RADIATION FROM MASON

MEASUREMENT AND ASSE

1 Technical Director Association of the German Brick and Tile Industry, 53113 Bonn,

The radiation emanating from standard building materials is extremely low compared to the annual dose of radiation to which the German population is usually exposed. The average radon-222 concentration in room abuildings, a design level, corresponding to an averageis currently recommended. In future, this value is to be assured with appropriate measures in building design. Building materials only contribute to the radon concentration in indoor air with radon exhalation that is generally lower than 10 increased radon concentrations in buildings, the determining factor tends to be the effect of building materials rather than these themselves as a source of natural radiation. The radioactivity of building materials is generally evaluated in the different member states on the basis of a recommendation of the European Commission, issued in 1999. The Basic Safety Standards Directive (BSS) published in September 2011 as a Commission proposal that takes up the evaluation concept on the basis of the calculation of an activity concentration index I. If the information, e.g. in connection with CE marking, an adjustment of the “dose modelling” to product properties such as density and component thickness is necessary. KEYWORDS: radon exhalation, gamma radiation,spectrometry. INTRODUCTION The mean effective annual dose of the German populaThe occupation of housing units accounts for around 1.3 this annual dose, amounting to 1.2 indoor air. Considered alongside this inhalation dose, direct gamma radiatioproducts at 0.1 mSv/a only plays a minor role. That means radioactivity frproducts is primarily an indoorproducts that are in contact with the indoor air. The possible use of byindustrial processes1 which are not usually a constituent of standard and factory production in handling such materials are not the subject of consideration in this paper.

1 The residues are listed in Annex XII Part A of StrlSchV [5].

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

RADIATION FROM MASONRY PRODUCTS MEASUREMENT AND ASSESSMENT

Dieter Rosen1

Technical Director Association of the German Brick and Tile Industry, 53113 Bonn, rosen@ziegel.de

The radiation emanating from standard building materials is extremely low compared to the annual dose of radiation to which the German population is usually exposed. The average

n room air measures around 50 Bq/m! in Germany. For new buildings, a design level, corresponding to an average radon gas concentration of 200 is currently recommended. In future, this value is to be assured with appropriate measures in

n. Building materials only contribute to the radon concentration in indoor air that is generally lower than 10 Bq/m!. For this reason, in the case of

increased radon concentrations in buildings, the determining factor tends to be the effect of building materials rather than these themselves as a source of natural radiation.

The radioactivity of building materials is generally evaluated in the different member states on the basis of a recommendation of the European Commission, the Radiation Protection 112issued in 1999. The Basic Safety Standards Directive (BSS) published in September 2011 as a

takes up the evaluation concept on the basis of the calculation of an activity concentration index I. If the index evaluation is also to be used in consumer information, e.g. in connection with CE marking, an adjustment of the “dose modelling” to product properties such as density and component thickness is necessary.

radon exhalation, gamma radiation, activity concentration index

The mean effective annual dose of the German population amounts to approximately 4 g units accounts for around 1.3 mSv of this dose. The main part of

unting to 1.2 mSv per year, is the result of the inhalation of radon from indoor air. Considered alongside this inhalation dose, direct gamma radiatio

mSv/a only plays a minor role. That means radioactivity frproducts is primarily an indoor-related issue and therefore only relevant for such building products that are in contact with the indoor air. The possible use of by

which are not usually a constituent of the raw material composition of standard and factory production controlled building products and occupational safety aspects in handling such materials are not the subject of consideration in this paper.

The residues are listed in Annex XII Part A of StrlSchV [5].

RY PRODUCTS –

rosen@ziegel.de

The radiation emanating from standard building materials is extremely low compared to the annual dose of radiation to which the German population is usually exposed. The average

Bq/m! in Germany. For new radon gas concentration of 200 Bq/m!

is currently recommended. In future, this value is to be assured with appropriate measures in n. Building materials only contribute to the radon concentration in indoor air

Bq/m!. For this reason, in the case of increased radon concentrations in buildings, the determining factor tends to be the sealing effect of building materials rather than these themselves as a source of natural radiation.

The radioactivity of building materials is generally evaluated in the different member states the Radiation Protection 112,

issued in 1999. The Basic Safety Standards Directive (BSS) published in September 2011 as a takes up the evaluation concept on the basis of the calculation of an

index evaluation is also to be used in consumer information, e.g. in connection with CE marking, an adjustment of the “dose modelling” to

activity concentration index, gamma ray

tion amounts to approximately 4 mSv. mSv of this dose. The main part of

mSv per year, is the result of the inhalation of radon from indoor air. Considered alongside this inhalation dose, direct gamma radiation from building

mSv/a only plays a minor role. That means radioactivity from the building related issue and therefore only relevant for such building

products that are in contact with the indoor air. The possible use of by-products from the raw material composition of

building products and occupational safety aspects in handling such materials are not the subject of consideration in this paper.

The mean cause of increased radon concentrations inthe ground via damaged areas, insufficient sealing and cracks in the components in contact with the ground. The radon concentrations in housing units vary depending on the local geological conditions in the range of Bq/m3 and, in extreme cases, may reach several 10 000 contribute – if only to a limited extent average indoor concentration of rado

Figure 1: Mean annual radiation exposure of the population in Germany from [4] This radon concentration is made up of the radon ingress from the ground and the radon released by the building material. The typical contribution of building materials to the indoor radon concentration is generally less than 10 building materials in the case of increased radon concentrations in buildings, the determiningfactor tends to be sealing effect of the building materials than the building materials themselves as the source of natural radiation. LEGAL FRAMEWORK CONSTRUCTION PRODUCTS DIRECTIVEBack in 1989, with the adoption of the European Construction Products against emissions of dangerous radiation“Hygiene, health and the environment” in Annex I, under Item 3. As a consequence, the European Commission issued via the European Committee for Stanstandardization mandate to the Technical Committee CEN/TC351 “Assessment of release of dangerous substances”. With the set“Radioactivity”, the organizational basis was formed for drafting testindetermination of natural radioactivity from building materials. In the time frame to 2013, in Task Group 31 a technical specification for a test method for the “determination of activity concentrations of Ra-226, Thup. A second Task Group 32 has been assigned to draw up proposals for a modification of the dose assessment on the basis of the “activity concentrations index” according to RP 112 [2].

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

The mean cause of increased radon concentrations in buildings is the ingress of radon from the ground via damaged areas, insufficient sealing and cracks in the components in contact with the ground. The radon concentrations in housing units vary depending on the local geological conditions in the range of a few Bq per cubic metre (Bq/m3) up to several 1

eme cases, may reach several 10 000 Bq/m3. But building materials also if only to a limited extent – to the release of radon into the indoor air. The

ration of radon-222 in Germany is around 50 Bq/m! [11].

Figure 1: Mean annual radiation exposure of the population in Germany from [4]

This radon concentration is made up of the radon ingress from the ground and the radon material. The typical contribution of building materials to the indoor

ation is generally less than 10 Bq/m!. For this reason, in the evaluation of building materials in the case of increased radon concentrations in buildings, the determiningfactor tends to be sealing effect of the building materials than the building materials themselves as the source of natural radiation.

