ISO 4917-3:2024
Design of nuclear power plants against seismic events — Part 3: Civil structures
Design of nuclear power plants against seismic events — Part 3: Civil structures
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 23
- Дата публикации:
- 22 февраля 2024 г.
- Издание:
- ISO IS 4917 edition 1 version 1
- ICS:
- 27.120.20
This document applies to civil structures of nuclear power plants with water cooled reactors in order to achieve the safety objectives given in ISO 4917-1. For other nuclear facilities the applicability of the document needs to be checked in advance, before it might be applied correspondingly. This document specifies the requirements for civil structures for the verification of their load-bearing capacity in case of a seismic event. Additionally, requirements are specified pertaining to the verification of the serviceability of civil structures as far as necessary for maintaining their safety-related function in case of a seismic event (e.g. deformation and crack-width limitations). This document will be applied under the presumption that the geology and tectonics of the plant site have been investigated with special emphasis on the existence of active geological faults and lasting geological ground displacements, and that the site has been deemed suitable for a nuclear installation. To achieve these goals, this document deals with the requirements specific to the seismic design of civil structures above and beyond their conventional design. The basic requirements of these precautionary measures are dealt with in ISO 4917-1. This document does not apply to cranes, to detachment devices for lifting equipment nor to the supporting and mounting constructions of components. This document is independent of national standards. Recommendations, given in Annex A, are mainly based on the KTA Design-Philosophy and European standards. Alternatively other equivalent standards or regulations can be used in case the general requirements given in this document can be met. NOTE The term civil structures as used in this document comprise buildings and structural members made of reinforced concrete, pre-stressed concrete, steel, as well as steel composite structures and masonry. Among others, these include the containment, crane runways, platforms, fastening constructions and canals.
Abstract
Overview
ISO 4917-3:2024 - Design of nuclear power plants against seismic events - Part 3: Civil structures specifies requirements for the seismic design and verification of civil structures in nuclear power plants with water-cooled reactors. The standard focuses on ensuring load-bearing capacity and serviceability (e.g., deformation and crack-width limits) during seismic events. It assumes the site geology and tectonics have been investigated and found suitable and excludes equipment cranes, lifting detachment devices, and component mounting supports.
Key topics and technical requirements
- Scope and applicability
- Applies to buildings and structural members (reinforced/pre‑stressed concrete, steel, steel‑composite, masonry) including containment, platforms, crane runways and canals.
- Independent of national codes; Annex A provides recommendations based on KTA and European standards.
- Seismic event definition and design philosophy
- Aligned with the safety objectives in ISO 4917-1 and nuclear seismic protection principles (IAEA guidance referenced).
- Structure analysis and modeling
- Requirements for geotechnical parameters, dynamic subsoil properties, material characteristics, effective stiffness, contributing masses and damping.
- Treatment of hydrodynamic effects for fluid‑containing structures.
- Analysis methods
- Permitted analysis approaches: response spectrum, time history, frequency‑domain and simplified methods, with guidelines for building response spectra and acceleration time‑history derivation.
- Soil–structure interaction
- Kinematic and inertial interaction considerations, impedance functions and dynamic foundation behavior.
- Seismic verification concept
- Ultimate Limit State (ULS) and Serviceability Limit State (SLS) verifications, load combinations, ductility concepts, equilibrium checks, deformation and crack controls.
- Requirements for foundations and beyond‑design considerations.
- Structure‑type specific verifications
- Verification approaches for reinforced/pre‑stressed concrete, steel structures, masonry, steel‑composite systems, fastening constructions, buried pipelines and support structures.
Practical applications and users
ISO 4917-3:2024 is intended for:
- Structural and seismic engineers designing nuclear civil structures
- Nuclear plant designers and engineering contractors
- Site evaluators and geotechnical engineers
- Regulatory authorities, licensing bodies and safety assessors
- Consultants preparing seismic verification reports and design documentation
Use cases include seismic design checks for containment buildings, foundation design accounting for soil–structure interaction, verification of deformation/crack limits for safety‑related functions, and development of time‑history or response‑spectrum analyses for licensing submittals.
Related standards
- ISO 4917-1:2024 - Principles (safety objectives and overarching requirements)
- ISO 4917-4:2024 - Components
- IAEA SSG-67 (Seismic Design for Nuclear Installations)
- Annex A (informative) - recommendations based on KTA and European standards
Keywords: ISO 4917-3:2024, seismic design, nuclear power plants, civil structures, seismic verification, soil‑structure interaction, response spectrum, time history.
Технические детали
- Технический комитет
- ISO/TC 85/SC 6 - Reactor technology
- SKU
- ISO 4917-3:2024
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