Exemption Levels for the Recycling and Disposal of Residues With Enhanced Levels of Natural Radioactivity (TENORM) in Germany

Author(s):  
R. Barthel ◽  
W. Goldammer ◽  
M. Helming

Abstract The new German Radiation Protection Ordinance contains for the first time a systematic framework of regulations protecting workers and the public against radiation exposures from residues of industrial and mining processes containing enhanced levels of naturally occurring radionuclides (TENORM). These regulations will satisfy the requirements of the European Council Directive 96/29/EURATOM and serve as a common basis for the radiation protection activities of the German states in this field. The consideration of exposures from materials containing naturally occurring radionuclides gains on this basis an increased level of significance within the German radiation protection efforts. The overall goal of the new regulations is to keep the additional effective dose for the population from the recycling and disposal of TENORM below 1 mSv/a. In order to achieve this objective, companies in which such residues arise have to carry out representative measurements of activity concentrations in these materials. If exemption levels defined in the new regulations are exceeded, restrictions on the recycling and disposal come into effect. These exemption levels are nuclide specific and distinguish between material types and different recycling and disposal options. This specific definition of exemption criteria serves the goal to minimise the number of companies and the amount of residues affected by the new regulations to the extent possible, focussing the efforts of operators and regulators to those materials having the potential to actually cause radiation exposure problems. The specific exemption criteria were derived on the basis of an analysis of typical amounts and activity concentrations of industrial and mining residues with enhanced radioactivity contents in Germany. In a second step, practically applied options for the recycling and disposal of these materials were investigated. On this basis, generic scenarios for the radiation exposure of the workforce and the public were defined and doses were estimated. All relevant pathways including possible long term effects (ground water) were considered in these analyses. Based on the 1 mSv/a criterion, a catalogue of relevant materials, potentially requiring radiation protection measures, was developed. For these materials the practically applied recycling or disposal options were grouped into categories, for which specific exemption levels were derived. The derivation of these criteria was based on realistic estimates of radiation exposure, for example taking into account the dilution of the residues with other materials in technological processes or during the disposal in landfills. The residues subject to the new regulations mostly arise in large quantities over extended periods of time. This leads to significant variations of radionuclide concentrations depending on feed materials and process parameters. To carry out representative measurements without the necessity of taking a too large number of samples, therefore, requires an adequate measurement strategy. Particular aspects to be considered are uncertainties of the measurements themselves and the heterogeneity of the residues. In addition, the measurement strategy has to be compatible with diverse situations in the different industries affected. The framework developed for designing individual strategies for the various industries and types of residues satisfies these requirements and can also provide guidance for measurement campaigns in other areas. The paper outlines the general situation with regard to TENORM in Germany. The main streams of residues and options for their recycling or disposal are described. On this basis, scenarios used for the radiological evaluation are defined and examples for resulting radiation exposures are given. The exemption levels derived from this analysis are discussed. Finally, the framework for the design and implementation of an adequate measurement strategy is outlined.

2019 ◽  
Vol 184 (3-4) ◽  
pp. 391-396 ◽  
Author(s):  
Saïdou ◽  
Shinji Tokonami ◽  
Masahiro Hosoda ◽  
Ndjana Nkoulou II Joseph Emmanuel ◽  
Naofumi Akata ◽  
...  

Abstract Within the framework of a joint research project on natural radiation exposure and its health effects in Cameroon from 2014 to 2017, the Institute of Geological and Mining Research and the Hirosaki University worked together to carry out natural radiation survey in mining and ore bearing regions of Cameroon. Air kerma rates were measured using car-borne survey method. In-situ gamma spectrometry was used to determine activity concentrations of 238U, 232Th and 40K in soil. A total of 450 RADUET detectors and 350 thoron progeny monitors were deployed in dwellings of the study areas for 2–3 months, collected and analysed. Although natural radioactivity level seems to be normal in most of the surveyed areas, there are many points where activity concentrations of natural radionuclides are largely above the world average values. Indoor radon, thoron and thoron progeny results show the importance to put in place the national radon plan in Cameroon. It was also pointed out that thoron cannot be neglected when assessing inhalation dose.


Author(s):  
P. K. Manigandan ◽  
K K Natrajan

Assessments of naturally occurring radionuclides in soil collected from a tropical rainforest forest of western Ghats, India were conducted. These radionuclides were distributed unevenly in the forest soil. For all soil samples, the terrestrial gamma dose rate and the corresponding outdoor annual effective dose equivalents were evaluated. The activity concentration of 232Th and average outdoor gamma dose rates were found to be higher than the global average which appears to affects Western Ghats environment in general, the radiological hazard indices were found to be within the International Commission on Radiological Protection recommended limits. Hence, obtained results for natural radionuclides in the forest soils were within the range specified by UNSCEAR (2000) report for virgin soils except 232Th.


Author(s):  
C K Rotich ◽  
N O Hashim ◽  
M W Chege ◽  
C Nyambura

Abstract The activity concentration of soil samples of Bureti sub-county was measured using thallium-activated sodium iodide detector. To ascertain the level of radiation hazard to the public, gamma radiation dose rates were also estimated. The average activity concentration due to 40K, 226Ra and 232Th for soil samples are 1164 ± 70, 106 ± 8 and 79 ± 5 Bqkg−1, respectively. An average dose rate of 145 ± 10 nGyh−1 was recorded, which is about 2.5 times higher than the world average value of 60 nGyh−1(UNSCEAR). On the other hand, an average outdoor effective dose of 0.35 ± 0.02 mSvy−1 was measured, which is lower than the ICRP safety limit of 1 mSvy−1. This shows that the radiation hazards from naturally occurring terrestrial radionuclides in Bureti is low and therefore human radiation exposure is within the accepted limits.


Dose-Response ◽  
2007 ◽  
Vol 6 (4) ◽  
pp. dose-response.0 ◽  
Author(s):  
Bobby R. Scott

The current system of radiation protection for humans is based on the linear-no-threshold (LNT) risk-assessment paradigm. Perceived harm to irradiated nuclear workers and the public is mainly reflected through calculated hypothetical increased cancers. The LNT-based system of protection employs easy-to-implement measures of radiation exposure. Such measures include the equivalent dose (a biological-damage-potential-weighted measure) and the effective dose (equivalent dose multiplied by a tissue-specific relative sensitivity factor for stochastic effects). These weighted doses have special units such as the sievert (Sv) and millisievert (mSv, one thousandth of a sievert). Radiation-induced harm is controlled via enforcing exposure limits expressed as effective dose. Expected cancer cases can be easily computed based on the summed effective dose (person-sievert) for an irradiated group or population. Yet the current system of radiation protection needs revision because radiation-induced natural protection (hormesis) has been neglected. A novel, nonlinear, hormetic relative risk model for radiation-induced cancers is discussed in the context of establishing new radiation exposure limits for nuclear workers and the public.


2019 ◽  
Vol 186 (4) ◽  
pp. 520-523 ◽  
Author(s):  
Shittu Abdullahi ◽  
Aznan Fazli Ismail ◽  
Supian Samat

Abstract The activity concentrations of 226Ra, 232Th and 40K radionuclides from common building materials used by Malaysian people for construction purposes were studied using High-Purity Germanium (HPGe) detector. The measured activity concentrations of the aforementioned radionuclides range from 10 ± 1 Bq kg−1 (limestone) to 155 ± 61 Bq kg−1 (feldspar), 12 ± 3 Bq kg−1 (limestone) to 274 ± 8 Bq kg−1 (kaolin) and 62 ± 19 Bq kg−1 (limestone) to 1114 ± 20 Bq kg−1 (pottery stone) for 226Ra, 232Th and 40K, respectively. The measured activity concentrations of the natural radionuclides reported herein were found to be in accordance with other previous studies. In general, the activity concentration of the natural radionuclides revealed that all the determined values were below the recommended limit.


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