SIST-TP CEN/TR 17113:2018

SLOVENSKI STANDARD
kSIST-TP FprCEN/TR 17113:2017
01-marec-2017
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Construction products - Assessment of release of dangerous substances - Radiation
from construction products - Dose assessment of emitted gamma radiation
Bauprodukte - Bewertung der Freisetzung von gefährlichen Stoffen - Festlegung des
Verfahrens zur Beurteilung der Strahlendosis und Klassifizierung von emittierter
Gammastrahlung
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Ta slovenski standard je istoveten z: FprCEN/TR 17113
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
kSIST-TP FprCEN/TR 17113:2017 en
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

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kSIST-TP FprCEN/TR 17113:2017

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kSIST-TP FprCEN/TR 17113:2017


FINAL DRAFT
TECHNICAL REPORT
FprCEN/TR 17113
RAPPORT TECHNIQUE

TECHNISCHER BERICHT

February 2017
ICS
English Version

Construction products - Assessment of release of
dangerous substances - Radiation from construction
products - Dose assessment of emitted gamma radiation
Produits de construction - Evaluation de l¿émission de Bauprodukte - Bewertung der Freisetzung von
substances dangereuses ¿ Détermination de gefährlichen Stoffen - Festlegung des Verfahrens zur
l¿estimation dosimétrique et classification en fonction Beurteilung der Strahlendosis und Klassifizierung von
de l¿émission de rayonnement gamma emittierter Gammastrahlung


This draft Technical Report is submitted to CEN members for Vote. It has been drawn up by the Technical Committee CEN/TC
351.

CEN members are the national standards bodies of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia,
Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania,
Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,
Turkey and United Kingdom.

Recipients of this draft are invited to submit, with their comments, notification of any relevant patent rights of which they are
aware and to provide supporting documentation.

Warning : This document is not a Technical Report. It is distributed for review and comments. It is subject to change without
notice and shall not be referred to as a Technical Report.


EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION

EUROPÄISCHES KOMITEE FÜR NORMUNG

CEN-CENELEC Management Centre: Avenue Marnix 17, B-1000 Brussels
© 2017 CEN All rights of exploitation in any form and by any means reserved Ref. No. FprCEN/TR 17113:2017 E
worldwide for CEN national Members.

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Contents Page
European foreword . 4
Introduction . 5
1 Scope . 7
2 Terms and definitions . 7
3 European Regulatory Framework . 9
3.1 Provisions on radiation protection . 9
3.2 Provisions on the marketing of construction products . 11
3.3 Radon exhalation from building materials . 11
4 Provisions for dose assessment . 11
4.1 General . 11
4.2 Principle of calculation . 12
4.3 Room model . 12
4.4 Basic assumptions. 13
4.4.1 Shielding effect of materials for cosmic radiation . 14
4.4.2 Conversion factor for absorbed dose in air . 14
4.4.3 Occupancy . 14
4.4.4 Activity concentrations for reference concrete in Europe . 14
4.5 Graded approach to dose assessment taking into account density and thickness . 14
4.6 Assessment of indoor gamma exposure due to building materials and construction
products . 17
4.6.1 General . 17
4.6.2 Composite material . 18
4.6.3 Dose estimate considering thickness and density . 19
4.6.4 Roof tiles . 19
4.6.5 Materials not complying to Formula (3) . 20
4.6.6 Conclusive . 20
Annex A (informative) Calculation of external gamma dose rate . 21
A.1 Calculation of gamma dose rate . 21
A.2 Parameters for a simple computer program . 23
Annex B (informative) Examples of dose assessment using Table 2 . 25
226
B.1 Example 1: Exposure to gamma radiation in a concrete room where the Ra and
232
Th concentrations are slightly above average . 25
B.2 Example 2: Exposure to gamma radiation in a room where the walls are made of
226 232
material with elevated Ra and Th concentrations and the floor and ceiling of
typical concrete . 26
B.3 Example 3: Exposure to gamma radiation in a room with concrete floor and ceiling,
and cavity walls with brick and limestone . 27
Annex C (informative) Estimate of indoor gamma dose based on mass per unit area as
control parameter . 29
Annex D (informative) Validation of the dose modelling and a density corrected index
formula. 35
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D.1 General . 35
D.2 Calculations . 35
D.3 Conclusion . 39
Annex E (informative) Considerations on and justification for choosing an appropriate room
size . 40
E.1 General . 40
E.2 Chosen dimensions for the model room . 41
E.3 Calculation of values given in Table E.1 . 42
E.3.1 Rooms 1a and 1b, with dimensions 12 m × 7 m × 2,8 m . 42
E.3.2 Rooms 2a and 2b, with dimensions 3 m × 4 m × 2,5 m . 42
E.4 Specific dose rates from different structures in the CEN/TS 16516 model room . 43
Bibliography . 47


