ISO 4917-4:2024 PDF
Design of nuclear power plants against seismic events — Part 4: Components
Design of nuclear power plants against seismic events — Part 4: Components
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 36
- Дата публикации:
- 7 марта 2024 г.
- Издание:
- ISO IS 4917 edition 1 version 1
- ICS:
- 27.120.20
This document applies to nuclear power plants with water cooled reactors. For other nuclear facilities check the applicability of the document in advance, before it might be applied correspondingly. This document specifies the requirements for the earthquake safety of components. The operation-specific safety-related requirements for each component, e.g. load-bearing capacity (stability), integrity and functionality (see 4.1) are not the subject of this document. With regard to analysing the mechanical behaviour of the individual components and verifying the fulfillment of their safety related functions, additionally, the respective component-specific standards need to be consulted. In this document, the term "mechanical components" refers to components such as vessels, heat exchangers, pumps, valves, lifting gear, distribution systems and pipe lines including their support structures in as far as these components are not considered to be civil structures in accordance with ISO 4917-3. Liners, crane runways, platforms and scaffoldings are not considered as being part of these mechanical components. In this document, the term electrical components refers to the combination of electrical devices including all electrical connections and their support structures (e.g. cabinets, frames, consoles, brackets, suspensions or supports). Supplementary to this document the seismic qualification of electrical components is reported in IEC/IEEE 60980-344. NOTE This document is independent of national standards. Recommendations, given in Annex A, are mainly based on the Eurocodes-Design-Philosophy and European Standards. Alternatively other equivalent standards or regulations can be used in case the general requirements given in this document together with Annex A can be met.
Abstract
Overview
ISO 4917-4:2024 - Design of nuclear power plants against seismic events - Part 4: Components specifies requirements for demonstrating earthquake safety of components in nuclear power plants with water-cooled reactors. It covers the seismic verification scope, modelling and analysis approaches, and testing/qualification principles for mechanical and electrical components (including their support structures). The document complements structural requirements in ISO 4917-3 and the principles in ISO 4917-1.
Key topics and technical requirements
- Scope and component types
- Applies to mechanical components such as vessels, heat exchangers, pumps, valves, lifting gear, distribution systems, pipelines and supports (excluding civil structures per ISO 4917-3). Liners, crane runways, platforms and scaffoldings are excluded.
- Defines electrical components as devices plus their electrical connections and support structures (cabinets, frames, brackets).
- Verification methods
- Verification by analysis: response spectrum, time-history, quasi-static and non-linear time-history methods; modelling of fluids, system characteristics, decoupling and relative displacements.
- Verification by testing: requirements for test objects and excitations (base excitation, single/multiple-frequency, centre-of-gravity and multi-axis considerations), and test-analysis correlation.
- Verification by analogy and by plausibility considerations are also addressed.
- Seismic inputs and modelling
- Use of design spectra, demand response spectra, and considerations for modal damping, center of gravity, and the behaviour coefficient q (reducing linear-analysis forces to account for dissipation).
- Limits of the document
- Does not set operation-specific safety performance criteria (load-bearing capacity, integrity, functionality); component-specific standards must be consulted for those checks.
- Guidance and references
- Annex A provides recommendations largely based on Eurocode design philosophy; equivalent standards are acceptable if they meet the general requirements.
Practical applications - who uses this standard
- Seismic and structural engineers designing or evaluating components for nuclear power plants (water-cooled reactors).
- Component manufacturers and suppliers performing seismic qualification and documentation.
- Test laboratories conducting seismic tests (shake-table, base excitation) and dynamic characterization.
- Nuclear safety assessors, plant operators and regulators verifying compliance with seismic design requirements.
- Consultants integrating component-level verification into plant-level seismic safety cases.
Related standards
- ISO 4917-1:2024 - Principles (series foundation)
- ISO 4917-3 - Structural components (civil structures)
- IEC/IEEE 60980-344 - Seismic qualification of electrical components (supplementary)
Keywords: ISO 4917-4:2024, seismic design, nuclear power plant components, seismic qualification, response spectrum, time history analysis, seismic testing, water-cooled reactors, component verification.
Технические детали
- Технический комитет
- ISO/TC 85/SC 6 - Reactor technology
- SKU
- ISO 4917-4:2024
Похожие стандарты
Стандарты, упомянутые в описании
ISO 4917-1:2024
ДействующийDesign of nuclear power plants against seismic events — Part 1: Principles
Overview ISO 4917-1:2024 - Design of nuclear power plants against seismic events - Part 1: Principles sets out the fundamental principles for seismic design of nuclear power plants with water-cooled…
BS ISO 4917-3:2024
ДействующийDesign of nuclear power plants against seismic events - Civil structures
BS ISO 4917-1:2024
ДействующийDesign of nuclear power plants against seismic events - Principles
1 Scope This document applies to nuclear power plants with water cooled reactors and, in particular, to the design of components and civil structures against seismic events in order to meet the safet…