EN ISO 19226:2020
(Main)Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals (ISO 19226:2017)
Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals (ISO 19226:2017)
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.
Kernenergie - Bestimmung der Neutronenfluenz und Verschiebungen pro Atom (dpa) im Reaktordruckbehälter und Einbauten (ISO 19226:2017)
Dieses Dokument stellt bei gegebener Neutronenquelle im Kern ein Verfahren zur Auswertung von Bestrahlungsdaten im Bereich zwischen dem Reaktorkern und der Innenfläche des Kernbehälters, durch den Reaktordruckbehälter und die Reaktor¬grube, auf der Höhe der Brennstoffsäule dar.
ANMERKUNG Diese Bestrahlungsdaten könnten Neutronenfluenz oder Verschiebungen pro Atom (dpa) und Helium¬produktion sein.
Die Auswertung erfolgt sowohl mit Neutronenflussberechnungen als auch mit Messdaten aus der Behälter und Hohlraumdosimetrie. Dieses Dokument gilt für Druckwasserreaktoren (DWR), Siedewasser¬reaktoren (SWR) und Druckschwerwasserreaktoren (PHWR).
Dieses Dokument enthält außerdem ein Verfahren zur Bewertung der Neutronenschädigungseigenschaften am Reaktordruckbehälter und der Kerneinbauten von DWR, SWR und PHWR. Die Schädigungs¬eigenschaften konzentrieren sich auf atomare Verschiebungsschäden durch direkte Verschiebungen von Atomen aufgrund von Kollisionen mit Neutronen und indirekte Schäden durch Gasproduktion, die beide stark vom Neutronenenergiespektrum abhängig sind. Daher sind Berechnungen der Gesamtzahl der Atomverschiebungen für eine gegebene Neutronenfluenz und ein gegebenes Neutronenenergiespektrum wichtige Daten, die für das Management der Reaktorlebensdauer verwendet werden.
Énergie nucléaire - Détermination de la fluence neutronique et des déplacements par atome (dpa) dans la cuve et les internes du réacteur (ISO 19226:2017)
Le présent document fournit une procédure d'évaluation des données d'irradiation dans la région située entre le cœur du réacteur et la surface interne de la cuve, à travers la cuve sous pression et la cavité du réacteur, entre les extrémités des assemblages combustibles, pour une source donnée de neutrons dans le cœur.
NOTE Ces données d'irradiation peuvent être la fluence neutronique ou les déplacements par atome (dpa), et la production d'Hélium.
Cette évaluation s'appuie à la fois sur des calculs de flux de neutrons et sur des données de mesures de dosimétrie à l'intérieur de la cuve et de la cavité, selon les cas. Le présent document s'applique aux réacteurs à eau sous pression (Pressurized Water Reactors, PWR), aux réacteurs à eau bouillante (Boiling Water Reactors, BWR) et aux réacteurs à eau lourde pressurisée (Pressurized Heavy Water Reactors, PHWR).
Le présent document donne également une procédure d'évaluation des endommagements dus aux neutrons sur la cuve sous pression du réacteur et les composants internes des PWR, BWR et PHWR. Les endommagements sont axés sur les dommages de déplacements atomiques causés par le déplacement direct des atomes dû aux collisions avec les neutrons, et sur les dommages indirects causés par la production de gaz, les deux types de dommages étant fortement dépendants du spectre d'énergie des neutrons. Pour une fluence neutronique et un spectre d'énergie des neutrons donnés, le calcul du nombre cumulé total de déplacements atomiques est donc une donnée importante à utiliser pour la gestion de la durée de vie du réacteur.
Jedrska energija - Ugotavljanje pretoka nevtronov in premikov na atom (dpa) v reaktorski posodi in vgrajenih delih (ISO 19226:2017)
General Information
Standards Content (Sample)
SLOVENSKI STANDARD
01-maj-2020
Jedrska energija - Ugotavljanje pretoka nevtronov in premikov na atom (dpa) v
reaktorski posodi in vgrajenih delih (ISO 19226:2017)
Nuclear energy - Determination of neutron fluence and displacement per atom (dpa) in
reactor vessel and internals (ISO 19226:2017)
Kernenergie - Bestimmung der Neutronenfluenz und Verschiebungen pro Atom (dpa) im
Reaktorbehälter und Einbauten (ISO 19226:2017)
Énergie nucléaire - Détermination de la fluence neutronique et des déplacements par
atome (dpa) dans la cuve et les internes du réacteur (ISO 19226:2017)
Ta slovenski standard je istoveten z: EN ISO 19226:2020
ICS:
27.120.10 Reaktorska tehnika Reactor engineering
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.
EN ISO 19226
EUROPEAN STANDARD
NORME EUROPÉENNE
February 2020
EUROPÄISCHE NORM
ICS 27.120.10
English Version
Nuclear energy - Determination of neutron fluence and
displacement per atom (dpa) in reactor vessel and
internals (ISO 19226:2017)
Énergie nucléaire - Détermination de la fluence Kernenergie - Bestimmung der Neutronenfluenz und
neutronique et des déplacements par atome (dpa) dans Verschiebungen pro Atom (dpa) im Reaktorbehälter
la cuve et les internes du réacteur (ISO 19226:2017) und Einbauten (ISO 19226:2017)
This European Standard was approved by CEN on 6 January 2020.