CONSTRUCTION PRODUCTS DIRECTIVE Back in 1989, with the adoption of the European Construction Products Directive, protection

of dangerous radiation is addressed as an essential requirement for “Hygiene, health and the environment” in Annex I, under Item 3. As a consequence, the European Commission issued via the European Committee for Standardization (CEN) a standardization mandate to the Technical Committee CEN/TC351 “Assessment of release of dangerous substances”. With the set-up of the working group CEN/TC351/WG3 on “Radioactivity”, the organizational basis was formed for drafting testing standards for the determination of natural radioactivity from building materials. In the time frame to 2013, in Task Group 31 a technical specification for a test method for the “determination of activity

226, Th-232 and K-40 using gamma/ray spectrometry” is to be drawn up. A second Task Group 32 has been assigned to draw up proposals for a modification of the dose assessment on the basis of the “activity concentrations index” according to RP 112 [2].

buildings is the ingress of radon from

the ground via damaged areas, insufficient sealing and cracks in the components in contact with the ground. The radon concentrations in housing units vary depending on the local

) up to several 1 000 lding materials also

to the release of radon into the indoor air. The Bq/m! [11].

Figure 1: Mean annual radiation exposure of the population in Germany from [4]

This radon concentration is made up of the radon ingress from the ground and the radon material. The typical contribution of building materials to the indoor

Bq/m!. For this reason, in the evaluation of building materials in the case of increased radon concentrations in buildings, the determining factor tends to be sealing effect of the building materials than the building materials

Directive, protection is addressed as an essential requirement for

“Hygiene, health and the environment” in Annex I, under Item 3. As a consequence, the dardization (CEN) a

standardization mandate to the Technical Committee CEN/TC351 “Assessment of release of up of the working group CEN/TC351/WG3 on

g standards for the determination of natural radioactivity from building materials. In the time frame to 2013, in Task Group 31 a technical specification for a test method for the “determination of activity

amma/ray spectrometry” is to be drawn up. A second Task Group 32 has been assigned to draw up proposals for a modification of the dose assessment on the basis of the “activity concentrations index” according to RP 112 [2].

BASIC SAFETY STANDARAt the end of September 2011, the EU Commission published the proposal of the ArticleGroup to reformulate the EURATOM basic safety standards in radiation protection for consultation in the EU council working group. A key addition to the Basic SaDirective (BSS) [1] is the consideration of other sources of natural radioactivity, namely from building materials amongst other things, and the evaluation of indoor radon exposure in housing and commercial construction. The radioactivity inthe basis of the knowledge level in the Radiation Protection RP 112 published in 1999 [2]. In accordance with the concept of RP 112 (1999), a screening tool is used to identify appropriate materials for exemption or rele REQUIREMENTS FOR THE MAXIMUM RADON CONCENTRATION IN THE INDOOR AIR Article 74 (3) of the Basic Safety Standards Directive explicitly calls for building codes prevent radon ingress from the soil andFor new buildings, a reference level for indoor annual average) is stipulated. This design limit is to assure that appropriate constructional measures (for example, pipe penetration seals) are implemented to ensure that the annual average is not exceeded. For housing and public buildings, the member states are called upon to establish a national reference level for indoor radon concentrationsnational action plant in accordance with Article 103. For exiBq/m3 is proposed. REQUIREMENTS FOR THE MAXIMUM RADIONUBUILDING MATERIALS For building materials, it is stated in Article 75 (2) that the indusradionuclide concentration of the building materials in accordance with an index evaluation in Annex VII and provides information to the competent authority on the results of measurements. According to Article 75 (4), building materials of which it can be assumed that they do not exceed the annual reference level for the external indoor rradiation) of 1 mSv/a (Category A products in accordance with Annex VII), exempted from requirements at national level and crestriction. For building materials which are liable to give doses exceeding the reference level of 1 mSv per year for indoor external exposure competent authority shall decide on appropriate measures.registration of the building materials, through special regulations for their use to on the use of these building materials. The dose regulated in Annex VII is based on the European recommendation “Radiation Protection 112 SURVEY MEASUREMENTS ON BUILDING MATERIALSIn 2007 Germany’s Federal Office for Radiation Protection (Bwith the German Building Materials Association (bbs) arranged for survey measurements to be conducted on building materials [8], [9]. The around 120 building material samples were selected and sourced thanks to the coordinationconcrete/prefabricated concrete elements, gypsum, sandlightweight concrete, mineral wool, mortar/plasters/screeds, aerated concrete, cement and clay bricks. The natural stone industry had arranged for these tes

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

BASIC SAFETY STANDARDS DIRECTIVE (BSS) At the end of September 2011, the EU Commission published the proposal of the ArticleGroup to reformulate the EURATOM basic safety standards in radiation protection for consultation in the EU council working group. A key addition to the Basic Sa

is the consideration of other sources of natural radioactivity, namely from building materials amongst other things, and the evaluation of indoor radon exposure in housing and commercial construction. The radioactivity in building materials is evaluated on the basis of the knowledge level in the Radiation Protection RP 112 published in 1999 [2]. In accordance with the concept of RP 112 (1999), a screening tool is used to identify appropriate materials for exemption or relevant materials for special investigation.

REQUIREMENTS FOR THE MAXIMUM RADON CONCENTRATION IN THE

Article 74 (3) of the Basic Safety Standards Directive explicitly calls for building codes prevent radon ingress from the soil and also against radon exhalation from building materials.

s, a reference level for indoor air radon concentrations of 200 annual average) is stipulated. This design limit is to assure that appropriate constructional

e penetration seals) are implemented to ensure that the annual average is not exceeded. For housing and public buildings, the member states are called upon

establish a national reference level for indoor radon concentrations in conjunction with the onal action plant in accordance with Article 103. For existing dwellings, a limit of 300

REQUIREMENTS FOR THE MAXIMUM RADIONUCLIDE CONCENTRATION OF

For building materials, it is stated in Article 75 (2) that the industry has to radionuclide concentration of the building materials in accordance with an index evaluation in

information to the competent authority on the results of measurements. According to Article 75 (4), building materials of which it can be assumed that

annual reference level for the external indoor rSv/a (Category A products in accordance with Annex VII),

requirements at national level and can be traded on the EU market without any materials which are liable to give doses exceeding the reference level

f 1 mSv per year for indoor external exposure (Category B Products after VII), competent authority shall decide on appropriate measures. These can range from national registration of the building materials, through special regulations for their use to on the use of these building materials. The dose regulated in Annex VII is based on the European recommendation “Radiation Protection 112".

