scholarly journals It's Time for a New Low-Dose-Radiation Risk Assessment Paradigm—One that Acknowledges Hormesis

Dose-Response ◽  
2007 ◽  
Vol 6 (4) ◽  
pp. dose-response.0 ◽  
Author(s):  
Bobby R. Scott
Keyword(s):  
Risk Assessment ◽  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Current System ◽  
Equivalent Dose ◽  
Exposure Limits ◽  
The Public ◽  
Nuclear Workers ◽  
Radiation Induced

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.

scholarly journals Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal-Fired Power Plant

2021 ◽  
Vol 2021 ◽  
pp. 1-8
Author(s):  
Boldsaikhan Purevsuren ◽  
Juyoul Kim
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radiation Exposure ◽  
Effective Dose ◽  
Nuclear Power ◽  
Equivalent Dose ◽  
Normal Operation ◽  
External Exposure ◽  
The Public ◽  
Organ Equivalent Dose

It has been well known that nuclear power plant and coal-fired power plant release some amount of radioactive materials during their normal operations. The purpose of this study was to compare radiation exposure doses to the public as a consequence of airborne effluents released from nuclear and coal-fired power plants under the normal operation. NRCDose3 was used to estimate radiation exposure doses to the public from gaseous effluents of nuclear power plant during its normal operation while CAP88-PC was used to calculate doses to the public living around coal-fired power plant. The results showed that radiation exposure doses from nuclear power plant were less than those from coal-fired power plant and regulatory annual limits. Effective dose by external exposure, skin equivalent dose, and organ equivalent dose from gaseous effluents of nuclear power plant were 2.93 × 10−4 mSv/y, 2.90 × 10−3 mSv/y, and 1.78 × 10−2 mSv/y, respectively. On the contrary, the corresponding effective dose by external exposure, external skin dose, and organ dose from coal-fired power plant were 1.13 × 10−2 mSv/y, 5.33 × 10−2 mSv/y, and 1.17 × 10−1 mSv/y, respectively.

Radiation exposure of the staff at the therapeutic and diagnostic nuclear medicine department

2008 ◽  
Vol 47 (04) ◽  
pp. 175-177 ◽  
Author(s):  
J. Dolezal
Keyword(s):  
Nuclear Medicine ◽  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Annual Effective Dose ◽  
Protection Measures ◽  
Professional Groups ◽  
Personal Dosimetry ◽  
The Mean ◽  
Administered Activity

SummaryAim: To assess a radiation exposure and the quality of radiation protection concerning a nuclear medicine staff at our department as a six-year retrospective study. Therapeutic radionuclides such as 131I, 153Sm, 186Re, 32P, 90Y and diagnostic ones as a 99mTc, 201Tl, 67Ga, 111In were used. Material, method: The effective dose was evaluated in the period of 2001–2006 for nuclear medicine physicians (n = 5), technologists (n = 9) and radiopharmacists (n = 2). A personnel film dosimeter and thermoluminescent ring dosimeter for measuring (1-month periods) the personal dose equivalent Hp(10) and Hp(0,07) were used by nuclear medicine workers. The wearing of dosimeters was obligatory within the framework of a nationwide service for personal dosimetry. The total administered activity of all radionuclides during these six years at our department was 17,779 GBq (99mTc 14 708 GBq, 131I 2490 GBq, others 581 GBq). The administered activity of 99mTc was similar, but the administered activity of 131I in 2006 increased by 200%, as compared with the year 2001. Results: The mean and one standard deviation (SD) of the personal annual effective dose (mSv) for nuclear medicine physicians was 1.9 ± 0.6, 1.8 ± 0.8, 1.2 ± 0.8, 1.4 ± 0.8, 1.3 ± 0.6, 0.8 ± 0.4 and for nuclear medicine technologists was 1.9 ± 0.8, 1.7 ± 1.4, 1.0 ± 1.0, 1.1 ± 1.2, 0.9 ± 0.4 and 0.7 ± 0.2 in 2001, 2002, 2003, 2004, 2005 and 2006, respectively. The mean (n = 2, estimate of SD makes little sense) of the personal annual effective dose (mSv) for radiopharmacists was 3.2, 1.8, 0.6, 1.3, 0.6 and 0.3. Although the administered activity of 131I increased, the mean personal effective dose per year decreased during the six years. Conclusion: In all three professional groups of nuclear medicine workers a decreasing radiation exposure was found, although the administered activity of 131I increased during this six-year period. Our observations suggest successful radiation protection measures at our department.

scholarly journals RADIATION HYGIENE AND SAFETY OF NUCLEAR INDUSTRY

2019 ◽  
Vol 96 (9) ◽  
pp. 868-874
Author(s):  
O. A. Kochetkov ◽  
A. P. Panfilov ◽  
V. Yu. Usoltsev ◽  
Vladimir N. Klochkov ◽  
S. M. Shinkarev ◽  
...  
Keyword(s):  
Radiation Protection ◽  
Nuclear Fuel ◽  
New Technologies ◽  
Spent Nuclear Fuel ◽  
Regulatory System ◽  
Nuclear Industry ◽  
Special Focus ◽  
Exposure Limits ◽  
The Public ◽  
Methodological Foundation

This article covers basic issues of the radiation protection in nuclear industry. It contains an overview of history of the national nuclear industry including the creation of industry-specific facilities (research centers, medical units etc.). Main stages of the creating the regulatory system for radiation protection, starting from the beginning of the industrial radiation protection, stages of introducing exposure limits and implementation of the radiation protection system in international documents are described. In 1996, for the first time, radiation protection requirements in Russia were documented in the form of the Federal Law 3-FZ of 09.01.1996 “Radiation Protection of the Public". A new stage of updating the global methodological foundation of radiation protection began in 2007. IRCP recommendations of 2007 moved from the legacy practice and intervention approach focused on the process to the approach based on characteristics of exposure situation. The evolvement of new technologies (specifically, in the field of reactor engineering and used nuclear fuel) in recent years requires a special focus on the safety of the personnel and the public. This stipulates the necessity of the appropriate radiation protection support of activities for the safe implementation of modern technologies. Handling of spent nuclear fuel and generated radioactive wastes, safe decommissioning of radiation hazardous facilities, radiation protection during operation of radiation facilities in nonstandard conditions are all the issues requiring specific examination. Regulatory and procedural documents on radiation protection of the personnel and the public during development and implementation of new technologies have been developed and approved as a result of long-term work of scientists and other professionals.

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

2001 ◽  
Author(s):  
R. Barthel ◽  
W. Goldammer ◽  
M. Helming
Keyword(s):  
Radiation Exposure ◽  
Radiation Protection ◽  
The Public ◽  
Naturally Occurring ◽  
Activity Concentrations ◽  
Measurement Strategy ◽  
Naturally Occurring Radionuclides ◽  
Disposal Options ◽  
Mining Residues ◽  
Adequate Measurement

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.

scholarly journals Numerical Modeling of the Exposure on Radiofrequency Radiation of Marine Mammal Observers During Their Shift: A Case Study

2020 ◽  
Vol 10 (6) ◽  
pp. 753-758
Author(s):  
Christos C. Spandonidis ◽  
Kyriakoula Arvaniti
Keyword(s):  
Risk Assessment ◽  
Numerical Modeling ◽  
Radiation Exposure ◽  
Marine Mammal ◽  
Working Environment ◽  
Control Measures ◽  
Operational Environment ◽  
Exposure Limits ◽  
Case Scenario ◽  
Worst Case

Following the standard numerical modeling approach for Electromagnetic Field (EMF) radiation exposure prediction, we intend to provide an analytical framework to Marine Mammal Observers (MMOs) for dynamic risk assessment; enhancing thus occupational health and safety awareness. The analysis is based on power levels and antenna characteristics reported by MMOs for two systems (VHF and UHF) located close to the working environment. Whilst occupational exposure limits apply for MMOs, as for the rest crew (seismic and maritime), evaluation of exposure levels against general public limits is presented as well. At present we have restricted our study to single-source radiation, as well as we did not consider any irregularities due to system malfunction. The worst-case scenario of continuous RF transmission was considered. Risk assessment indicated regions where radiation exposure is higher than the permissible limits. Uncertainty due to the operational environment is inserted in methodology using an uncertainty coefficient. A list of control measures is proposed, to support both MMO’s and Operators’ decision making.

Optimization of radiation exposure for staff using e-controlling devices during radiopharmaceuticals' loading and dispensing procedures in F18-PET/CT daily practice

2018 ◽  
Vol 53 (1) ◽  
pp. 45-50
Author(s):  
C. Peștean ◽  
E. Bărbuș ◽  
M.L. Larg ◽  
D. Piciu
Keyword(s):  
Radiation Exposure ◽  
Effective Dose ◽  
Radiation Protection ◽  
Daily Practice ◽  
Total Activity ◽  
Control Area ◽  
Annual Dose ◽  
Pet Ct ◽  
Total Effective Dose ◽  
Loading Procedure

Background: F18-PET/CT technique has been permanently optimized to ensure the best accuracy and to extend its clinical application. Radiation protection remains an omnipresent aspect of daily practice in F18-PET/CT. Introduction: We tried to demonstrate the usefulness of remotely controlled radiopharmaceutical dispensers with smart-phones or tablets in the optimization of staff exposure. Material and methods: We performed a study to evaluate the exposure during loading and dispensing of radiopharmaceuticals working in two different ways: according to the user's manual of the automatic dispenser and, respectively, with an e-controlling application. We calculated the maximal radiation exposure and analyzed the differences related to the annual effective dose. Have been considered 40 loading and 353 dispensing procedures. During the loading, it has been manipulated a total activity of 9348.8 mCi (345905.6 MBq) FDG. A total activity of 2622.5 mCi (97032.5 MBq) FDG has been manipulated during dispensing. Results: The effective dose resulted from the loading procedure measured at the dispenser contact was 445.05 µSv. The effective dose measured in the remote control area during the loading procedure was 0.34 µSv, having a difference of 444.71 µSv. The total effective dose during dispensing procedures measured at the dispenser was 206.6 µSv and the total effective dose measured in the controlling room was 2.64 µSv, thus a difference of 203.96 µSv. The cumulative difference between the effective doses was of 648.67 µSv. Discussion: E-controlling the dispenser, we got an exposure saving representing 61.2% from the operator's annual dose. Conclusions: This study demonstrates the effectiveness of e-controlling devices in radiation protection of the staff working in F18-PET/CT.

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