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>UNE EN IEC 62705:2026 - Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle (Endorsed by Asociación Española de Normalización in July of 2026.)
Vydáno: 2026-07-01
UNE EN IEC 62705:2026 - Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle (Endorsed by Asociación Española de Normalización in July of 2026.)

UNE EN IEC 62705:2026

Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle (Endorsed by Asociación Española de Normalización in July of 2026.)

Instalaciones nucleares. Instrumentación y control importantes para la seguridad. Sistemas de monitorización de la radiación (RMS): Características y ciclo de vida (Ratificada por la Asociación Española de Normalización en julio de 2026.)

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Označení normy:UNE EN IEC 62705:2026
Vydáno:2026-07-01
Status:Norma
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UNE EN IEC 62705:2026

This document gives requirements for the lifecycle management of radiation monitoring systems (RMS) and gives guidance on the application of existing IEC standards covering the design and qualification of systems and equipment. The purpose of this document is to lay down requirements for the lifecycle management of RMSs and give application guidance. This document is intended to be consistent with the latest versions of International Standards dealing with radiation monitors, sampling of radioactive materials, instruments calibration, hardware and software design, classification, and qualification. Unless otherwise specified in this document, top level IEC SC 45A standard, IEC 61513, and the second level IEC SC 45A standards apply to RMSs. This document is applicable to RMSs installed in nuclear facilities intended for use during normal operation, anticipated operational occurrences (AOO), design basis accidents (DBA) and design extension conditions (DEC), including severe accidents (SA). The technical guidance contained in this document applies to nuclear facilities, although the specific functions of individual facilities are considered during the design and operational lifecycle of RMSs. Laboratory analysis and associated sample extraction, which are essential to a complete programme of effluent monitoring, and investigation for fuel removal are not in the scope of this document.

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