SURVEY MEASUREMENTS ON BUILDING MATERIALS In 2007 Germany’s Federal Office for Radiation Protection (BfS) working in collaboration with the German Building Materials Association (bbs) arranged for survey measurements to be conducted on building materials [8], [9]. The around 120 building material samples were selected and sourced thanks to the coordination of the German and industrial associations for concrete/prefabricated concrete elements, gypsum, sand-lime bricks, ceramic tiles and panels, lightweight concrete, mineral wool, mortar/plasters/screeds, aerated concrete, cement and clay

stone industry had arranged for these tests to be conducted back in 2005

At the end of September 2011, the EU Commission published the proposal of the Article-31-Group to reformulate the EURATOM basic safety standards in radiation protection for consultation in the EU council working group. A key addition to the Basic Safety Standards

is the consideration of other sources of natural radioactivity, namely from building materials amongst other things, and the evaluation of indoor radon exposure in

building materials is evaluated on the basis of the knowledge level in the Radiation Protection RP 112 published in 1999 [2]. In accordance with the concept of RP 112 (1999), a screening tool is used to identify appropriate

REQUIREMENTS FOR THE MAXIMUM RADON CONCENTRATION IN THE

Article 74 (3) of the Basic Safety Standards Directive explicitly calls for building codes to radon exhalation from building materials.

air radon concentrations of 200 Bq/m3 (as an annual average) is stipulated. This design limit is to assure that appropriate constructional

e penetration seals) are implemented to ensure that the annual average is not exceeded. For housing and public buildings, the member states are called upon

in conjunction with the sting dwellings, a limit of 300

LIDE CONCENTRATION OF

try has to determine the radionuclide concentration of the building materials in accordance with an index evaluation in

information to the competent authority on the results of measurements. According to Article 75 (4), building materials of which it can be assumed that

annual reference level for the external indoor radiation (gamma Sv/a (Category A products in accordance with Annex VII), shall be

an be traded on the EU market without any materials which are liable to give doses exceeding the reference level

(Category B Products after VII), the These can range from national

registration of the building materials, through special regulations for their use to restrictions on the use of these building materials. The dose regulated in Annex VII is based on the

fS) working in collaboration with the German Building Materials Association (bbs) arranged for survey measurements to be conducted on building materials [8], [9]. The around 120 building material samples were

of the German and industrial associations for lime bricks, ceramic tiles and panels,

lightweight concrete, mineral wool, mortar/plasters/screeds, aerated concrete, cement and clay ts to be conducted back in 2005 /

2006 [12]. Only products in contact with the indoor air were tested. In this connection, two exposure routes must be taken into consideration, namely the irradiation of the human bofrom the outside by gamma radiation formed during the decay of the relevant radium-226, thorium-232 and potassiumresulting from internal radiation exposure of the respiratory organs by alinhalation of radon gas and its progeny. GAMMA MEASUREMENTSThe measurement was conducted as a gammaconcentrations of the natural radionuclides radiumactivity concentration of the nuclides was calculated by means of calibration of the analysis instruments with standard preparations. Prior to analysis, the samples were stored in gastight containers for at least 23 days until the radiumits short-lived secondary nuclides [4]. Many products exhibit very low values of below 50 activities. The value 50 Bq/kg represents the average radioactivity of these radionuclides in soils in Germany. For the other materials, specific activities for Rarange of 50 Bq/kg to a maximum 135 Bq/kg were determined. For clay and the ceramic products made from this (clay bricks, tiles), a higher Kmaximum 1700 Bq/kg was determined. From the radionuclide Kto the radon in the indoor air. A listing of the specific activities in building materials from the current results of the survey mea Table 1: Specific activities in building materials

Products Number

of samples

Gypsum products 5

Sand-lime bricks 3

Mineral wool 7

Clay bricks 19

Cement/mortar 11

Tiles/panels 5

Clay 15

Aerated concrete 10

Mortar 7

Plasters 19

Screeds 5 Lightweight concrete 7

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Florianópolis – Brazil – 2012

2006 [12]. Only products in contact with the indoor air were tested. In this connection, two exposure routes must be taken into consideration, namely the irradiation of the human bofrom the outside by gamma radiation formed during the decay of the relevant

232 and potassium-40, and the biologically more effective exposure, resulting from internal radiation exposure of the respiratory organs by alinhalation of radon gas and its progeny.

GAMMA MEASUREMENTS The measurement was conducted as a gamma-spectrometric determination of the activity concentrations of the natural radionuclides radium-226, thorium-232 and potassiumactivity concentration of the nuclides was calculated by means of calibration of the analysis instruments with standard preparations. Prior to analysis, the samples were stored in gastight containers for at least 23 days until the radium-226 was in equilibrium with the radon

lived secondary nuclides [4].

bit very low values of below 50 Bq/kg for Ra-226 and ThBq/kg represents the average radioactivity of these radionuclides in

in Germany. For the other materials, specific activities for Ra-226 and Thrange of 50 Bq/kg to a maximum 135 Bq/kg were determined. For clay and the ceramic products made from this (clay bricks, tiles), a higher K-40 activity above 400 Bq/kg tomaximum 1700 Bq/kg was determined. From the radionuclide K-40, no contribution is made to the radon in the indoor air. A listing of the specific activities in building materials from the current results of the survey measurements [8] is given in Table 1.

ctivities in building materials – summarized from [8]

Specific activity [Bq/kg]

Ra-226 Th-228

Min. Max. Mean Min. Max. Mean

3.8 13 8.6 1,6 5,8 3,3 < 20

4,1 10 8 2.8 7,2 6,3

16 80 35 4,7 64 22

38 63 48 37 89 56

11 35 22 11 21 15

67 110 88 39 97 62

15 115 46 20 135 54

8 26 18 4,8 19 12

11 53 27 6 31 19

2 22 7,7 0,9 31 6

11 26 15 11 34 17

27 98 62 28 83 49

2006 [12]. Only products in contact with the indoor air were tested. In this connection, two exposure routes must be taken into consideration, namely the irradiation of the human body from the outside by gamma radiation formed during the decay of the relevant radionuclides,

40, and the biologically more effective exposure, resulting from internal radiation exposure of the respiratory organs by alpha radiation, i.e.

spectrometric determination of the activity 232 and potassium-40. The

activity concentration of the nuclides was calculated by means of calibration of the analysis instruments with standard preparations. Prior to analysis, the samples were stored in gastight

rium with the radon-222 and

226 and Th-232 specific Bq/kg represents the average radioactivity of these radionuclides in

226 and Th-232 in the range of 50 Bq/kg to a maximum 135 Bq/kg were determined. For clay and the ceramic

40 activity above 400 Bq/kg to a 40, no contribution is made

to the radon in the indoor air. A listing of the specific activities in building materials from the

summarized from [8]

K-40

Min. Max. Mean

< 20 120 51

35 180 115

49 350 155

470 1200 716

135 380 230

295 620 429

65 1700 664

97 350 193

120 310 226

12 220 75

210 295 213

710 850 845

While in the literature on clay bricks/clinkers, a radionucliBq/kg as a mean value (value range 10 conducted by the BfS resulted in a meanThe production sites for sampling were selected at sites with known high geogenic radon activity concentration in the ground air. DETERMINATION OF THEAnother objective of the study was the determination of the materialthe indoor concentration of radonand its short-lived decay products (alpha radiation) is the second exposure route of the radioactivity from building materials. In contrast to thecontent, up to now no standardized measurement method exists for determining the radon exhalation. The surface radon exhalation rates of the radondetermined directly on the brick under an (brick chippings) based on determination of the emanation coefficient. The analyser developed at the University of Homburg by Professor Gerd Keller for determining radon exhalation consists of an aluminium hemplaced on top of the sample. See figure 2

Figure 2: Test bench for determining the radon exhalation rate with the radon analyzer The perforations in the clay brick are also sealed. The exhalation rates for the radon-220 are measured based on electrostatic deposition of the positive polonium 218 and polonium-216 ions formed during transformation of the radon onto the detector surface with subsequent alpha spectrometry. The increase in the radon concvolume is registered over several measurement cycles and evaluated [4].materials that have perforations, cavities, glazed or sintered surfaces or similar, the applied conversion can lead to possible inaccuracies. material is described with the exhalation rate in mBqbuilding materials, clay bricks exhibit the lowest values for radon release. A comparison of the radon release of different wall materials is shown in Table 2.

