EJ/T 20150.10-2018 Active Industry standards-The nuclear industry

EJ/T 20150.10-2018 EJ/T 20150.10-2018 Post irradiation inspection of PWR fuel assembly - Part 10: Detection of fuel rod leaks by bubble method

EJ/T 20150.10-2018 EJ/T 20150.10-2018 Post irradiation inspection of PWR fuel assembly - Part 10: Detection of fuel rod leaks by bubble method

Publish Date: 2018-01-18 Implement Date: 2018-05-01 For services related to genuine standard inquiry, procurement, translation, and other related services in China, please Contact Us

Basic Information

Standard Code: EJ/T 20150.10-2018
Standard Type: Industry standards
Standard Status: Active
is_force_gb: no
CCS Name: Nuclear materials, nuclear fuels, and their analysis and testing methods
ICS Name: Fissile material
Publish Date: 2018-01-18
Implement Date: 2018-05-01

Scope

This section specifies the outline of the bubble method for leak detection of fuel rods in pressurized water reactors after irradiation, including the inspection personnel, inspection equipment, inspection conditions, inspection steps, and result processing. This section is applicable to the bubble method for leak detection of fuel rods in pressurized water reactors after irradiation.

Development Information

Same series standard

EJ/T 20150.1-2018 Radiation inspection of pressurized water reactor fuel assembly bundles after irradiation - Part 1: General principles EJ/T 20150.2-2018 Checking of irradiated pressurized water reactor fuel assembly beam-type component - Part 2: Underwater visual inspection of fuel assemblies EJ/T 20150.7-2018 Checking of irradiated fuel assembly in pressurized water reactor (PWER) with rod bundle type - Part 7: Visual inspection of fuel rods EJ/T 20150.11-2018 Radiation inspection of pressurized water reactor fuel assembly after irradiation - Part 11: Detection of fuel rod leak by helium mass spectrometry EJ/T 20150.12-2018 EJ/T 20150.12-2018 Post irradiation inspection of pressurized water reactor fuel bundle type components - Part 12: Detection of fuel rod leaks - End pressure test method EJ/T 20150.13-2018 Radiation Exposure of Pressurized Water Reactor Fuel Assembly Components - Part 13: X-ray Inspection of Fuel Rods EJ/T 20150.14-2018 Checking of irradiated pressurized water reactor fuel assembly - Part 14: Eddy current testing of fuel rods EJ/T 20150.16-2018 Checking of irradiated fuel assembly in pressurized water reactor - Part 16: Pressure measurement inside fuel rods EJ/T 20150.17-2018 Checking of irradiated pressure water reactor fuel assembly - Part 17: Analysis of krypton and xenon in fission gases using gas chromatography method EJ/T 20150.18-2018 Radiation inspection of pressurized water reactor fuel assembly after irradiation - Part 18: Sampling technical requirements for fuel rods EJ/T 20150.19-2018 Check of irradiated pressure water reactor fuel assembly, Part 19: Tensile testing of cladding tube of fuel assembly EJ/T 20150.21-2018 Post-irradiation inspection of pressurized water reactor rod bundle fuel assembly - Part 21: Pressure burst testing of cladding tube fuel can only provide the English translation of the text EJ/T 20150.23-2018 Fuel assembly inspection after irradiation for pressurized water reactor (PWR) rod bundle type, Part 23: Scanning electron microscopy analysis of cladding tube EJ/T 20150.25-2018 Radiation Inspection of Pressurized Water Reactor Bearing Column Fuel Assembly After Exposure - Part 25: Microstructure Examination of Fuel Rods EJ/T 20150.26-2018 Post-irradiation inspection of pressurized water reactor rod bundle fuel assembly - Part 26: Micro-Vickers hardness testing of cladding tube specimens EJ/T 20150.27-2018 Radiation inspection of pressurized water reactor fuel assembly after irradiation - Part 27: Absolute fuel rod burn-up measurement by mass spectrometry EJ/T 20150.28-2018 Radiation inspection of pressurized water reactor fuel assembly after irradiation - Part 28: Absolute fuel burnup measurement by activity method EJ/T 20150.29-2018 Checking the radiation damage of the fuel assembly with the beam type in a pressurized water reactor - Part 29: Measurement of hydrogen content in the cladding tube of fuel elements using high frequency electrode heat conduction method EJ/T 20150.30-2018 Radiation inspection of pressurized water reactor fuel assembly - Part 30: Measurement of elements Fe, Ni, Cr, Mn, Si, Cu in surface deposits of cladding tube by atomic emission spectroscopy

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