The data below are the 'raw' extracts from the documents and/or papers. Please refer to the last column for the reference and obtain the full text if required. Please also let me know if there are any mistakes here.
No
Data
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1
Netherlands, Slagwool fire doors
In 60's and 70's a type of slagwool containing enhanced levels of radioactivity was used, eg. in fire doors.
Activity (mostly due to Th-232 series) = 150-200 Bq/g, dose rate 0.1-0.2 microSv/hr
A-04
2
Australia, sandblasting
In Queensland (1984-1986) ilmenite was used extensively in the sand blasting.
Dry ilmenite: Th-232 0.2 Bq/g, U-238 0.1 Bq/g; wet ilmenite: Th-232 4.3 Bq/g, U-238 1.1 Bq/g; monazite (90%): Th-232 251.6 Bq/g, U-238 303.4 Bq/g; bagged zircon: Th-232 0.7 Bq/g, U-238 3.9 Bq/g
Exposure due to the use of ilmenite is estimated at ~3 mSv/year.
Garnet heavily contaminated with monazite and zircon was also used for sandblasting (specific activity 40-100 Bq/g Th-232, 15-30 Bq/g U-238). Worst case scenario - 2,500 mSv/year to a sand blasting operator. Residual garnet at a sand blasting yard could result in external exposure of 20-30 mSv/year.
Widespread use and distribution of contaminated garnet - motor body repairers, hobbyists, metal foundries, engineering workshops, ship dock yards, stone masons, gas pipelines.
W-04
3
Italy, tuff and cement
Dose rate: tuff 0.26-0.40 microGy/hr, cement 0.16-0.30 microGy/hr. Tuff analysis: Th-232 0.19-0.35 Bq/g, Ra-226 0.11-0.26 Bq/g, K-40 0.9-2.0 Bq/g.
N-03
4

Hungary
<also relevant for coal>
Coal mined in some regions of Hungary contains elevated concentrations of Ra-226, up to 5- to 10-fold of world average. Coal slag and fly ash are enriched in Ra, - after burning. Slag samples (Bq/g):
Th-232 0.016-0.119, Ra-226 0.16-2.89. Ra significantly above world average for building materialss of 0.05 Bq/g. Gamma dose rates are >0.08 microGy/hr (world average) and 0.12 (Hungarian average) - up to 0.65 microGy/hr

N-04
5

European Union
Natural stone - some granites 1 Bq/g U or Th, black shale (alum shale, other shales) - up to 5 Bq/g, tuff - up to 2 Bq/g
J-02
9
Germany
Masonry bricks with coal ash, Germany (Bq/g):
Brick: Ra-226 0.029, Th-232 0.031, K-40 0.487
Hollow brick: Ra-226 0.078, Th-232 0.063, K-40 0.591
Sand-lime brick: Ra-226 0.081, Th-232 0.062, K-40 0.859
P-05
10

Australia
Building materials in Western Australia (Bq/g):
Red brick: Ra-226 0.03, Th-232 0.06, K-40 0.42
Brown brick: Ra-226 0.02, Th-232 0.09, K-40 0.57
White brick: Ra-226 0.05, Th-232 0.07, K-40 0.82
Concrete: Ra-226 0.02, Th-232 0.03, K-40 0.69
Sand: Ra-226 0.01, Th-232 0.04, K-40 0.09
Granites: Ra-226 0.07, Th-232 0.08, K-40 1.23
Laterites: Ra-226 0.06, Th-232 0.12, K-40 0.30
Bauxite residue: Ra-226 0.08, Th-232 0.32, K-40 0.02
E-07
11
 Taiwan
Measurements of radiation dose from road base in Taoyuan city were carried out. Dose rate on road surface was up to 1.5 microSv/hr (background level in the area is 0.08 microSv/hr). Crushed rock and coarse sand separated from asphalt pavement were identified as the source of excess radioactivity (concentration of Th-232 was up to 4 Bq/g, U-238 - up to 1 Bq/g). Origin of the source material is still not identified.
C-10
12
 Hungary
Brown coal rich in uranium - 0.3-0.9 Bq/g. Slag and spoil of the coal were used in town of Ajka for building before 1960. In the survey of 86 buildings elevated levels of Rn-222 were found. The estimated annual surplus dose is 0.64 mSv for population of the whole town and 1.86 mSv for 7000 occupants of family houses built before 1960.
P-11
13
 EU
A number of waste materials containing enhanced levels of radioactivity are used in the manufacture of building materials. Probably the most significant of these is phosphogypsum, which is used in place of natural gypsum in various building products. Less widespread, but also of radiological significance, is the use of mining wastes and slags, particularly in Germany. Assessments of occupational exposure during the manufacture of building materials using recycled waste suggest that, even with conservative assumptions, individual doses are only a few mSv/yr at most. Studies have shown that a member of the public typically receives an external body dose of only about 0.6 mSv/yr as a result of time spent indoors or in the vicinity of buildings if the building materials do not contain enhanced levels of radioactivity. Thus, there is considerable margin for increases in external exposure resulting from use of the recycled materials.
E-08

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