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SLOVENSKI STANDARD
01-februar-2023
Gradbeni proizvodi - Ocenjevanje sproščanja nevarnih snovi - Ocenjevanje doze
emitiranega gama sevanja
Construction products: Assessment of release of dangerous substances - Dose
assessment of emitted gamma radiation
Bauprodukte - Bewertung der Freisetzung von gefährlichen Stoffen - Verfahren zur
Beurteilung von emittierter Gammastrahlung
Produits de construction : Évaluation de l’émission de substances dangereuses -
Évaluation de la dose de rayonnement gamma émis
Ta slovenski standard je istoveten z: EN 17637:2022
ICS:
13.020.99 Drugi standardi v zvezi z Other standards related to
varstvom okolja environmental protection
13.280 Varstvo pred sevanjem Radiation protection
91.100.01 Gradbeni materiali na Construction materials in
splošno general
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.
EN 17637
EUROPEAN STANDARD
NORME EUROPÉENNE
November 2022
EUROPÄISCHE NORM
ICS 91.100.01
English Version
Construction products: Assessment of release of
dangerous substances - Dose assessment of emitted
gamma radiation
Produits de construction : Évaluation de l'émission de Bauprodukte - Bewertung der Freisetzung von
substances dangereuses - Évaluation de la dose de gefährlichen Stoffen - Verfahren zur Beurteilung von
rayonnement gamma émis emittierter Gammastrahlung
This European Standard was approved by CEN on 13 June 2022.
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, Türkiye 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
© 2022 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN 17637:2022 E
worldwide for CEN national Members.
Contents Page
European foreword . 3
Introduction . 4
1 Scope . 5
2 Normative references . 5
3 Terms and definitions . 6
4 Symbols and abbreviated terms . 8
5 Method for dose assessment . 9
5.1 General . 9
5.2 Assessment for evaluation of a construction product .11
5.2.1 Product information .11
5.2.2 Dose assessment of the construction product .12
5.2.3 Dose assessment of the model building .14
5.3 Assessment for evaluation of a building design .15
5.3.1 Product information .15
5.3.2 Dose assessment of the construction product .16
5.3.3 Dose assessment of the model building .19
6 Reporting .19
Annex A (informative) Description of the dose assessment model .20
A.1 General .20
A.2 Method description .20
A.3 Dimensions of the model room .20
A.4 Model assumptions .20
Annex B (informative) Examples of dose assessment .22
B.1 Assessment for evaluation of the construction product .22
B.2 Assessment for evaluation of the building design .25
Bibliography .28
European foreword
This document (EN 17637:2022) has been prepared by Technical Committee CEN/TC 351 “Construction
products: Assessment of release of dangerous substances”, the secretariat of which is held by NEN.
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 May 2023, and conflicting national standards shall be
withdrawn at the latest by May 2023.
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.
This document has been prepared under a Standardization Request given to CEN by the European
Commission and the European Free Trade Association.
Any feedback and questions on this document should be directed to the users’ national standards body.
A complete listing of these bodies can be found on the CEN website.
According to the CEN-CENELEC Internal Regulations, the national standards organisations 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, Türkiye and the United
Kingdom.
Introduction
In January 2014 the Basic Safety Standards Directive (2013/59/Euratom) [1], also named EU-BSS, was
issued laying down basic safety standards for the protection against the danger arising from exposure to
ionising radiation. The directive also sets requirements on the gamma radiation dose from the naturally
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occurring radionuclides ( Ra, Th and K) in building materials and must be taken into account along
with the 2011 EU regulation laying down harmonized conditions for the marketing of construction
products (EU no 305/2011) [2], so called CPR. Both EU regulatory documents constitute a new basis for
radiation protection regulation of building materials and are to be complemented by EU guidance and
standards of which this document (EN 17637) is part.
Pivotal in the regulatory system of the EU-BSS and CPR is the dose assessment of building materials and
its compliance against a reference level as defined under Article 75 of the EU-BSS. For this purpose, an
activity concentration index is provided in the directive under Annex VIII. The index value is determined
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using the material’s massic activities of Ra, Th and K. As the index is proposed as a conservative
screening tool provisions are put in place under Annex VIII to allow for more precise assessment of the
dose if needed. This includes consideration of the material’s density, thickness and other factors relating
to the type of construction and the intended use. However, no method for a more refined dose assessment
is provided in the directive, despite the fact that various EU member states allow for such refined
assessment. This EN document serves as a harmonized standard under the CPR to address the provisions
in the EU-BSS for a more refined assessment.
This document is an addition to the activity concentration index as formulated in the Annex VIII of the
EU-BSS. The method describes a dose assessment that takes account of all factors stipulated under
Annex VIII of the directive. In the method, important consideration is given to differentiate between the
dose from the individual construction product and the assembly of products that result in the dose from
the model building. In the EU-BSS dose requirements are expressed in terms of a dose from the building,
while the CPR is intended to set product specific requirements. For this reason, the method provides for
a calculation of dose from the individual product, followed by a calculation of the product assembly with
subtraction of terrestrial background dose to enable assessment against the reference level defined in
Article 75 of the EU-BSS.
The document provides the following structure:
— A normative instruction on the use of the assessment method with description of the equations and
parameters to be used, followed by a list of information to be reported;
— An informative annex with a description of the dose assessment model, including explanation of the
modelling principles, main assumptions, coefficients and conversion factors;
— An informative annex containing a series of examples on the use of the assessment method.
1 Scope
This document describes a calculation method to determine the indoor gamma dose from construction
products. The method includes calculation of the indoor gamma dose from the individual construction
product under its intended use, as well as the dose from the building taking consideration of multiple
building materials where this is deemed necessary and any shielding from the terrestrial background.
The calculation method builds on existing modelling principles for photon emission and absorption.
Parameters of the modelling that are not product specific, such as room geometry, exposure coefficients,
and conversion factors are predefined and form the underlying basis for the method in this EN. The choice
for pre-defined model parameters is essential from a harmonization perspective, despite the fact that
such parameters can vary considerably for every homeowner, building type, region or country. Typical
examples are the exposure time, the location of exposure in the building, the terrestrial background
radiation and the amounts and way the building materials are used in the building. The parameters are
selected on the basis of international consensus, as laid down in ICRP, UNSCEAR, EU RP guidelines and
other renowned publications. Product specific parameters such as density and thickness are specified in
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accordance with the product’s intended use. In addition, the product’s massic activities of Ra, Th and
K are specified and obtained according to prEN 17216 [3]. The method provides a tiered approach
with a basic approach intended for assessing individual construction products, followed by a more
refined approach to assess a complete building design. The former approach assumes an identical
structure of building materials on all six surfaces of the model room, and where needed complemented
with other building materials that form an intrinsic part of the product’s intended use. The latter
approach enables evaluation of a known building design. Here the user can specify the applied
construction product to walls, floor or ceiling separately in accordance with the product’s intended use.
The indoor gamma dose from the individual construction product as well as the building is expressed in
terms of an annual effective dose from gamma radiation in the indoor environment. The formulation of
the indoor gamma dose in the building is consistent with the dose for indoor external exposure as stated
under Article 75 of the Basic Safety Standards Directive. As a result, the described method enables
assessment of the calculated annual dose of the building against the reference level as defined in the Basic
Safety Standards Directive .
The method is designed for assessment of mineral based building materials applied in bulk or
superficially and used as a construction product in buildings. This includes any building materials that
have been identified by EU member states as being of concern from a radiation protection point of view.
The method is envisaged for use by producers of building materials, architects and building constructors
a
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