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

While in the literature on clay bricks/clinkers, a radionuclide content for radiumBq/kg as a mean value (value range 10 - 200) was reported, the survey measurements conducted by the BfS resulted in a mean value of 48 Bq/kg and a value range 38 The production sites for sampling were selected at sites with known high geogenic radon activity concentration in the ground air.

DETERMINATION OF THE RADON EXHALATION Another objective of the study was the determination of the material-relatedthe indoor concentration of radon-222. The inhalation of the radioactive inert gas Radon

lived decay products (alpha radiation) is the second exposure route of the radioactivity from building materials. In contrast to the determination of the radionuclide content, up to now no standardized measurement method exists for determining the radon exhalation. The surface radon exhalation rates of the radon-222 and radondetermined directly on the brick under an aluminium hemisphere or on material particles (brick chippings) based on determination of the emanation coefficient.

The analyser developed at the University of Homburg by Professor Gerd Keller for determining radon exhalation consists of an aluminium hemisphere with sealing lips which is

. See figure 2.

: Test bench for determining the radon exhalation rate with the radon analyzer

The perforations in the clay brick are also sealed. The exhalation rates for the 220 are measured based on electrostatic deposition of the positive polonium 218 and

216 ions formed during transformation of the radon onto the detector surface with subsequent alpha spectrometry. The increase in the radon concentration in the measurement volume is registered over several measurement cycles and evaluated [4].materials that have perforations, cavities, glazed or sintered surfaces or similar, the applied conversion can lead to possible inaccuracies. The release of the radon from the building material is described with the exhalation rate in mBq/m-2 s-1. In direct comparison with other building materials, clay bricks exhibit the lowest values for radon release. A comparison of

erent wall materials is shown in Table 2.

de content for radium-226 of 60

200) was reported, the survey measurements value of 48 Bq/kg and a value range 38 – 63 Bq/kg.

The production sites for sampling were selected at sites with known high geogenic radon

related contribution to 222. The inhalation of the radioactive inert gas Radon-222

lived decay products (alpha radiation) is the second exposure route of the determination of the radionuclide

content, up to now no standardized measurement method exists for determining the radon 222 and radon-220 can either be

aluminium hemisphere or on material particles

The analyser developed at the University of Homburg by Professor Gerd Keller for isphere with sealing lips which is

: Test bench for determining the radon exhalation rate with the radon analyzer

The perforations in the clay brick are also sealed. The exhalation rates for the radon-222 and 220 are measured based on electrostatic deposition of the positive polonium 218 and

216 ions formed during transformation of the radon onto the detector surface with entration in the measurement

volume is registered over several measurement cycles and evaluated [4]. For building materials that have perforations, cavities, glazed or sintered surfaces or similar, the applied

The release of the radon from the building . In direct comparison with other

building materials, clay bricks exhibit the lowest values for radon release. A comparison of

Table 2: Comparison of the radon released by different wall building materials from [4]

Building materials Building material

Wall

thickness d

(cm)

Sand-lime bricks 17,5Clay bricks 36,5Lightweight concrete 36,5

Concrete 15,0Aerated concrete 36.5 ASSESSMENT OF THE NATURAL RADIATION OF BUILDING MATERIALSIn 1999 the European Commission published a guidance document "Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials (Radiation Protection 112)” on the basis of a study providing information about natural radioactivity in building [2]. Here, too, the starting point is a design level recommended by the EU Commission corresponding to an annual average radon gas concentwhether a building material meets this limit value is also made here not by measuring the radon exhalation, but indirectly via the activity concentration index (I). If the activity concentration index according to the summation formula (1) remains below 1the maximum additional radiation dose of approx 1 mSv/a for building materials, defined as the “excess to typical outdoor exposure”, is assumed. The threshold dose is based on the model room assumptions for a concrete wall/floor with a thickness of 0.20 m and a density of 2350 kg/m! according to RP 112. The activity concentration index (I), has to be calculated where potassium activity concentrations (Bq/kg) in the building material. Where the value of the index exceeds 1 for materials used in bulk amounts, or 6 for superficial and other materials with restricted use, the actual doses for comparison with the reference level shall need to be assessed. It should be emphasized that the activity concentration index should be used only as a screening tool and only for the purpose of identifying materials which might be of concern. Any actual decision on restricting the use oa material will need a separate dose assessment to confirm that the reference level (in terms of dose) is exceeded.

2001300 !

+"

!!

=

Bq

C

kgBq

RaC

I

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

Table 2: Comparison of the radon released by different wall building materials from [4]

Building material sizes

Measured values

Wall thickness

Density (gross) 226Ra-Conc. Emanation

capacity

(cm) (kg/dm3) Bq/kg (%)

17,5 1,8 9 28,0 36,5 0,7 35 0,7

36,5 0.7 49 4,6

15,0 2,35 52 3,6 36.5 0,4 19 24,0

ASSESSMENT OF THE NATURAL RADIATION OF BUILDING MATERIALSIn 1999 the European Commission published a guidance document "Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials (Radiation Protection

the basis of a study providing information about natural radioactivity in building [2]. Here, too, the starting point is a design level recommended by the EU Commission corresponding to an annual average radon gas concentration of 200 Bq/mwhether a building material meets this limit value is also made here not by measuring the radon exhalation, but indirectly via the activity concentration index (I). If the activity concentration index according to the summation formula (1) remains below 1the maximum additional radiation dose of approx 1 mSv/a for building materials, defined as the “excess to typical outdoor exposure”, is assumed.

The threshold dose is based on the model room assumptions for a concrete wall/floor with a m and a density of 2350 kg/m! according to RP 112. The activity

concentration index (I), has to be calculated where CRa, CTh, CK are the radium, thorium and potassium activity concentrations (Bq/kg) in the building material.

Where the value of the index exceeds 1 for materials used in bulk amounts, or 6 for superficial and other materials with restricted use, the actual doses for comparison with the

level shall need to be assessed. It should be emphasized that the activity concentration index should be used only as a screening tool and only for the purpose of identifying materials which might be of concern. Any actual decision on restricting the use oa material will need a separate dose assessment to confirm that the reference level (in terms of

130001 "!!

