Cena s DPH / bez DPH
Hlavní stránka>BS ISO 20890-5:2020 Guidelines for in-service inspections for primary coolant circuit components of light water reactors Eddy current testing of steam generator heating tubes
Sponsored link
sklademVydáno: 2020-06-22
BS ISO 20890-5:2020 Guidelines for in-service inspections for primary coolant circuit components of light water reactors Eddy current testing of steam generator heating tubes

BS ISO 20890-5:2020

Guidelines for in-service inspections for primary coolant circuit components of light water reactors Eddy current testing of steam generator heating tubes

Formát
Dostupnost
Cena a měna
Anglicky Zabezpečené PDF
K okamžitému stažení
6448 Kč
Čtěte normu po dobu 1 hodiny. Více informací v kategorii E-READING
Čtení normy
na 1 hodinu
644.80 Kč
Čtěte normu po dobu 24 hodin. Více informací v kategorii E-READING
Čtení normy
na 24 hodin
1934.40 Kč
Anglicky Tisk
Skladem
6448 Kč
Označení normy:BS ISO 20890-5:2020
Počet stran:26
Vydáno:2020-06-22
ISBN:978 0 580 93457 5
Status:Standard
Popis

BS ISO 20890-5:2020


This standard BS ISO 20890-5:2020 Guidelines for in-service inspections for primary coolant circuit components of light water reactors is classified in these ICS categories:
  • 27.120.10 Reactor engineering

This document gives guidelines for pre-service inspection (PSI) and in-service inspections (ISI) by eddy current tests on non-ferromagnetic steam generator heating tubes of light water reactors, whereby the test is carried out using mechanised test equipment outwards from the tube inner side.

An in-service eddy current test of steam generator heating tube plugs as a component of the primary circuit is not an object of this document. Owing to the different embodiments of steam generator heating tube plugs, the use of specially adapted test systems to be qualified is necessary.

Test systems for the localisation of inhomogeneities (surface) and requirements for test personnel, test devices, the preparation of test and device systems, the implementation of the testing as well as the recording are defined.

NOTE

Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the nuclear safety standards.

It is recommended that the technical specifications are based on experience on U-tube bends with even bend radius (similar to the S/KWU design). To test other kind of tube bends (e.g. U-tube bends with two 90° bends) further qualifications will be provided.