Gaston Bourguigne

Lead Stress Engineer at Seaborg Technologies
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Contact Information
Location
Copenhagen Metropolitan Area, DK
Languages
  • Danish Elementary proficiency

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Credentials

  • Seismic Walkdown - SQUG
    EPRI
    May, 2019
    - Sep, 2024

Experience

    • Denmark
    • Nuclear Electric Power Generation
    • 1 - 100 Employee
    • Lead Stress Engineer
      • Nov 2022 - Present

    • Stress Expert
      • Jun 2022 - Nov 2022

    • Senior Stress Analyst
      • Nov 2021 - Oct 2022

    • Argentina
    • Nuclear Electric Power Generation
    • 700 & Above Employee
    • Principal Mechanical Engineer
      • Jun 2020 - Nov 2021

    • Section Head
      • Jun 2013 - Jun 2020

      -ASME III Stress & Fatigue Analysis of ageing piping and pressure vessels in Nuclear Power Plants aiming for life extension in Argentina,-Detailed Fatigue ASME III Evaluation of piping and pressure vessels using online temperature monitoring data (plug and stratified flows) for Atucha I and II,-AREVA FAMOS (Fatigue monitoring System) data processing and evaluation for Atucha I and II,-Environmental Fatigue assessment for Nuclear Power Plants aiming for life extension in Argentina,-Vibration analysis and mitigation in high-energy piping for CANDU NPP,-Seismic capacity evaluation (HCLPF) and retrofitting related to piping, structures and pressure vessels of Nuclear Power Plants in Argentina,-Pressurized Thermal Shock mechanical calculations for life extension of Atucha I NPP.-Paper Author and Presenter at ASME PVP and SMiRT conferences. Show less

    • Stress Analyst
      • Dec 2010 - Jun 2013

      -Realización de Stress Analysis de cañerías envejecidas para la Central Nuclear Embalse utilizando el programa de elementos finitos Abaqus CAE y siguiendo los requerimientos del código ASME Sección III.-Programación para calculo de evaluación de fatiga y ecuaciones del código ASME Sección III.-Realización de evaluación de aptitud para el servicio de Tubos de Calandria desgastados debido a contacto con lanza de inyección de veneno en la Central Nuclear Embalse utilizando el programa de elementos finitos Abaqus CAE y siguiendo los requerimientos del código ASME Sección III.-Realización de cálculos de soporte para cañerías de vapor principal en la Central Nuclear Embalse para reducir los valores de vibración.-Realización de reportes de tension del sistema primario de transporte de calor de la Central Nuclear Atucha 1 utilizando el programa de elementos finitos Abaqus CAE y siguiendo los requerimientos del código ASME Sección III.-Realización de análisis Elasto-Plasticos y de Carga Limite para demostrar la aptitud para el servicio de Feeders desgastados en la Central Nuclear Embalse.-Realización de cálculos térmicos en estructuras. Show less

    • Renewable Energy Semiconductor Manufacturing
    • 100 - 200 Employee
    • Engineer at technical office
      • Nov 2008 - Jan 2010

Education

  • Arts et Métiers ParisTech - École Nationale Supérieure d'Arts et Métiers
    Master's Degree, Materials and StrucEngineering
    2014 - 2015
  • Instituto Balseiro
    Specialist, Nuclear Energy
    2009 - 2010
  • Universidad Nacional de Mar del Plata
    Engineer, Electromechanical Engineering
    2003 - 2009
  • Università degli Studi di Perugia
    Ingegnere, Ingegneria Energetica
    2003 - 2007

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