+"

! kgBq

KC

kgBq

ThC

Table 2: Comparison of the radon released by different wall building materials from [4]

Calculated

values

Emanation Radon concentration

(Bq/m3)

8,57 0,68

6,22

7,13 7,19

ASSESSMENT OF THE NATURAL RADIATION OF BUILDING MATERIALS In 1999 the European Commission published a guidance document "Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials (Radiation Protection

the basis of a study providing information about natural radioactivity in building [2]. Here, too, the starting point is a design level recommended by the EU Commission

Bq/m3. The assessment whether a building material meets this limit value is also made here not by measuring the radon exhalation, but indirectly via the activity concentration index (I). If the activity concentration index according to the summation formula (1) remains below 1, observation of the maximum additional radiation dose of approx 1 mSv/a for building materials, defined as

The threshold dose is based on the model room assumptions for a concrete wall/floor with a m and a density of 2350 kg/m! according to RP 112. The activity

are the radium, thorium and

(1)

Where the value of the index exceeds 1 for materials used in bulk amounts, or 6 for superficial and other materials with restricted use, the actual doses for comparison with the

level shall need to be assessed. It should be emphasized that the activity concentration index should be used only as a screening tool and only for the purpose of identifying materials which might be of concern. Any actual decision on restricting the use of a material will need a separate dose assessment to confirm that the reference level (in terms of

Table 3: Average and maximum values of wall materials [8]

Wall materials

Wall bulk material

Clay masonry units (mean)

Clay masonry units (max.)

Calcium silicate units (mean)

Calcium silicate units (max.)

Aerated concrete (mean)

Aerated concrete (max.)

Concrete (mean)

Concrete (max.)

Lightweight concrete (mean)

Lightweight concrete (max.)

NATIONAL REQUIREMENTS IN THE EU MEMBER STATESSeveral EU MS regulations have adopted the approach of the activity such or with slight modifications.

CZECH REPUBLIC The requirements for manufacturers and importers to provide systematic measurements and evaluation of natural radionuclides concentrations are specified in Section 6 (6) of the AtomiAct No. 18/1997 Coll. 2 A three-step approach is taken in the assessment of construction products in Regulations on Radiation Protection in the Czech Republicmaterials are listed in Annex 10, Table 1.habitable rooms (independent of whether the product is in contact with indoor air or not) the limiting mass activities should not exceed 150 materials exceed the limitations on natural radionuclide concentrations, their sale and distribution are prohibited. The guidance levels for the natural radionuclide content of building materials are determined based on the mass activity indices I.

2) Atomic Act on Peaceful Utilisation of Nuclear Energy and Ionising Radiation (the and on Amendments and Alterations to SomeNo. 18/1997 Col 3) The ‘Draft regulation of 2005 (2005-452June 2002 on Radiation Protection. 4) The mass activity index I is determined by the formula I = aK/3000 Bq kgRegulations of the State Office for Nuclear Safety No 307/2002 C

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

Table 3: Average and maximum values of wall materials [8]

1 2 3 4 5

Bq/kg 1 mSv/a

Measurements (BfS) Assessment RP

Ra-226 Th-232 K40 Ra /300 Th/200

48 57 719 0.16 0.29

63 89 1200 0.21 0.45

Calcium silicate units (mean) 8 6 115 0.03 0.03

Calcium silicate units (max.) 10 7 180 0.03 0.04

18 12 193 0.06 0.06

26 19 350 0.09 0.10

22 15 230 0.07 0.08

35 21 380 0.12 0.11

Lightweight concrete (mean) 62 49 845 0.21 0.25

Lightweight concrete (max.) 98 83 850 0.33 0.42

NATIONAL REQUIREMENTS IN THE EU MEMBER STATES Several EU MS regulations have adopted the approach of the activity concentration index as such or with slight modifications.

The requirements for manufacturers and importers to provide systematic measurements and evaluation of natural radionuclides concentrations are specified in Section 6 (6) of the Atomi

step approach is taken in the assessment of construction products in Regulations on Radiation Protection in the Czech Republic3. First the values for the mass activity of building materials are listed in Annex 10, Table 1. For building materials for use in buildings with habitable rooms (independent of whether the product is in contact with indoor air or not) the

ctivities should not exceed 150 Bq/kg Ra-226 mass activity. If the building limitations on natural radionuclide concentrations, their sale and

distribution are prohibited. The guidance levels for the natural radionuclide content of building materials are determined based on the mass activity indices I.4

) Atomic Act on Peaceful Utilisation of Nuclear Energy and Ionising Radiation (the and on Amendments and Alterations to Some

452-CZ) amends the Regulations of the State Office for Nuclear Saf

) The mass activity index I is determined by the formula I = aK/3000 Bq kg-1 + aRa/300 Bq kg-1+ aTh/200 Bq kgRegulations of the State Office for Nuclear Safety No 307/2002 Coll. of 13 June 2002 in section 3, letter h)”

6 7

1 mSv/a

Assessment RP 112/ BSS

Th/200 K/3000 Index

0.29 0.24 0.68

0.45 0.40 1.06

0.03 0.04 0.10

0.04 0.06 0.13

0.06 0.06 0.18

0.10 0.12 0.30

0.08 0.08 0.23

0.11 0.13 0.35

0.25 0.28 0.73

0.42 0.28 1.03

concentration index as

The requirements for manufacturers and importers to provide systematic measurements and evaluation of natural radionuclides concentrations are specified in Section 6 (6) of the Atomic

step approach is taken in the assessment of construction products in Regulations on . First the values for the mass activity of building For building materials for use in buildings with

habitable rooms (independent of whether the product is in contact with indoor air or not) the 226 mass activity. If the building

limitations on natural radionuclide concentrations, their sale and distribution are prohibited. The guidance levels for the natural radionuclide content of

) Atomic Act on Peaceful Utilisation of Nuclear Energy and Ionising Radiation (the and on Amendments and Alterations to Some Acts,

CZ) amends the Regulations of the State Office for Nuclear Safety No 307/2002 Coll. of 13

1+ aTh/200 Bq kg-1 defined in the

The limiting levels for the natural radionuclide contents of building materials are listed in Annex 10, Table 2. The massintended for walls, ceilings and floors in buildings with habitable rooms (in particular masonry elements, prefabricated products, blocks, bricks, concrete and plasterbvalues of Index I = 0.5 are exceeded, then the distribution of the building materials, if these are intended for direct embedding into buildings, is only permitted in justificase an extended assessment based on the optimization study "radiaSÚJB (2009) is possible5. According to Table concentration, the gross density and thickness of the mconsideration. AUSTRIA In Austria the assessment of the radioactivity of building materials is founded in the Ordinance on Hazards from Naturally Occurring Radioactive Materials, Federal Ministry of Agriculture and Forestry, Environment and Water Management, January §20, Para. 7, for the reuse of residues in housing construction, it is necessary to comply with a two-stage process in accordance with the provisions in Annex 3. For the use of residues in the manufacture of building materials, it can be assumed thfor protection of the population if the following criterion been fulfilled: The activity concentrations of Ragamma spectrometry. If Criterion 1 is not fulfilled and providing specific application parameters for the use of the residue in building materials are known, the second test stage is to be applied: here the procedure specified in ÖNORM S5200 [10] should be used in preference.

where: ai = activity concentration of natural radio nuclides, in Bq/kg = emanating capacity, as measured but no more than 0.1 = density, in kg/m!, as measured but no more that 2000 kg/m!d = thickness, in m, as measured but no more that 0.3 m In annotations to Annex 3, 2.2 building materials. This dose limit is the sum of thethe accepted exposure owing to excess radioactivity

5) The Guide of State Office for Nuclear Safety in Czech Republic is named “Mereni a hodnoceni obsahu prirodnich radionuklidù stavebnich materialech“ edited by SÚJB (2009)

6) Ordinance issued by Austria’s Federal Ministry of Agriculture, Forestry, Environment and Water concerning radiation protection with regard to natural terrestrial sources of radiation (Ordinance on Sources of Natural Radiation

240232

40

40226 "+"

" Raa

Raa

,01(880

2268800

40 +!"+" Raa

Ka

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

e natural radionuclide contents of building materials are listed in Table 2. The mass activity index is limited to I = 0.5 for building materials

intended for walls, ceilings and floors in buildings with habitable rooms (in particular ments, prefabricated products, blocks, bricks, concrete and plasterb

= 0.5 are exceeded, then the distribution of the building materials, if these are intended for direct embedding into buildings, is only permitted in justificase an extended assessment based on the optimization study "radianí ochrana" edited by

. According to Table 6 for determination of the share of radionuclide concentration, the gross density and thickness of the materials must be taken into

In Austria the assessment of the radioactivity of building materials is founded in the Ordinance on Hazards from Naturally Occurring Radioactive Materials, Federal Ministry of Agriculture and Forestry, Environment and Water Management, January 2008

20, Para. 7, for the reuse of residues in housing construction, it is necessary to comply with a stage process in accordance with the provisions in Annex 3. For the use of residues in the

manufacture of building materials, it can be assumed that sufficient provision has been made for protection of the population if the following criterion according to the formula (2)

The activity concentrations of Ra-226 and K-40 can be expediently determined by means of gamma spectrometry. If Criterion 1 is not fulfilled and providing specific application parameters for the use of the residue in building materials are known, the second test stage is

e procedure specified in ÖNORM S5200 [10] should be used in

= activity concentration of natural radio nuclides, in Bq/kg = emanating capacity, as measured but no more than 0.1 = density, in kg/m!, as measured but no more that 2000 kg/m!

in m, as measured but no more that 0.3 m.

In annotations to Annex 3, 2.2 mSv/a is defined as a dose limit for application of residues for building materials. This dose limit is the sum of the average natural exposure = 1.2

owing to excess radioactivity in building materials = 1 mSv/a.

) The Guide of State Office for Nuclear Safety in Czech Republic is named “Mereni a hodnoceni obsahu prirodnich radionuklidù

stavebnich materialech“ edited by SÚJB (2009) Federal Ministry of Agriculture, Forestry, Environment and Water concerning radiation protection with

regard to natural terrestrial sources of radiation (Ordinance on Sources of Natural Radiation – NatStrV) BGBl. II

14000

37040240

25232 #"

"+"

Ka

1500

232)07, #"+!!! Tha

d$%

e natural radionuclide contents of building materials are listed in

= 0.5 for building materials intended for walls, ceilings and floors in buildings with habitable rooms (in particular

ments, prefabricated products, blocks, bricks, concrete and plasterboard). If the = 0.5 are exceeded, then the distribution of the building materials, if these

are intended for direct embedding into buildings, is only permitted in justified cases. In this ní ochrana" edited by

6 for determination of the share of radionuclide aterials must be taken into

In Austria the assessment of the radioactivity of building materials is founded in the Ordinance on Hazards from Naturally Occurring Radioactive Materials, Federal Ministry of

20086. According to 20, Para. 7, for the reuse of residues in housing construction, it is necessary to comply with a

stage process in accordance with the provisions in Annex 3. For the use of residues in the at sufficient provision has been made

according to the formula (2) has

(2)

40 can be expediently determined by means of gamma spectrometry. If Criterion 1 is not fulfilled and providing specific application parameters for the use of the residue in building materials are known, the second test stage is

e procedure specified in ÖNORM S5200 [10] should be used in

mSv/a is defined as a dose limit for application of residues for average natural exposure = 1.2 mSv/a and in building materials = 1 mSv/a.

) The Guide of State Office for Nuclear Safety in Czech Republic is named “Mereni a hodnoceni obsahu prirodnich radionuklidù ve

Federal Ministry of Agriculture, Forestry, Environment and Water concerning radiation protection with NatStrV) BGBl. II – 7 January 2008 - No. 2

(3)

Relevant is also the ÖNORM S5200:2009in addition to specifying the formula of RP concentration index I, introduces a more sophisticated formula (3) that takes into consideration the emanation factor (use.7 POLAND Relevant regulation is the regulation issued by the council of ministers (dated 2 January 2007) on the requirements concerning the content of natural radioactive isotopes of potassium Kradium Ra-226 and thorium Thto accommodate people and livestock, as well as in industrial waste used in construction industry, and the procedures for controlling the content of these Reference is made to construction products; the radionuclide Rathe activity concentration index (RP112). A simple approximation to limit the dose emanating from building materials is described. Materials for the building industry are classified on the basis of two parameters: where SK, SRa and STh denote the respective radioactive concentration of isotopes of potassium K-40, radium Ra-226 and thorium Th

Parameter f1 (4) defines the content of natural radioactive isotopes in the examined material. Parameter f2 (5) limits the content of the radium isotope Raradiation from the radon and its progeny. The first parameter is calculated on the basis of concentrations of the activities of Radesigned for people and livestock, the values fparameters should not be exceeded by more than 20 FINLAND The Radiation Act (592/91) states that radiation practices also comprise operations or circumstances in which a person's exposure to natural radiation causes or may cause a health hazard. Under § 70 (2), STUKgeneral instructions, known as Radiation Safety Guides (ST Guides)radiation and operations involving radiation. running a radiation practice is responsible for the safety of the operations. The responsible 7) Building Materials List “ÖE” (2011/281/A) Annex B 1 health and environmental protection within the meaning of essential requirement 3 of Council Directive 89/106/EEC, ÖNORM S 52(2009.04.01) on radioactivity in construction materials must in any case be complied with. If the various limit values contained 5200 (1 April 2009) or in other relevant Federal provisions are not observed, then any such use shall be banned. 8) REGULATION OF THE COUNCIL OF MINISTERS of 2 January 2007 on the requirements imposed on the content of natural radioisotopes: potassium K-40, radium Ra-226 and thorium Thaccommodation of people and livestock, and in industrial waste applied in construction, and the control of radioisotope content. Pursuant to the Art. 6 section 3 of the Atomic Energy Law of 29 November 2000 (Journal of Laws of 2004, No. 161, item 1689)

300130001

!

+"

!!

