International Organization for Standardization (ISO)
Latest
ISO 19226:2017
Scope
This document provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core.
NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production.
The evaluation employs both neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. This document applies to pressurized water reactors (PWRs), boiling water reactors (BWRs), and pressurized heavy water reactors (PHWRs).
This document also provides a procedure for evaluating neutron damage properties at the reactor pressure vessel and internal components of PWRs, BWRs, and PHWRs. Damage properties are focused on atomic displacement damage caused by direct displacements of atoms due to collisions with neutrons and indirect damage caused by gas production, both of which are strongly dependent on the neutron energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, calculations of the total accumulated number of atomic displacements are important data to be used for reactor life management.
ISO 19226:2017 Referenced Document
ANSI/ANS 19.10-2009 Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals*, 2024-04-20 Update
ASTM E1005-16 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance*, 2024-04-20 Update
ASTM E1297-08 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
ASTM E170-16 Standard Terminology Relating to Radiation Measurements and Dosimetry*, 2024-04-20 Update
ASTM E181-10 Standard Test Methods for Detector Calibration and Analysis of Radionuclides
ASTM E2006-16 Standard Guide for Benchmark Testing of Light Water Reactor Calculations*, 2024-04-20 Update
ASTM E261-16 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques*, 2024-04-20 Update
ASTM E263-13 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron*, 2024-04-20 Update
ASTM E264-08 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel*, 2024-04-20 Update
ASTM E523-16 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
ASTM E526-08 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium*, 2024-04-20 Update
ASTM E704-13 Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238*, 2024-04-20 Update
ASTM E705-13 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237*, 2024-04-20 Update
ASTM E854-03 Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)*, 2024-04-20 Update
ASTM E910-07 Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)*, 2024-04-20 Update
ISO 8529-1:2001 Reference neutron radiations - Part 1: Characteristics and methods of production
ISO 19226:2017 history
2017ISO 19226:2017 Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals