© 2017 KOASIS Inc. 



    We provide analytical engineering services mainly based on finite element analysis with ANSYS, a general purpose finite element analysis software. The scope of our services are as follows;

    • Mechanical component engineering in nuclear industry (KEPIC/ASME B&PV Code Section III)

      • Design reports

      • RPE certification

      • Environment fatigue evaluation

      • Calculation reports

      • Design drawing

    • Seismic analysis for Equipment Qualification of nuclear safety-related facilities

    • Analysis works covering thermal/structural/dynamic/fatigue/fracture/buckling/piping​

    • Engineering support for future reactor development

      • Elevated temperature reactor

      • International thermonuclear experimental reactor

    • Mechanical compenent engineering in fossil power and petrochemical industries
      (ASME Code Section VIII Div.2)

    • Software development for design and analysis

      • Programming for fatigue evaluation

    • Third-party review

      • Review of design & assessment document

    • Training

      • KEPIC/ASME Code, design by analysis

      • Design report

      • FE analysis

      • Supporting acquisition of KEPIC/ASME certification, in design activity

    • Application of advanced engineering technologies



    Some of our project experiences are shown below;

    • Design reports for APR1400 primary components including Steam Generator, Pressurizer, and Safety Injection Tank

    • Design analysis of Korea Advanced Liquid Metal Reactor, KALIMER-600

    • Seismic analysis of Nuclear Fuel Cleaning Fixture

    • Design analysis of ITER Tritium Storage and Delivery System Components

    • High energy line break analysis of Class 1&2 piping lines

    • Lifetime extension evaluation of CANDU Fuelling Machine

    • Leak-before-break evaluation of Class 1 piping

    • Structural analysis of Pool Platform for Jordan research reactor

    • Environmental fatigue evaluation of Class 1 valves

    • Design and dynamic qualification reports for Emergency Diesel Generator tanks

    • Optimization study on fatigue evaluation of Pressurizer Surge Line

    • Analytical engineering for Steam Generator Replacement

    • High temperature design analyses of pressure components for Sodium-cooled Fast Reactor test loop, STELLA-2

    • Consultation on design and analysis in accordance with ASME B&PV Code, Section III, Subsection NB and NF


    Samples of our project experiences are shown below.