=

BqkgBq

KS

f

RaSf =2

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

Relevant is also the ÖNORM S5200:2009-04 Standard concerning building materials, which, to specifying the formula of RP 112 for the determination of an activity

concentration index I, introduces a more sophisticated formula (3) that takes into consideration the emanation factor (), the density () and the thickness (d) of the material

Relevant regulation is the regulation issued by the council of ministers (dated 2 January 2007) on the requirements concerning the content of natural radioactive isotopes of potassium K

226 and thorium Th-228 in raw materials and materials used in buildings designed to accommodate people and livestock, as well as in industrial waste used in construction industry, and the procedures for controlling the content of these isotopes.8

Reference is made to construction products; the radionuclide Ra-226, K-40 and THthe activity concentration index (RP112). A simple approximation to limit the dose emanating from building materials is described. Materials for the building industry are classified on the

denote the respective radioactive concentration of isotopes of potassium 226 and thorium Th-228 expressed in [Bq/kg]

defines the content of natural radioactive isotopes in the examined material. limits the content of the radium isotope Ra-226 owing to the risk of alpha

don and its progeny. The first parameter is calculated on the basis of concentrations of the activities of Ra-226, Th-228 and K-40. For materials used in buildings designed for people and livestock, the values f1 = 1 and f2 = 200 of the above activity

not be exceeded by more than 20 %.

The Radiation Act (592/91) states that radiation practices also comprise operations or circumstances in which a person's exposure to natural radiation causes or may cause a health

, STUK – the Radiation and Nuclear Safety Authority (Finland) issues general instructions, known as Radiation Safety Guides (ST Guides) concerning the use of radiation and operations involving radiation. The Radiation Act stipulates that the party

nning a radiation practice is responsible for the safety of the operations. The responsible

terials List “ÖE” (2011/281/A) Annex B 1 – Definitions of requirements for "hazardous substances": health and environmental protection within the meaning of essential requirement 3 of Council Directive 89/106/EEC, ÖNORM S 52

9.04.01) on radioactivity in construction materials must in any case be complied with. If the various limit values contained 5200 (1 April 2009) or in other relevant Federal provisions are not observed, then any such use shall be banned.

ULATION OF THE COUNCIL OF MINISTERS of 2 January 2007 on the requirements imposed on the content of natural 226 and thorium Th-228 in raw materials and materials applied in buildings for the

and livestock, and in industrial waste applied in construction, and the control of radioisotope content. Pursuant to Energy Law of 29 November 2000 (Journal of Laws of 2004, No. 161, item 1689)

12001 "!!

+"

! kgBq

thS

kgBq

RaS

04 Standard concerning building materials, which,

112 for the determination of an activity concentration index I, introduces a more sophisticated formula (3) that takes into

) and the thickness (d) of the material in

Relevant regulation is the regulation issued by the council of ministers (dated 2 January 2007) on the requirements concerning the content of natural radioactive isotopes of potassium K-40,

ed in buildings designed to accommodate people and livestock, as well as in industrial waste used in construction

40 and TH-228 and the activity concentration index (RP112). A simple approximation to limit the dose emanating from building materials is described. Materials for the building industry are classified on the

(4)

denote the respective radioactive concentration of isotopes of potassium

(5)

defines the content of natural radioactive isotopes in the examined material. 226 owing to the risk of alpha

don and its progeny. The first parameter is calculated on the basis of 40. For materials used in buildings

= 200 of the above activity

The Radiation Act (592/91) states that radiation practices also comprise operations or circumstances in which a person's exposure to natural radiation causes or may cause a health

the Radiation and Nuclear Safety Authority (Finland) issues oncerning the use of

The Radiation Act stipulates that the party nning a radiation practice is responsible for the safety of the operations. The responsible

ts for "hazardous substances": With respect to hygiene, health and environmental protection within the meaning of essential requirement 3 of Council Directive 89/106/EEC, ÖNORM S 5200

9.04.01) on radioactivity in construction materials must in any case be complied with. If the various limit values contained in ÖNORM S 5200 (1 April 2009) or in other relevant Federal provisions are not observed, then any such use shall be banned.

ULATION OF THE COUNCIL OF MINISTERS of 2 January 2007 on the requirements imposed on the content of natural 228 in raw materials and materials applied in buildings for the

and livestock, and in industrial waste applied in construction, and the control of radioisotope content. Pursuant to Energy Law of 29 November 2000 (Journal of Laws of 2004, No. 161, item 1689)

party is obliged to ensure that the level of safety specified in the ST Guides is attained and maintained. In the STUK Technical Guide 12.2Ra-226, K-40 and Th-232 and the activity concentration index (RP112); caesium only in the case of materials used in road, street and related construction work, materials used in landfill and landscaping and handling of ash. required to show specifically that the relevant action level is not exceeded. If the activity index is 1 or less than 1, the material can be used, so far as radioactivity is concerned, without restriction. If necessary, the radiation exposure due to the practice can be investigated casespecifically without separate examination of the activity index. SUMMARY The radiation emanating from standardized building materials is extremely low compared to the annual dose to which the German population is usually exposed. For this reason, in the case of increased radon concentrations in buildings, the determining factor tends to be the sealing effect of building materials rather than these themselves as a source of naturadiation. Precondition for this, however, is that no industrial process residues that may be considered critical with regard to radiation protection and are not usually a constituent in the raw material composition of standard building products are Accordingly, various member ststrategy – introduced legally binding national regulations to limit the radionuclide concentration in building materials. So tstates do not lead to trade barriers, for example as a result of double testing, the EU Commission has issued a standardization mandate to the CEN to undertake harmonization of the existing testing methods. The radioactivity of building materials is generally evaluated in the different member states on the basis of a recommendation of the European Commission, the Radiation Protection 112 issued in 1999. The Basic Safety Standards Directive (BSS) published Commission proposal takes up the evaluation concept on the basis of the calculation of an activity concentration index (I). If the index evaluation is also to be used in consumer information, e.g. in connection with CE marking, an adproduct properties such as density and component thickness is necessary. REFERENCES

1) Proposal for a COUNCIL DIRECTIVE laying down basic safety standards for protection against the dangers arising from exposure to ionispresented under Article 31 Euratom Treaty for the opinion of the European Economic and Social Committee; COM(2011)

2) Radiation protection 112 Radioactivity of Building MaterialsProtection, 1999

9) STUK Technical Guide 12.2 The radioactivity of building materials and ash

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

party is obliged to ensure that the level of safety specified in the ST Guides is attained and maintained. In the STUK Technical Guide 12.29, reference is made to construction products;

232 and the activity concentration index (RP112); caesium only in the materials used in road, street and related construction work, materials used in landfill

and landscaping and handling of ash. If the activity index exceeds 1, the responsible party is required to show specifically that the relevant action level is not exceeded. If the activity index is 1 or less than 1, the material can be used, so far as radioactivity is concerned, without

necessary, the radiation exposure due to the practice can be investigated casespecifically without separate examination of the activity index.

The radiation emanating from standardized building materials is extremely low compared to ose to which the German population is usually exposed. For this reason, in the

case of increased radon concentrations in buildings, the determining factor tends to be the sealing effect of building materials rather than these themselves as a source of natu

Precondition for this, however, is that no industrial process residues that may be considered critical with regard to radiation protection and are not usually a constituent in the raw material composition of standard building products are used in the manufacture of these products. Accordingly, various member states in the European Union have – in a quasi pre

introduced legally binding national regulations to limit the radionuclide concentration in building materials. So that these notified regulations of different member states do not lead to trade barriers, for example as a result of double testing, the EU Commission has issued a standardization mandate to the CEN to undertake harmonization of

The radioactivity of building materials is generally evaluated in the different member states on the basis of a recommendation of the European Commission, the Radiation Protection 112 issued in 1999. The Basic Safety Standards Directive (BSS) published in September 2011 as a Commission proposal takes up the evaluation concept on the basis of the calculation of an activity concentration index (I). If the index evaluation is also to be used in consumer information, e.g. in connection with CE marking, an adjustment of the “dose modelling” to product properties such as density and component thickness is necessary.

