BS EN ISO 19226:2020
$142.49
Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
| Published By | Publication Date | Number of Pages |
| BSI | 2020 | 24 |
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.
PDF Catalog
| PDF Pages | PDF Title |
|---|---|
| 2 | undefined |
| 5 | European foreword Endorsement notice |
| 8 | Foreword |
| 9 | Introduction |
| 11 | 1 Scope 2 Normative references 3 Terms and definitions |
| 13 | 4 Transport theory calculational models 4.1 General 4.1.1 Output requirements 4.1.2 Methodology: transport calculations with fixed sources |
| 14 | 4.2 Transport calculation 4.2.1 Input data 4.2.2 Discrete ordinates (SN) method 4.2.3 Monte Carlo transport method |
| 15 | 4.2.4 Adjoint fluence calculations 4.3 Validation of neutron fluence calculational values 4.4 Determination of calculational uncertainties |
| 16 | 5 Reactor pressure vessel neutron dosimetry measurements 5.1 Introduction 5.2 General requirements for reactor vessel neutron metrology |
| 17 | 5.3 Stable-product neutron dosimeters 5.4 Dosimeter response parameters 5.5 Uncertainty estimates and measurement validation in standard neutron fields |
| 18 | 6 Comparison of calculations with measurements 6.1 Introduction 6.2 Direct comparison of calculated activities with measured sensor activities 6.3 Comparison of calculated rates with measured average full-power reaction rates 6.4 Comparison of the calculations against measurements using least-squares methods |
| 19 | 7 Determination of the best-estimate fluence 8 Calculational methods for dpa and gas production 8.1 Displacements per atom (dpa) 8.2 Gas production |
| 21 | Bibliography |
