27.120.20 – Nuclear power plants. Safety – PDF Standards Store ?u= Wed, 06 Nov 2024 00:06:28 +0000 en-US hourly 1 https://wordpress.org/?v=6.7.1 ?u=/wp-content/uploads/2024/11/cropped-icon-150x150.png 27.120.20 – Nuclear power plants. Safety – PDF Standards Store ?u= 32 32 ISO 8107:1993 ?u=/product/publishers/iso/iso-81071993/ Wed, 06 Nov 2024 00:06:28 +0000 Centrales nucléaires — Maintenabilité — Terminologie
Published By Publication Date Number of Pages
ISO 1993-06 17
]]> Identifies the typical parameters and terms necessary for collecting and exchanging maintainability data. The definitions are valid for corrective maintenance. For preventive maintenance, a similar classification can be drawn up. The general guidelines on the exchange of reliability data for nuclear power plants are given in ISO 6527.

]]> ISO 7385:1983 ?u=/product/publishers/iso/iso-73851983/ Tue, 05 Nov 2024 23:55:48 +0000 Centrales nucléaires — Principes directeurs pour assurer la qualité des données de fiabilité recueillies
Published By Publication Date Number of Pages
ISO 1983-08 8
]]> The output of a data collection system is strongly dependent on the quality of the information collected. Before starting such a system, it is necessary to clearly define the following items: the overall goal, the suppliers of field data, the users of processed data, the terms and expressions used, the means used to collect data and to treat them, the questions to be answered by field data, field data needed. The standard gives a comprehensive guidance to ensure quality of availability and reliability data collected in nuclear power plants.

]]> ISO 6527:1982 ?u=/product/publishers/iso/iso-65271982/ Tue, 05 Nov 2024 23:43:53 +0000 Nuclear power plants — Reliability data exchange — General guidelines
Published By Publication Date Number of Pages
ISO 1982-10 12
]]> Identifies the typical parameters of a component that permit it to be characterized unequivocally and to allow the corresponding reliability data to be associated with those of other components having equivalent typical parameters. Parameters refer to technical characteristics including the physical principle of operation and quality level and to actual operating conditions and maintenance and test intervals. Data may be represented both in a historical and in a statistical form.

]]> ISO 6258:1985 ?u=/product/publishers/iso/iso-62581985/ Tue, 05 Nov 2024 23:39:45 +0000 Nuclear power plants — Design against seismic hazards
Published By Publication Date Number of Pages
ISO 1985-01 45
]]> Specifies the requirements for designing and the data required and the way in which they should be used in order to determine the earth motions to be taken as the design basis earthquake (DBE), moreover the way in which the proof of seismic design adequacy should be established and documented. Determination of DBE is covered by both probabilistic and deterministic methods. Is entirely applicable when the DBE is greater than or equal to intensity VII on the MSK scale. When the DBE is less, the structural analysis could also be performed by using simpler rules.

]]> ISO 23467:2020 ?u=/product/publishers/iso/iso-234672020/ Tue, 05 Nov 2024 22:42:29 +0000 Ice plug isolation of piping in nuclear power plant
Published By Publication Date Number of Pages
ISO 2020-11 22
]]> This document specifies requirements for the ice plug technique with liquid nitrogen or dry ice as refrigerant (cryogenic medium) on metal pipes of nuclear power plants. The freezing liquid can be water or water mixture (e.g. boric acid mixture).

This document specifies technical requirements of ice plug generation, formation judgment and removal, measures before, during and after ice plugging and requirements for personnel and non-destructive testing.

The application of the ice plug isolation technique is principally not allowed on cladded pipes or pipes with internal coatings. The application for pressure test is not in the scope of this document and will be qualified separately.

]]> ISO 23466:2020 ?u=/product/publishers/iso/iso-234662020/ Tue, 05 Nov 2024 22:42:28 +0000 Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
Published By Publication Date Number of Pages
ISO 2020-10 30
]]> This document specifies the basic requirements of thermal insulation design of reactor coolant system (RCS) equipment and piping.

Among thermal insulation of various RCS equipment and piping, the following two kinds of thermal insulations are described in detailed based on common design logic and requirements:

— thermal insulation of reactor pressure vessel (RPV);

— thermal insulation of RCS piping and other equipment.

This document is valid for two types of thermal insulation:

— metallic thermal insulation;

— non-metallic thermal insulation.

This document mainly applies to nuclear power plants with pressurized water reactor (PWR). For other reactor types, this document can be taken as reference.

]]> ISO 23133:2021 ?u=/product/publishers/iso/iso-231332021/ Tue, 05 Nov 2024 22:40:41 +0000 Nuclear criticality safety — Nuclear criticality safety training for operations
Published By Publication Date Number of Pages
ISO 2021-01 16
]]> This document specifies minimum nuclear criticality safety training requirements for operations staff, operations supervisors, and management.

This document is applicable to areas, processes or facilities containing quantities of fissile material for which nuclear criticality safety assessment is required as defined in ISO 1709.

This document is not applicable to the transport of fissile materials outside the boundaries of nuclear establishments.

]]> ISO 21614:2008 ?u=/product/publishers/iso/iso-216142008/ Tue, 05 Nov 2024 22:29:44 +0000 Determination of carbon content of UO2, (U, Gd)O2 and (U, Pu)O2 powders and sintered pellets — Combustion in a high-frequency induction furnace — Infrared absorption spectrometry
Published By Publication Date Number of Pages
ISO 2008-12 10
]]> ISO 21614:2008 describes a method for determining the carbon content in UO2, (U,Gd)O2 and (U,Pu)O2 powder and sintered pellets by combustion in an induction furnace and infrared absorption spectroscopy measurement.

ISO 21614:2008 is applicable for determining 10 µg/g to 500 µg/g of carbon in UO2, (U,Gd)O2 and (U,Pu)O2 powder and pellets.

]]> ISO 21613:2015 ?u=/product/publishers/iso/iso-216132015/ Tue, 05 Nov 2024 22:29:44 +0000 (U, Pu)O2 Powders and sintered pellets — Determination of chlorine and fluorine
Published By Publication Date Number of Pages
ISO 2015-06 18
]]> ISO 21613:2015 describes a method for determining chlorine and fluorine in mixed (U,Pu)O2 powders and sintered pellets. It is applicable for the analysis of samples containing 5 µg.g-1 to 50 µg.g-1 of chlorine and 2 µg.g-1 to 50 µg.g-1of fluorine.

For UO2 powder and sintered pellets, refer to ISO 22875.

]]> ISO 21243:2008 ?u=/product/publishers/iso/iso-212432008/ Tue, 05 Nov 2024 22:27:03 +0000 Radiation protection — Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies — General principles and application to dicentric assay
Published By Publication Date Number of Pages
ISO 2008-09 28
]]> ISO 21243:2008 is to give an overview of the minimum requirements of process and quality-control components of the cytogenetic response for triage of mass casualties. Cytogenetic triage is the use of chromosome damage to evaluate approximately and rapidly radiation doses received by individuals in order to supplement the early clinical categorization of casualties. ISO 21243:2008 concentrates on organizational aspects of applying the dicentric assay for operation in a triage mode. The technical aspects of the dicentric assay can be found in the ISO 19238, ISO 21243:2008 is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories.

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