the various RePEc services.

    IDEAS is a RePEc service. RePEc uses bibliographic data supplied by the respective publishers.