CEN members are bound to comply with the CEN/CENELEC Internal Regulations which stipulate the conditions for giving this
European Standard the status of a national standard without any alteration. Up-to-date lists and bibliographical references
concerning such national standards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN
member.
This European Standard exists in three official versions (English, French, German). A version in any other language made by
translation under the responsibility of a CEN member into its own language and notified to the CEN-CENELEC Management
Centre has the same status as the official versions.
CEN members are the national standards bodies of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia,
Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway,
Poland, Portugal, Republic of North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and
United Kingdom.
EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION
EUROPÄISCHES KOMITEE FÜR NORMUNG
CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels
© 2020 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 19226:2020 E
worldwide for CEN national Members.
Contents Page
European foreword . 3
European foreword
The text of ISO 19226:2017 has been prepared by Technical Committee ISO/TC 85 "Nuclear energy,
nuclear technologies, and radiological protection” of the International Organization for Standardization
(ISO) and has been taken over as EN ISO 19226:2020 by Technical Committee CEN/TC 430 “Nuclear
energy, nuclear technologies, and radiological protection” the secretariat of which is held by AFNOR.
This European Standard shall be given the status of a national standard, either by publication of an
identical text or by endorsement, at the latest by August 2020, and conflicting national standards shall
be withdrawn at the latest by August 2020.
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CEN shall not be held responsible for identifying any or all such patent rights.
According to the CEN-CENELEC Internal Regulations, the national standards organizations of the
following countries are bound to implement this European Standard: Austria, Belgium, Bulgaria,
Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, France, Germany, Greece, Hungary, Iceland,
Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Republic of
North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the
United Kingdom.
Endorsement notice
The text of ISO 19226:2017 has been approved by CEN as EN ISO 19226:2020 without any modification.
INTERNATIONAL ISO
STANDARD 19226
First edition
2017-11
Nuclear energy — Determination of
neutron fluence and displacement
per atom (dpa) in reactor vessel and
internals
Énergie nucléaire — Détermination de la fluence neutronique et du
déplacement par atome (dpa) dans la cuve et les internes du réacteur
Reference number
ISO 19226:2017(E)
©
ISO 2017
ISO 19226:2017(E)
© ISO 2017, Published in Switzerland
All rights reserved. Unless otherwise specified, no part of this publication may be reproduced or utilized otherwise in any form
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ii © ISO 2017 – All rights reserved
ISO 19226:2017(E)
Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
4 Transport theory calculational models . 3
4.1 General . 3
4.1.1 Output requirements. 3
4.1.2 Methodology: transport calculations with fixed sources . 3
4.2 Transport calculation . 4
4.2.1 Input data . 4
4.2.2 Discrete ordinates (SN) method . 4
4.2.3 Monte Carlo transport method . 4
4.2.4 Adjoint fluence calculations . 5
4.3 Validation of neutron fluence calculational values . 5
4.4 Determination of calculational uncertainties . 5
5 Reactor pressure vessel neutron dosimetry measurements . 6
5.1 Introduction . 6
5.2 General requirements for reactor vessel neutron metrology . 6
5.3 Stable-product neutron dosimeters . 7
5.4 Dosimeter response parameters . 7
5.5 Uncertainty estimates and measurement validation in standard neutron fields . 7
6 Comparison of calculations with measurements . 8
6.1 Introduction . 8
6.2 Direct comparison of calculated activities with measured sensor activities . 8
6.3 Comparison of calculated rates with measured average full-power reaction rates . 8
6.4 Comparison of the calculations against measurements using least-squares methods . 8
7 Determination of the best-estimate fluence . 9
8 Calculational methods for dpa and gas production . 9
8.1 Displacements per atom (dpa) . 9
8.2 Gas production . 9
Bibliography .11
ISO 19226:2017(E)
Foreword
ISO (the International Organization for Standardization) is a worldwide federation of national standards
bodies (ISO member bodies). The work of preparing International Standards is normally carried out
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electrotechnical standardization.
The procedures used to develop this document and those intended for its further maintenance are
described in the ISO/IEC Directives, Part 1. In particular the different approval criteria needed for the
different types of ISO documents should be noted. This document was drafted in accordance with the
editorial rules of the ISO/IEC Directives, Part 2 (see www.iso.org/directives).
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. ISO shall not be held responsible for identifying any or all such patent rights. Details of
any patent rights identified during the development of the document will be in the Introduction and/or
on the ISO list of patent declarations received (see www.iso.org/patents).
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For an explanation on the voluntary nature of standards, the meaning of ISO specific terms and
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URL: www.iso.org/iso/foreword.html.
This document was prepared by Technical committee ISO/TC 85, Nuclear energy, nuclear technologies,
and radiological protection, Subcommittee SC 6, Reactor Technology.
This document is based on the ANSI/ANS 19.10-2009 but extends to cover the evaluation of irradiation
damage due to neutron fluence.
iv © ISO 2017 – All rights reserved
ISO 19226:2017(E)
Introduction
This document is intended for use by
a) those involved in the determination of exposure parameters for the prediction of irradiation
damage to the vessel and to the internals of a nuclear reactor, where the exposure parameters can
be neutron fluence and/or displacements per atom (dpa),
b) those involved in the determination of material properties of irradiated reactor vessel and reactor
internals,
c) regulatory agencies in licensing actions such as the writing of Regulatory Guides, analysis of
reports concerning the integrity and
...
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