scholarly journals On the use of age-specific effective dose coefficients in radiation protection of the public

1998 ◽  
Author(s):  
D.C. Kocher ◽  
K.F. Eckerman
Keyword(s):  
Effective Dose ◽  
Radiation Protection ◽  
The Public ◽  
Dose Coefficients

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.

Radiological safety and assessment of the performance of X-ray systems in veterinary facilities

2020 ◽  
Author(s):  
S. Economides ◽  
C.J. Hourdakis ◽  
C. Pafilis ◽  
G. Simantirakis ◽  
P. Tritakis ◽  
...  
Keyword(s):  
Decision Making ◽  
Radiation Protection ◽  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Regulatory Control ◽  
Continuous Training ◽  
X Ray ◽  
The Public ◽  
Radiological Safety ◽  
High Level

This paper concerns an analysis regarding the performance of X-ray equipment as well as the radiological safety in veterinary facilities. Data were collected from 380 X-ray veterinary facilities countrywide during the on-site regulatory inspections carried out by the Greek Atomic Energy Commission. The analysis of the results shows that the majority of the veterinary radiographic systems perform within the acceptable limits; moreover, the design and shielding of X-ray rooms as well as the applied procedures ensure a high level of radiological safety for the practitioners, operators and the members of the public. An issue that requires specific attention in the optimization process for the proper implementation of veterinary radiology practices in terms of radiological safety is the continuous training of the personnel. The above findings and the regulatory experience gained were valuable decision-making elements regarding the type of the regulatory control of veterinary radiology practices in the new radiation protection framework.

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 Radon Activity Concentrations in Natural Hot Spring Water: Dose Assessment and Health Perspective

2021 ◽  
Vol 18 (3) ◽  
pp. 920
Author(s):  
Eka Djatnika Nugraha ◽  
Masahiro Hosoda ◽  
June Mellawati ◽  
Untara Untara ◽  
Ilsa Rosianna ◽  
...  
Keyword(s):  
Public Health ◽  
Effective Dose ◽  
Radiation Protection ◽  
Water Samples ◽  
Hot Springs ◽  
Hot Spring ◽  
Annual Effective Dose ◽  
Spring Water ◽  
Dose Assessment ◽  
West Java

The world community has long used natural hot springs for tourist and medicinal purposes. In Indonesia, the province of West Java, which is naturally surrounded by volcanoes, is the main destination for hot spring tourism. This paper is the first report on radon measurements in tourism natural hot spring water in Indonesia as part of radiation protection for public health. The purpose of this paper is to study the contribution of radon doses from natural hot spring water and thereby facilitate radiation protection for public health. A total of 18 water samples were measured with an electrostatic collection type radon monitor (RAD7, Durridge Co., USA). The concentration of radon in natural hot spring water samples in the West Java region, Indonesia ranges from 0.26 to 31 Bq L−1. An estimate of the annual effective dose in the natural hot spring water area ranges from 0.51 to 0.71 mSv with a mean of 0.60 mSv for workers. Meanwhile, the annual effective dose for the public ranges from 0.10 to 0.14 mSv with an average of 0.12 mSv. This value is within the range of the average committed effective dose from inhalation and terrestrial radiation for the general public, 1.7 mSv annually.

A review of radiation doses and associated parameters in western australian mining operations (2018-20)

2021 ◽  
Author(s):  
Martin Ian Ralph ◽  
Marcus Cattani
Keyword(s):  
Effective Dose ◽  
Annual Reports ◽  
Radiological Protection ◽  
Annual Dose ◽  
Mining Operations ◽  
Decay Series ◽  
Dose Coefficients ◽  
The Mean ◽  
Institutional Controls ◽  
First Time

