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Normas DIN – AENOR
DIN EN ISO 19226:2019-09

DIN EN ISO 19226:2019-09

Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals (ISO 19226:2017); German and English version prEN ISO 19226:2019 / Note: Date of issue 2019-08-23

Énergie nucléaire - Détermination de la fluence neutronique et des déplacements par atome (dpa) dans la cuve et les internes du réacteur (ISO 19226:2017); Version allemande et anglaise prEN ISO 19226:2019 / Attention: Date de parution 2019-08-23

Kernenergie - Bestimmung der Neutronenfluenz und Verschiebungen pro Atom (dpa) im Reaktorbehälter und Einbauten (ISO 19226:2017); Deutsche und Englische Fassung prEN ISO 19226:2019 / Achtung: Erscheinungsdatum 2019-08-23

Fecha Anulación:
2020-05 /Withdrawn
Equivalencias internacionales:

ISO 19226 (2017-11)

prEN ISO 19226 (2019-09)

Relación con otras normas DIN:

Reemplazada por: DIN EN ISO 19226:2020-05

Resumen:
ISO 19226:2017 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).ISO 19226:2017 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.
Keywords:
Attenuation, Cavity, Cores, Definitions, Extrapolation, Flux (rate), Internal, Irradiation, Measurement, Neutron fluence, Nuclear technology, Plant, Prediction, Pressure vessels, Radiant flux, Radiation, Reactor technology, Reactor vessels, Reactors, Surfaces, Transport, Validation, Vessels
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