Natural Radioactivity In Building Materials Research Articles

Measurement of natural radioactivity of building materials used in the southern valley region of Manipur, India

A study of natural radionuclides of different types of houses was conducted at 493 houses in the southern valley region of Manipur, India. The average annual effective doses of gamma radiation level in indoor and outdoor were estimated from the measurements using Micro R-survey meter and found as 1.25 ± 0.10 (range: 1.02–1.38) mSv/y and 0.76 ± 0.08 (range: 0.58–0.99) mSv/y for reinforced cement concrete (RCC) houses, followed by 1.07 ± 0.09 (range: 0.95–1.19) mSv/y and 0.76 ± 0.08 (range: 0.67–0.95) mSv/y for Adobe laid earthen houses, 1.05 ± 0.09 (range: 0.78–1.24) mSv/y and 0.74 ± 0.08 (range: 0.58–0.91) mSv/y for Assam-type (AT) brick houses, 0.83 ± 0.09 (range: 0.40–1.07) mSv/y and 0.72 ± 0.08 (range: 0.23–0.97) mSv/y for AT mud houses and 0.73 ± 0.08 (range: 0.66–0.82) mSv/y and 0.74 ± 0.07 (range: 0.64–0.82) mSv/y for AT katcha houses. The activity concentration226Ra,232Th, and40K of building materials was evaluated using the gamma ray spectrometry and found average value as 42.4 (range: 23.0–69.9) Bq/kg, 111.3 (range: 23.8–214.5) Bq/kg, and 1369.0 (range: 995.7–2284.6) Bq/kg. Moreover, the annual effective dose conceived from the building material was found as 1.1 mSv/y from Portland cement, 1.4 mSv/y from sand, and 1.5 mSv/y from brick. Seasonal variations of indoor effective dose rates were observed in RCC houses; the highest dose rate was observed during the premonsoon season followed by postmonsoon and least with monsoon season.

Using RESRAD-BUILD to assess the external dose from the natural radioactivity of building materials

RESRAD-BUILD is a code developed by Argonne US National Laboratory for assessing the radiological doses resulting from the occupancy of buildings contaminated with radioactive material. This freely downloadable software allows to consider multiple sources of contamination and to assess not only the external exposure pathway but also the dose resulting from inhalation or ingestion of contaminated dust as well as the dose from inhalation of radon.The software offers the possibility to assess in a flexible way the external dose from the natural radioactivity of building materials. A room model similar to the one used for deriving the activity concentration index of the 2013/59/euratom directive may easily be implemented and gives consistent results.A comparison is made with the calculations performed in the CEN technical report on dose-assessment of gamma radiation from building materials. An example of assessment of the external dose resulting from multiple layers of building materials is given where measurements data are used for the activity concentrations. The assessment allows demonstrating compliance with the reference level set up in the directive.

Criteria for evaluation of building materials hazard based on their natural radioactivity in Russia and in the European Union countries

We hereby have considered the natural radioactivity of building materials as a source of radiation for the human environment. We have considered the Russian and the European evaluation criteria for ensuring radiation safety of the population. We also present an experimental research of the content of natural radionuclides in building materials. We have calculated the effective specific activity and the activity concentration index based on the results presented. We have identified discrepancies between the Russian and the European standards.

Screening tools to limit the use of building materials with enhanced/elevated levels of natural radioactivity: Analysis and application of index criteria

Until now various methods have been developed in several countries to evaluate and classify building materials on the basis of their natural radioactivity. Some of them also account for the contribution of radon to the annual effective dose. In this paper the authors review these methods and apply some of them to the contents of a database of natural radioactivity of building materials in the European Union, that was established by the authors. Based on the activity concentration index introduced by the EC Radiation Protection 112 guidance, IRP112, a new index is also proposed, that accounts for the radon contribution to the effective dose indoors. The results obtained with different indexes are compared in order to evaluate the impact of the new Basic Safety Standards Directive implementation in the EU Member States, particularly in Countries where radioactivity in building materials is already regulated. Moreover, some non EU screening tools were considered to provide suggestions for possible future improvements of the EC IRP112.

Natural radioactivity in granite stones used as building materials in Iran

Due to increasing concern about environmental radiological protection, specific radioactivity concentrations of (226)Ra, (232)Th and (40)K in different types of commonly used granite stone samples collected from the Tehran city of Iran have been determined by means of a high-resolution HPGe gamma-spectroscopy system. The activity concentrations of (232)Th, (226)Ra and (40)K in the selected granite samples ranged from 18 to 178, 6 to 160 and 556 to 1539 Bq kg(-1), respectively. The radium equivalent activities (Ra(eq)) are lower than the limit of 370 Bq kg(-1) set by NEA-OECD [Nuclear Energy Agency. Exposure to radiation from natural radioactivity in building materials. Report by NEA Group of Experts. OECD (1979)], except in two samples. The internal hazard indexes have been found well below the acceptable limit in most of the samples. Five samples of investigated commercial granite stones do not satisfy the safety criterion illustrated by UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation. Exposure from natural sources of radiation. Report to the General Assembly (1993). Applying dose criteria recently recommended by the EC [European Commission Report on Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials. Radiation Protection 112 (1999)] for superficial materials, all investigated samples meet the exemption dose limit of 0.3 mSv y(-1).