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European foreword
This document (FprCEN/TR 17113:2017) 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 document is currently submitted to the Vote on TR.
This document has been prepared under a mandate given to CEN by the European Commission and the
European Free Trade Association.
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Introduction
The aim of this report is to propose a dose assessment methodology that accounts for factors such as
density or thickness of the material as well as factors relating to the type of construction and the
intended use of the material (bulk or superficial) as required by Annex VIII of the Euratom-BSS [1]. This
approach is specially needed for building materials and construction products with an index exceeding
1 but that nonetheless may comply with the 1 mSv per year reference level established in the Euratom-
BSS [1].
NOTE Although the methodology is centred around the reference level of 1 mSv established in the Euratom-
BSS, the methodology is also applicable if a reference value other than 1 mSv per year is selected. In that case, the
selected dose value D and its corresponding index value I is adjusted accordingly.
In 1996, natural radiation sources were already included in the standards established by Euratom as
well as those established by the IAEA [2]. Since then, the European Commission has moved ahead
publishing, on a regular basis, technical support guidance and recommendations on Naturally Occurring
Radioactive Material (NORM) issues. In 1997, for instance, recommendations [3] were published to help
deal with "significant increase in exposure due to natural radiations". In 1999, the European
Commission published radiological protection principles concerning the natural radioactivity of
building materials [4] and reference levels for workplaces processing materials with enhanced levels of
naturally occurring radionuclides [5]. Lastly, in 2001 the European Commission published
recommendations dealing with exemption and clearance levels for NORM residues [6].
These recommendations have provided Member States with criteria and a sound technical framework
to help establish national regulations for NORM and building materials. Some Member States have
already included all or parts of these recommendations in their regulatory framework anticipating the
new EU directive.
Subsequently, the European Commission decided to harmonize, promote and consolidate the main
recommendations, introducing them into a new Council directive (2013/59/Euratom; Euratom-BSS
[1]) laying down basic safety standards for the protection against the danger arising from exposure to
ionising radiation. This BSS directive was officially issued in January 2014. Member States have four
years to transpose and implement this directive and according to the Euratom treaty, these members
will before then, communicate to the Commission their existing and draft provisions. The Commission
will then make appropriate recommendations for harmonizing the provisions amongst member States.
Requirements of this directive (Euratom-BSS, [1]) dealing with building materials are hereby presented.
They should be taken into account along with the 2011 EU regulation laying down harmonized
conditions for the marketing of construction products (EU no 305/2011) [7], so called CPR, containing
many relevant articles which complement the aforesaid directive.
Both EU regulatory documents constitute the new basis for building material radiation protection
regulation and should be soon followed by more detailed EU guidance and standards of which this
document (FprCEN/TR 17113) should be part.
The European Commission (EC) has mandated the CEN to establish EU harmonized standards regarding
dose assessment of emitted gamma radiation from construction products. The EC has also informed
CEN (CEN/TC 351, Berlin 11 February 2013) that the aim is to establish one test method per product, or
product type, that the method should be demonstrably robust and should be adopted by all Member
States as soon as the Euratom-BSS comes into force.
This document can help Member State regulators to complete the Euratom-BSS and CPR regulatory
framework covering a screening tool, dose modelling, and related technical information about radiation
protection. Amongst others, the following recommendations were discussed by the CEN and the EC for
the content of this document:
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— The scope will exclude radon and thoron exhalation from building materials because this
exhalation is dealt with in a different manner in the EU regulation. Regulatory explanations are
given in Clause 3.
— Main assumptions, coefficients and conversion factors are taken into account.
— The methodology enables establishing which building materials may lead to a dose exceeding
1 mSv per year for a member of the public or which building materials can be exempted from
further restrictions.
2
— Mass per unit area (kg/m ) of the material will be considered in the approach keeping a dose
estimate model based on similar room models as the one used to establish the index mentioned in
the Euratom-BSS.
— Additional sensitivity analysis regarding the room geometry is presented in Annex E to
demonstrate that there is no more than 10 % of influence of such geometry upon the determination
of doses.
Lastly, it is important to underline that the EU regulatory philosophy is to ensure that gamma doses
from building materials to a member of the public remain under 1 mSv per year in addition to outdoor
external exposure (Euratom-BSS Article 75) [1]. A simplified model, so called "index" in the Euratom-
BSS is also proposed as a conservative screening tool ensuring that materials with an index I less than 1
do not present any risk exceeding 1 mSv per year of indoor gamma radiation, in any construction, to a
member of the public.
Annex VIII of the Euratom-BSS Directive presents such an index asking determination of three
radionuclides of gamma radiation. For the purposes of this determination, CEN/TC 351 has developed a
test method to be published first as a Technical Specification (TS) and later after completed validation
as a European Standard (EN). In certain cases, there is a need to assess dose more precisely as
described in Annex VIII of the Euratom-BSS Directive. This TR presents such a formula for more
sophisticated calculation of dose. It could serve as basis for a European approach supporting the
implementation of the Euratom-BSS Directive taking place in member states, also from a harmonized
approach point of view.
As determination of three radionuclides of gamma radiation according to an EN (TS) will be part of
obligations of product manufacturers and will be referred to in harmonized product standards under
the Construction Products Regulation (CPR; EU 305/2011) (hEN) it is proposed that assessment of dose
could be consequently described in an EN.
This Technical Report presents the state-of-the-art on dose assessment presented in RP 112 [4] and
now further developed into the form of a more sophisticated formula. It has been noticed that for
credibility reasons exact correctness of all background data must be further checked. It is proposed that
this could take place when developing a European Standard.
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1 Scope
The aim of this Technical Report is to propose a methodology to determine indoor gamma dose from
building materials and to help classify such a product as required in the Construction Products
Regulation [7]. This first technical approach could be a precursor for the development of a harmonized
European Standard based on this methodology.
NOTE 1 In this Technical Report, doses from radon and thoron exhalation are excluded. However, in 3.3,
information is given on how radon exhalation is dealt with in (EU)2013/59/Euratom, the Basic Safety Standards
Directive (Euratom-BSS) [1].
NOTE 2 Building materials considered in this Technical Report are the construction products used for
buildings. Other construction products used for any other construction works (civil engineering…) are not
relevant and out of the purpose of the scope of this Technical Report.
NOTE 3 Compliance with national exemption levels for NORM nuclides remains.
2 Terms and definitions
For the purposes of this document, the terms and definitions given in EN 16687 [8] and the following
apply.
2.1
authorization
registration or licensing of a practice
[SOURCE: Euratom-BSS, chapter II, Article 4, (7) [1]]
2.2
building material
any construction product for incorporation in a permanent manner in a building or parts thereof and
the performance of which has an effect on the performance of the building with regard to exposure of
its occupants to ionizing radiation
[SOURCE: Euratom-BSS, chapter II, Article 4, (9) [1]]
Note 1 to entry: Building materials considered in this Technical Report are the construction products used for