Proposal for a COUNCIL DIRECTIVE laying down basic safety standards for protection against the dangers arising from exposure to ionising radiation; Draft presented under Article 31 Euratom Treaty for the opinion of the European Economic and Social Committee; COM(2011) Radiation protection 112 – Radiological Protection Principles concerning the Natural Radioactivity of Building Materials, DG-Environment, Nuclear Safety and Civil

2 The radioactivity of building materials and ash

party is obliged to ensure that the level of safety specified in the ST Guides is attained and

onstruction products; 232 and the activity concentration index (RP112); caesium only in the

materials used in road, street and related construction work, materials used in landfill ivity index exceeds 1, the responsible party is

required to show specifically that the relevant action level is not exceeded. If the activity index is 1 or less than 1, the material can be used, so far as radioactivity is concerned, without

necessary, the radiation exposure due to the practice can be investigated case-

The radiation emanating from standardized building materials is extremely low compared to ose to which the German population is usually exposed. For this reason, in the

case of increased radon concentrations in buildings, the determining factor tends to be the sealing effect of building materials rather than these themselves as a source of natural

Precondition for this, however, is that no industrial process residues that may be considered critical with regard to radiation protection and are not usually a constituent in the raw material

used in the manufacture of these products. in a quasi pre-emptive

introduced legally binding national regulations to limit the radionuclide hat these notified regulations of different member

states do not lead to trade barriers, for example as a result of double testing, the EU Commission has issued a standardization mandate to the CEN to undertake harmonization of

The radioactivity of building materials is generally evaluated in the different member states on the basis of a recommendation of the European Commission, the Radiation Protection 112

in September 2011 as a Commission proposal takes up the evaluation concept on the basis of the calculation of an activity concentration index (I). If the index evaluation is also to be used in consumer

justment of the “dose modelling” to

Proposal for a COUNCIL DIRECTIVE laying down basic safety standards for ing radiation; Draft

presented under Article 31 Euratom Treaty for the opinion of the European Economic

Radiological Protection Principles concerning the Natural Environment, Nuclear Safety and Civil

3) Keller, G., Folkerts K.H. and Muth H. “Discussing possible Standards of natural

radioactivity in building materials”, Homburg/Saar, Federal Republic of Germany; 1987

4) Keller, G., Result reportthe radioactivity of building bricks

5) Ordinance on protection against ionizing radiation (radiation protection ordinance) dated 20 July 2001, BGBl. I p.1714

6) Council Directive dated 21 December 1988 on the Approximation of Regulations and Administrative ProvisionsProducts (89/106/EEC), amended by the Council Directive 93/68/EEC dated 22 July 1993

7) Act on marketing and free movement of building products to implement the Council Directive 89/106/EEC of 21 December 1988 on the approximation of acts, regulations and administrative provisions of the Member States with regard to building products dated 10 August 1992

8) Gehrcke, K., Hoffmann, B., Schkade, U., Schmidt, V., Wichterey, K. „radioactivity into building materials and the radiation exposure resulting from itGermany’s Federal Office for Radiation Protection,

9) Annual Report of the Germany’s F2009, To Which Extent are Building Materials Radioactive?

10) ÖNORM S 5200 Radioactivity in construction materials, April 2009, Austrian Standards Institute

11) Annual Report of the Germany’s Federal Office for R2005, Estimation of the annual cases of lung cancer in Germany caused by natural radon in housing, p. 83

12) Annual Report of the Germany’s Federal Office for Radiation Protection, Salzgitter; 2006 “Natural radionuclides i

13) Markkanen M., Radiation Dose Assessments for Materials with Elevated Natural Radioactivity. Report STUK

Rosen, 05.12.2011

15th International Brick and Block Masonry Conference

Florianópolis – Brazil – 2012

Keller, G., Folkerts K.H. and Muth H. “Discussing possible Standards of natural radioactivity in building materials”, Homburg/Saar, Federal Republic of Germany;

Result report Nr. KB 21/07 Examinations, assessement and statement on the radioactivity of building bricks, Homburg, 20.09.2007 Ordinance on protection against ionizing radiation (radiation protection ordinance) dated 20 July 2001, BGBl. I p.1714 Council Directive dated 21 December 1988 on the Approximation of Regulations and Administrative Provisions of the Member States relating to Building Products (89/106/EEC), amended by the Council Directive 93/68/EEC dated 22 July

and free movement of building products to implement the Council Directive 89/106/EEC of 21 December 1988 on the approximation of acts, regulations and administrative provisions of the Member States with regard to building products

rcke, K., Hoffmann, B., Schkade, U., Schmidt, V., Wichterey, K. „

radioactivity into building materials and the radiation exposure resulting from itGermany’s Federal Office for Radiation Protection, (Entwurf 2008)Annual Report of the Germany’s Federal Office for Radiation Protection, Salzgitter;

To Which Extent are Building Materials Radioactive? ÖNORM S 5200 Radioactivity in construction materials, April 2009, Austrian

Annual Report of the Germany’s Federal Office for Radiation Protection, Salzgitter; 2005, Estimation of the annual cases of lung cancer in Germany caused by natural radon in housing, p. 83 - 84 Annual Report of the Germany’s Federal Office for Radiation Protection, Salzgitter; 2006 “Natural radionuclides in ashlar products”, p. 48 – 49

Radiation Dose Assessments for Materials with Elevated Natural Radioactivity. Report STUK-B-STO 32, Radiation and Nuclear Safety Authority

Keller, G., Folkerts K.H. and Muth H. “Discussing possible Standards of natural radioactivity in building materials”, Homburg/Saar, Federal Republic of Germany;

Examinations, assessement and statement on

Ordinance on protection against ionizing radiation (radiation protection ordinance)

Council Directive dated 21 December 1988 on the Approximation of Laws, of the Member States relating to Building

Products (89/106/EEC), amended by the Council Directive 93/68/EEC dated 22 July

and free movement of building products to implement the Council Directive 89/106/EEC of 21 December 1988 on the approximation of acts, regulations and administrative provisions of the Member States with regard to building products

rcke, K., Hoffmann, B., Schkade, U., Schmidt, V., Wichterey, K. „Natural radioactivity into building materials and the radiation exposure resulting from it“,

(Entwurf 2008) ederal Office for Radiation Protection, Salzgitter;

ÖNORM S 5200 Radioactivity in construction materials, April 2009, Austrian

adiation Protection, Salzgitter; 2005, Estimation of the annual cases of lung cancer in Germany caused by natural

Annual Report of the Germany’s Federal Office for Radiation Protection, Salzgitter;

Radiation Dose Assessments for Materials with Elevated Natural STO 32, Radiation and Nuclear Safety Authority