{"id":24632,"date":"2026-02-01T19:19:06","date_gmt":"2026-02-01T19:19:06","guid":{"rendered":"http:\/\/141.23.68.248\/wp\/?page_id=24632"},"modified":"2026-02-09T19:22:30","modified_gmt":"2026-02-09T19:22:30","slug":"ontology","status":"publish","type":"page","link":"http:\/\/141.23.68.248\/wp\/?page_id=24632","title":{"rendered":"Ontology"},"content":{"rendered":"\n

Introduction:<\/strong><\/h2>\n\n\n\n

The nuclear containment building is a critical safety structure designed to confine radioactive substances and protect the environment from internal pressures or external attacks.<\/p>\n\n\n\n

\"\"<\/a><\/figure>\n\n\n\n

Purpose:
<\/strong>To provide a modular model that maps the interactions between physical components, safety functions, and materials, aiding in the design and comparison of various nuclear plant configurations.<\/p>\n\n\n\n

Scope:
<\/strong>Covers the physical superstructure (walls, dome), substructure (foundation), auxiliary safety systems (spray, ventilation), and functional requirements like radiation shielding and leak-tightness.<\/p>\n\n\n\n

Intended Users & Intended Use:<\/strong><\/p>\n\n\n\n

Users: Civil engineers, nuclear safety researchers, and plant designers. Use: To enable “what-if” scenarios for different reactor types (PWR vs. BWR or Fission vs. Fusion) and to facilitate the selection of materials based on regulatory and environmental constraints.<\/p>\n\n\n\n

Class Hierarchy:<\/strong>
<\/h2>\n\n\n\n

The ontology is organized into several main branches:<\/p>\n\n\n\n

1.ContainmentComponent: Includes Superstructure, Substructure, and Auxiliary systems.<\/p>\n\n\n\n

2.ContainmentFunction: Covers leak-tightness, radiation shielding, and pressure retention.<\/p>\n\n\n\n

3.ContainmentMaterial: Includes specific materials like prestressed concrete, liner metal alloys, and various soil types. <\/p>\n\n\n\n

4.ContainmentUse: Defines the plant’s purpose (e.g., Power Reactor, Research, Waste Treatment).
<\/p>\n\n\n\n

\"\"<\/a><\/figure>\n\n\n\n

Ontograf (Logic & Axioms):<\/strong><\/h2>\n\n\n\n

A) Wall Logic: A WallSuperstructure must have exactly one wall type (Single or Double). If it is a DoubleWall, it must contain an InnerWall, OuterWall, and Annulus.<\/p>\n\n\n\n

B) Object Properties: The model defines transitive properties like hasComponent and isComponentOf, and maps functions to specific components (e.g., DomeSuperstructure has the function to EnsurePressureRetention).<\/p>\n\n\n\n

\"\"<\/a><\/figure>\n\n\n\n

Engineering Examples:<\/strong><\/h2>\n\n\n\n
    \n
  1. Fusion vs. Fission: Comparing a standard fission reactor to a Tokamak (fusion) vessel to identify different shielding requirements.<\/li>\n\n\n\n
  2. Environmental Adaptation: Using the ontology to swap traditional concrete for low-carbon alternatives to meet new environmental regulations.<\/li>\n\n\n\n
  3. Seismic Integration: Modeling the addition of a Tuned Mass Damper (TMD) to evaluate how it interacts with the existing internal volume and vibration modes.<\/li>\n<\/ol>\n\n\n\n

    Conclusion:<\/strong><\/h2>\n\n\n\n

    The ontology provides a robust framework for documenting safety requirements and structural dependencies. It allows designers to automatically integrate material and geometric choices into parametric models for further mechanical and environmental simulation.<\/p>\n\n\n\n

    References:<\/strong><\/h2>\n\n\n\n

    1.Evolution of nuclear reactor containments in India: Addressing the present day challenges<\/em>, A. Kakodkar, 2014<\/p>\n\n\n\n

    2.Thermal-Hydraulic comparative analysis of G-III+BWR and PWR passive safety features under Loss of coolant accident<\/em>, X. Zhang et al., 2023<\/p>\n\n\n\n

    3.Chapter 4 \u00abDesign Requrement\u00bb, Safety Series No.50-SG-D12 Design of Reactor Containment Systems in Nuclear Plants A Safety Guide, 1985<\/em><\/p>\n\n\n\n

    4.Section 4 \u00abEngineering Design, Fabrication, Erection and Testing\u00bb, Nuclear Reactor Containment Buildings And Pressure Vessels<\/em>, The Royal College Of Science & Technology, Glasgow, 1960<\/p>\n\n\n\n

    5.Section 2 \u00abDesign Studies And Methods Of Stress Analysis\u00bb, Nuclear Reactor Containment Buildings And Pressure Vessels<\/em>, The Royal College Of Science & Technology, Glasgow, 1960<\/p>\n\n\n\n

    6.Strain Monitoring and Numerical Simulation Analysis of Nuclear Containment Structure During Containment Tests<\/em>, X\/Yin et al., 2025<\/p>\n\n\n\n

    7.Pre-conceptual design of prestressed concrete containment for a GFR nuclear reactor<\/em>, Petr B\u00edl\u00fd et al., 2025<\/p>\n\n\n\n

    8.Stochastic finite elements analysis of large concrete structures\u2019 serviceability under thermo-hydro-mechanical loads \u2013 Case of nuclear containment buildings<\/em>, D.E.-M. Bouhjiti et al., 2020<\/p>\n\n\n\n

    9.Enciente de confinement pour un reacteur a eau lourde-gaz de 250 MWe<\/em>, Verstraete et al., 1967<\/p>\n\n\n\n

    \u00a010.A novel computational framework for efficient nuclear containment design: Structural integrity, radiation shielding, and reliability assessment<\/em>, S.Saxena et al., 2025<\/p>\n\n\n\n

    Parametric Model<\/a> > <\/p>\n","protected":false},"excerpt":{"rendered":"

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