building works. Other construction products used for any other construction works (civil engineering, etc.) are not
relevant and out of the purpose of the scope of this Technical Report.
2.3
competent authority
authority or system of authorities designated by Member States as having legal authority for the
purposes of the Euratom-BSS [1]
[SOURCE: Euratom-BSS, chapter II, Article 4, (16) [1]]
2.4
effective dose
E
sum of the weighted equivalent doses in all the tissues and organs of the body from internal and
external exposure
Note 1 to entry: It is defined by the expression:
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(1)
E w H w wD
∑ T T ∑∑T R TR,
T TR
where
DT,R is the absorbed dose averaged over tissue or organ T, due to radiation R [-];
wR is the radiation weighting factor [-];
w is the tissue weighting factor for tissue or organ T [-].
T
Note 2 to entry: The values for wT and wR are specified in Annex II of the BSS [1].
Note 3 to entry: The unit for effective dose is the sievert (Sv).
[SOURCE: Euratom-BSS, chapter II, Article 4, (25) [1]]
2.5
exemption level
value established by a competent authority or in legislation and expressed in terms of activity
concentration, total activity at or below which a radiation source is not subject to notification or
authorisation
[SOURCE: Euratom-BSS, chapter II, Article 4, (34) [1]]
2.6
practice
human activity that can increase the exposure of individuals to radiation from a radiation source and is
managed as a planned exposure situation
[SOURCE: Euratom-BSS, chapter II, Article 4, (65) [1]]
2.7
226
Ra
226
radionuclide Ra and its progenies in secular equilibrium
2.8
radon
222
radionuclide Rn and its progeny, as appropriate
[SOURCE: Euratom-BSS, chapter II, Article 4, (82) [1]]
2.9
reference level
level of effective dose or equivalent dose or activity concentration above which it is judged
inappropriate to allow exposures to occur, even though it is not a limit that may not be exceeded
Note 1 to entry: Exposure to gamma radiation from building materials is ranked by the EU BSS among the
existing exposure situations.
[SOURCE: Euratom-BSS, chapter II, Article 4, (84) [1]]
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2.10
regulatory control
any form of control or regulation applied to human activities for the enforcement of radiation
protection requirements
[SOURCE: Euratom-BSS, chapter II, Article 4, (87) [1]]
2.11
Sievert
Sv
special name of the unit of equivalent or effective dose
Note 1 to entry: One sievert is equivalent to one joule per kilogram: 1 Sv = 1 J/kg.
[SOURCE: Euratom-BSS, chapter II, Article 4, (91) [1]]
Note 2 to entry: 1 Gy is also 1 J/kg.
2.12
232
Th
232
radionuclide Th and its progenies in secular equilibrium
2.13
thoron
220
radionuclide Rn and its progeny, as appropriate
[SOURCE: Euratom-BSS, chapter II, Article 4, (97) [1]]
3 European Regulatory Framework
3.1 Provisions on radiation protection
Some new requirements have been established for building materials in the Euratom-BSS [1] but they
derive from earlier EU or IAEA principles and recommendations given in references [4], [5], [6], [9],
[10], [11], [12], and [13]. Such principles and recommendations were taken into consideration by some
Member States but further harmonisation and consistency throughout Europe were to be established.
Existing principles and recommendations were then reviewed and enhanced by EU Member States to be
turned into proper harmonized EU regulations (Euratom-BSS, [1]) which was officially issued in
January 2014.
Building materials of concern, which are to be identified by individual Member States, whether from
natural origin or from those in which specific residues from identified NORM industries have been
incorporated, need to comply with the reference level of 1 mSv per year (compared to outdoor
background dose).
If the dose resulting from a building material exceeds the reference level of 1 mSv per year, the radium
concentration of this material can be quite high and this possibly leads to a significant emission
(exhalation) of radon. Due to the influence of the release (emanation) and of the transport process
(diffusion, convection) inside the building material, no clear correlation between the radium
concentration and the exhalation of radon can be found. Even materials with a low radium
concentration can release a significant and relevant amount of radon. To regulate the radium
concentration is necessary but not sufficient to reduce the radon exhalation.