Abstract In the 2019-20 reporting period, nineteen mining operations in Western Australia were identified as having workers who were likely to be exposed to ionising radiation stemming from naturally occurring radioactive materials (NORMs), seventeen of which, known hereinafter as Reporting Entities (REs), were required to submit an annual report of the dose estimates of their workforce to the mining regulatory authority. In 2018 the International Commission for Radiological Protection published the revision of the Dose Coefficients (DCs) for occupational intakes of radionuclides of the uranium-238 and thorium-232 decay series, in ICRP-137 and ICRP-141. The 2019-20 annual reports are the first to apply the revised DCs to estimate worker doses. The mean effective dose (ED) reported by the 17 REs increased by 32.4% to 0.94 mSv in 2019-20 from 0.71 mSv reported in 2018-19, indicating that the mean ED is approaching the 1 mSv annual dose estimate at which regulatory intervention should be considered. The mean committed effective dose (CED) from inhalation of dusts containing long-lived alpha-emitting (LLα) nuclides has increased by 35% from 0.40 mSv in 2018-19 to 0.54 mSv in 2019-20. The maximum CED from LLα increased by 16.3% from 3.20 mSv in 2018-19 to 3.72 mSv in 2019-20. The authors consider that, in the absence of other explanations provided by the REs, the increase is largely attributable to the revised DC’s published in ICRP-137 and ICRP-141, but highlight that there are significant variations between REs that make a generalised conclusion problematic. The maximum reported ED in 2019-20 was 6.0 mSv, an increase of 36.4% from 2018-19 (4.4 mSv). The 2019-20 reporting period is the first time in a decade in which mine worker EDs have been elevated to the point that EDs have exceeded 5 mSv, a level at which personal monitoring and additional institutional controls are required.

IN-FLIGHT EXPOSURE TO COSMIC RADIATION ALONG SOME COMMERCIAL AIRLINE ROUTES TO AND FROM NIGERIA

2017 ◽  
Vol 15 (1) ◽  
pp. 57-69
Author(s):  
O O ALATISE ◽  
A A ADEPOJU
Keyword(s):  
Effective Dose ◽  
Radiation Protection ◽  
Cosmic Radiation ◽  
Ground Level ◽  
Radiation Doses ◽  
Human Beings ◽  
The Earth ◽  
Commercial Airline ◽  
Additional Level ◽  
Airline Crews

The study of “external” radiation called cosmic radiation that strikes the earth from anywhere beyond the atmosphere is of great importance in radiation protection. All human beings are exposed to an uncontrollable amount of cosmic radiation on the ground level. Those who travel in space, airline crews and frequent flyers are exposed to additional level of cosmic radiation during their trip but unfor-tunately many of them are not aware of this. This workcalculates the exposure of aircrews and fre-quent flyers to cosmic radiation during travel along some air routes to and from Nigeria. The effective dose was computed using a dedicated software CARI 6M, developed by US FAA.The study focuses on the significance of the in-flight exposure, assessment and estimation of in-flight exposure using the dedicated software and some ways of controlling the exposures so that airline crews and frequent flyers are not exposed to fatal levels of radiation.It was observed that the cosmic radiation doses re-ceived by passengers and crew members on board on flights from Lagos Nigeria to countries in Amer-ica were more than what they received en-route countries in Asia.

scholarly journals A critical look at UNEP reports concerning depleted uranium on Yugoslav territory

2005 ◽  
Vol 20 (1) ◽  
pp. 86-90
Author(s):  
Marko Ninkovic ◽  
Ruzica Glisic
Keyword(s):  
Radiation Protection ◽  
Dose Level ◽  
Depleted Uranium ◽  
Reference Level ◽  
External Exposure ◽  
Dose Limit ◽  
Annual Dose ◽  
Uranium Contamination ◽  
The Public ◽  
Scientific Mission

A critical look at UNEP Reports concerning depleted uranium on Yugoslav territory is presented in this paper. The subjects of the analysis are summarized as remarks high-lighting the following three points: (a) those concerning the use of terms significant and insignificant doses (risks), (b) those concerning the use of 1 mSv as a border between these two risk types and (c) those concerning the composition of ex pert UNEP Teams investigating the depleted uranium issue. To start with, the assumption that it should be possible to express the risks (con sequences) caused by the in take of depleted uranium ( by ingestion/ inhalation and/ or external exposure) to b and g rays from depleted uranium as insignificant or significant for comparison purposes is, in our view, in collision with the linear non thresh old hypothesis, still valid in the radiation protection field. Secondly, the limit of 1 mSv per year as a reference dose level between insignificant and significant risks (con sequences) is not accept able in the case of military depleted uranium contamination. This is because the reference level of 1 mSv, according to the ICRP Recommendation, can be used in the optimization of radiation protection as an additional annual dose limit for members of the public solely for useful practices. Military usage of depleted uranium can not be classified as being useful for both sides - the culprit and the victim alike. Our third objection concerns the composition of ex pert UNEP teams for Kosovo (Desk Assessment Group, Scientific Reviewer Group, and UNEP Scientific Mission) as not being representative enough, bearing in mind all UN member-countries. This last objection may be rather difficult to understand for any one viewing it from the perspective other than that of the victims.

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.

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