Measurement of natural radioactivity in common building materials used in Tiruvannamalai, Tamilnadu, India

The radioactivity of some building materials used in Tiruvannamali City has been measured using a NaI (Tl) detector based gamma ray spectrometer. The distribution of natural occurring radionuclides ( 226 Ra, 232 Th and 40 K) in the building materials was studied. The radium equivalent activity (Ra eq ), the activity utilization index (I), external hazard index (H ex ) and internal radiation hazard index (H in ) associated with the natural radionuclide are calculated to assess the radiation hazard of the natural radioactivity in the building materials. The present work shows that the natural radioactivity levels in the building construction materials used in Tiruvannmalai City is well below the acceptable limits. From the analysis, it was found that these materials may be safely used as construction materials and do not pose significant radiation hazards.

Radiological protection aspects of natural radioactivity of building materials

Radiological protection aspects of natural radioactivity of building materials

Radiological constraints of using building materials and industrial by-products in construction

The advantages of utilization of coal fly ash, phosphogypsum and some other industrial by-products in construction are discussed, as well as the technological and environmental problems caused by an elevated content of chemical/radioactive contaminants. Radiological aspects and legislation issues are analyzed. The tendency to develop stricter environmental norms observed in the last years in both national and international scale is noted. The reasons and possible methods of solving the difficulties with the application of legislation rules and radiation controls in construction industry are discussed. As an example, an experience with the new Israeli Standard 5098 regulating radioactivity in building products is reported. The principles of this standard are analyzed and compared to the Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials Principles of Radiation (Radiological Protection Principles Concerning the Natural Radioactivity of Building Materials, Radiation Protection Report RP-112, EC, European Commission, Luxembourg, 1999) and other existing national standards and guidelines in the field.

Radioactivity of some domestic and imported building materials from South Eastern Europe

Radioactivity of some building materials, gypsum, ceramic, marble, granite, etc., imported from some neighbour countries of South Eastern Europe (Macedonia, Greece and Bulgaria) or produced in Serbia is presented in this paper. Measurements were done with HpGe detector and multichannel analyser. Activity concentration index, I , defined in [EC 1999, 1999. European Commission. Radiation Protection Unit, Radiological protection principles concerning the natural radioactivity of building materials. Radiat. Prot. 112] was calculated for each investigated sample. The ranges of I are 0.0297–1.2545 and 0.0376–0.1521 for Macedonian and Bulgarian gypsum, respectively. The ranges of I for marble are 0.0124–0.6245, 0.0104–1.2089 and 0.0162–0.6747 for Macedonian, Greek and Bulgarian, respectively. The range of I for Greek ceramic and granite are 0.3508–1.0152 and 0.0438–1.0062, respectively. Concentration of natural radionuclides ( 226Ra, 232Th and 40K) are in usual range (except few exceptions) and below maximal permitted values, so that examined materials could be used for construction of new buildings (for interior and external works) as well as for covering of pavements, floors, etc.

Natural Radioactivity of Some Brazilian Building Materials

The natural radioactivity of some building materials commonly used in the city of Sao Paulo was measured by gamma ray spectrometry. The radium equivalent concentration and the gamma absorbed dose rate in air were estimated as well as the internal and external hazard indices. The results indicate that these materials are not a major source of exposure.

Evaluation of gamma and alpha doses due to natural radioactivity of building materials

A method of calculation was developed for evaluating the contributions of external (gamma) and internal (alpha) doses due to the natural radioactivity of building materials. The radionuclides examined are 40K and members of the 235U, 238U and 232Th radioactive decay chains. The method makes it possible to correlate the specific activities of these radionuclides in material used for constructing the walls of a room with the alpha and gamma dose absorbed by an individual at the centre of the room. The results obtained are in agreement with the experimental data and with values calculated by other authors.

Natural radioactivity of building materials

Experiments were designed to measure trace uranium concentration and the rate of radon exhalation from masonry structural materials, both bare and surface finished and coated. LR115 cellulose nitrate track detectors were used to record the alpha emission from structural material surface. Fission track, neutron activation and fluorometric analysis methods were used to determine the uranium content. Most types of paints studied will reduce alpha contribution and radon emanation from building materials.

Natural Radioactivity of Building Materials in Austria

Natural Radioactivity of Building Materials in Austria

Natural Radioactivity of Building Materials in Austria

Natural Radioactivity of Building Materials in Austria