NOTE 1 The inhalation dose from radon is not considered in the reference level of 1 mSv per year. The radon
from building materials and soil is regulated by a separate reference level for indoor radon concentration.
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There are some examples where building materials have led to an increased dose for the inhabitants of
buildings.
NOTE 2 Examples include lightweight concrete made with alum shale or, in some cases, the use of gypsum from
the phosphate production. In addition, the use of tailings from the production of uranium, slag from the copper
production or sand with high uranium concentrations can be found in formerly used building materials.
NOTE 3 A list of NORM industries is included in Euratom-BSS Annex XIII [1] and is to be taken into account by
Member States when establishing theirs.
NOTE 4 In the case of composite material, like concrete, the activity concentration index can be calculated from
the contribution of the constituents (see Figure 3), and not every constituent will necessarily comply with the
condition I < 1.
The EU RP 112 principles [4] established the first non-prescriptive EU radiation protection framework
concerning the natural radioactivity of building materials. This EU RP 112 was based on a publication
[14] from the Finnish regulator (STUK) and provides EU Member States with a user friendly screening
tool to evaluate building materials’ radiation gamma emissions and help check compliance with the
maximum reference level mentioned above.
To establish this screening tool, a conservative dose estimate model was first created. This model
226 232
considered the activity concentrations of Ra and Th in secular equilibrium with the members of
40
each decay chain (progenies) and K. The calculations were based on a hypothetical room (with
dimensions of 4 m × 5 m × 2,5 m) with walls, ceiling and floor of 20 cm thick and made of a material
3
with a fixed density of 2.350 kg/m (similar to concrete). In this model, it is also assumed: an annual
exposure time of 7.000 hours a year; a dose conversion factor of 0,7 Sv/Gy and a background absorbed
dose rate of 50 nGy/h. The doses were calculated according to the Berger approach with empirical
build-up factors and self-attenuation.
Considering all these assumptions, an activity concentration index (I) was then determined by the
following simplified Formula (2):
C C C
226 232 40
Ra
Th K
I= ++ (2)
300 200 3000
where
226 232 40
C is the activity concentration of Ra, Th or K naturally contained in
most building materials [Bq/kg].
The dose estimate is close to 1 mSv per year only when the index value is close to 1. An index < 1 with
the conditions mentioned above means a dose estimate in compliance with the maximum reference
level of 1 mSv per year for a member of the public. This simplified model was deemed to be sufficiently
conservative to be part of the Euratom-BSS [1] since most dwellings or buildings will not be designed to
be as massive as the 'bunker' (hypothetical room) described above.
In the Euratom-BSS [1], for building materials identified by the Member States as being of concern, it is
226 232 40
required that the activity concentrations of Ra, Th and K be determined (Euratom-BSS article 75
and its annex VIII, [1]). The index can then be used as a screening tool to allow building material to be
placed onto the EU market without any restrictions. National regulators and/or building codes may use
this index to identify building materials which need no further analysis with respect to emitted gamma
radiation.
Although this screening tool should be sufficient for most building materials, it remains much too
conservative for thin materials such as tiles, for light density products or for materials used in marginal
quantities. The Euratom-BSS [1] allows density, thickness and use of materials to be taken into account
in an appropriate dose modelling approach if need be.
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3.2 Provisions on the marketing of construction products
The CPR [7] regulates the placing on the market of construction products. It establishes, in its Chapters
II, III and IV, the requirements and obligations that have to be fulfilled where a construction product is
covered by a harmonised technical specification (i.e. a harmonised standard or a European Technical
Assessment). Generally for such products, a 'declaration of performance', which includes health and
safety aspects (CPR Recitals 15 and 16) has to be drawn up, and this permits the affixing of the CE
...