Norm

ISO/DIS 19226:2017 en

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

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Over deze norm

Status Ontwerp
Aantal pagina's 12
Gepubliceerd op 24-01-2017
Taal Engels
This International Standard 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. These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production (in BWRs and PHWRs). The evaluation employs both neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. This International Standard applies to pressurized water reactors (PWRs), boiling water reactors (BWRs), and pressurized heavy water reactors (PHWRs). This International Standard 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 direct damage caused by neutron fluence and indirect damage caused by gas production. Therefore, fluence calculation is an important data to determinate reactor lifetime.

Details

ICS-code 27.120.10
Nederlandse titel Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
Engelse titel Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals

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