PRICES include / exclude VAT
Homepage>BS Standards>27 ENERGY AND HEAT TRANSFER ENGINEERING>27.120 Nuclear energy engineering>27.120.10 Reactor engineering>BS EN ISO 19226:2020 Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
Sponsored link
immediate downloadReleased: 2020-03-18
BS EN ISO 19226:2020 Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals

BS EN ISO 19226:2020

Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals

Format
Availability
Price and currency
English Secure PDF
Immediate download
266.20 EUR
You can read the standard for 1 hour. More information in the category: E-reading
Reading the standard
for 1 hour
26.62 EUR
You can read the standard for 24 hours. More information in the category: E-reading
Reading the standard
for 24 hours
79.86 EUR
English Hardcopy
In stock
266.20 EUR
Standard number:BS EN ISO 19226:2020
Pages:24
Released:2020-03-18
ISBN:978 0 539 05834 5
Status:Standard
DESCRIPTION

BS EN ISO 19226:2020


This standard BS EN ISO 19226:2020 Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals is classified in these ICS categories:
  • 27.120.10 Reactor engineering

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.