Dose evaluation for the public around the Tokai reprocessing plant

International Nuclear Information System (INIS)

Takeishi, Minoru; Furuta, Sadaaki; Miyabe, Kenjiro; Shinohara, Kunihiko

2007-01-01

The dose evaluations for the public around the Tokai Reprocessing Plant (TRP) have been carried out by using the mathematical models, because the effects on the environmental radiation due to the operation of the TRP are too small to separate from the background level. The models were developed by the site-specific investigations of the environment and reviewed in several times based on the latest scientific knowledge. The maximum annual effective dose through the whole period of the operation of the TRP was evaluated as 1.4 μSv with the data of the discharge monitoring and the meteorological observation in 1992. The evaluated doses revealed to be kept as far below the annual dose limit for the public as 1 mSv. (author)

Radiation risk factors and dose limits

International Nuclear Information System (INIS)

Barendsen, G.W.

1979-01-01

The contents of the ICRP publications 9 (1965) and 26 (1977) are outlined and the research conducted during these years considered. Expressions are derived for the frequency for induction of cancer from the most common irradiations - X rays, gamma rays and electrons. The dose limits advised by the ICRP are discussed and the first two fundamental principles are presented - that no one should be subjected to radiation without useful cause and that in those cases where irradiation is thought necessary, the medical, scientific, social and economic advantages need to be carefully considered with respect to the possible disadvantages. (C.F.)

Current estimates of radiation risks and implications for dose limits

International Nuclear Information System (INIS)

Clarke, R.H.

1989-01-01

The publication of the 1988 report of UNSCEAR represents a major step forward in that there is an international consensus on the estimation of risk from exposure to ionising radiation. The estimates of fatal cancers in the UNSCEAR report are up to 4 times the values in the 1977 review. This paper will describe the reasons for the increase, the remaining uncertainties and the implications for dose limits in occupational and public exposure. (author)

Effectance, committed effective dose equivalent and annual limits on intake: what are the changes?

International Nuclear Information System (INIS)

Kendall, G.M.; Stather, J.W.; Phipps, A.W.

1990-01-01

This paper outlines the concept of effectance, compares committed effectance with the old committed effective dose equivalent and goes on to discuss changes in the annual limits on intakes and the maximum organ doses which would result from an intake of an ALI (Annual Limit of Intake). It is shown that committed effectance is usually, but not always, higher than committed effective dose equivalent. ALIS are usually well below those resulting from the ICRP Publication 30 scheme. However, if the ALI were based only on a limit on effectance it would imply a high dose to specific organs for certain nuclides. In order to control maximum organ doses an explicit limit could be introduced. However, this would destroy some of the attractive features of the new scheme. An alternative would be a slight modification to some of the weighting factors. (author)

The monetary value of the averted dose for public exposure

International Nuclear Information System (INIS)

Katona, T.; Eged, K.; Kanyar, B.; Kis, Z.; Nenvei, A.

2002-01-01

In general, the concept of optimisation in radiation protection and safety appears as cost-minimisation in new procedures, methods in practices, and/or protective actions following unacceptable contamination. In the practical implementation of the concept, the cost of protective actions should be balanced with the benefits of exposure reduction. The monetary value of the averted dose can be assessed by the product of the cost of unit avoided collective dose (alpha-value) and the averted collective dose (ICRP 1991, 1993). According to the ICRP and others, the monetary value of the averted dose - in addition to the avoided health detriment - needs to take into account economical and social circumstances, ethical factors etc. (ICRP 1993, 2000; IBSS 1995; Oughton 2000). Most of the alpha-value assessments have been performed for workers (Hardeman et al. 1998; Lefaure 1998). Due to the different dose limitations and action levels for public exposures the monetary value of the averted dose may vary whether the averted dose refers to workers or to the public. Until now, only a few investigations have been performed to the public exposures. Eeckhoudt et al. (1999) proposed a method based on compensation dependency and on comparisons between the workers and the general public. The present paper includes the results obtained by the WTP method for the public. The questionnaire and analysis were developed by the CEPN (Centre d'Etude sur L'Evaluation de la Protection dans le Domaine Nucleaire, France) for specialists in the nuclear field (Leblanc et al. 1994). In 2000, questionnaire modifications were first introduced to adjust the Hungarian factors (Eged et al. 2001, 2002). The questionnaire was further modified in 2001 to take into account the Hungarian public factors

Experience with dose limitation during preparations for sea dumping operations

International Nuclear Information System (INIS)

Fieuw, G.; Voorde, N. van de; Baekelandt, L.

1982-01-01

Since 1967 low-level radioactive wastes from operational nuclear facilities in Belgium have been dumped into the sea. The dumping is carried out in accordance with the recommendations issued by the IAEA under the London Convention. All these dumping operations have taken place under the surveillance of the Nuclear Energy Agency of the OECD. To limit the doses received by workers and the public during the various phases leading up to sea dumping, appropriate measures are required in connection with waste treatment and packaging, limitation of radiation levels, storage and handling, organization and selection of the means of transport and organization and means of monitoring. Although treatment and handling at the nuclear sites are entrusted to occupationally exposed workers, temporary labour is used for the transport and handling operations. Effective treatment and packaging reduce the risk of internal exposure to a negligible value. Meticulous planning and permanent personnel monitoring reduce the doses received by the workers to acceptable values not exceeding the statutory dose limits. The doses received by personnel involved in the preparations for sea dumping operations from 1967 to 1980 are given and a relationship is established between these doses and the activities handled. Experience shows that sea dumping operations do not entail unacceptable risks either for the workers concerned or for the population and allows us to optimize the methods used for loading, handling and transport. (author)

State of the art in Europe on dose limit

International Nuclear Information System (INIS)

Munoz, M. J.; Amor, I.

2002-01-01

The process of setting up new radiological protection limits and requirements constitutes a long and laborious task, since the definition of the scientific bases that support them until their obliged fulfillment by adoption in national regulations. This paper analyzes the most important news contained in the Directive 96/29/Euratom, that are being transposed into Member States national legislations. Additionally the implications derived from the process are taken into consideration. Certain items as the new dose limits for exposed workers and public, the application of dose constraints, and the requirements for the protection of pregnant women and fetus, were object of special controversy during the development of the directive and they are not being transposed in a common way. So the different approach in the setting up of occupational doses can generate difficulties in the context of the european market. Through the directive constitutes the framework for the radiological protection in the European Union, there are certain difficulties for common implementation that will require subsequent explanations from the Commission and the Competent National Authorities. (Author)

Use of dose constraints in public exposure

International Nuclear Information System (INIS)

Tageldein, Amged

2015-02-01

An overview of the dose constraints in public exposures has been carried out in this project. The establishment, development and the application of the concept of dose constraints are reviewed with regards to public exposure. The role of dose constraints in the process of optimization of radiation protection was described and has been showed that the concept of the dose constraints along with many other concept of radiation protection is widely applied in the optimization of exposure to radiation. From the beginning of the establishment of dose constraints as a concept in radiation protection, the International Commission of Radiological Protection (ICRP) has published a number of documents that provides detailed application related to radiation protection and safety of public exposure from ionizing radiation. This work provides an overview of such publications and related documents with special emphasis on optimization of public exposure using dose constraints. (au)

Revision of risk estimates and implications for dose limits

International Nuclear Information System (INIS)

Clarke, R.H.

1989-01-01

It has been apparent for some time that our estimates of the risks associated with exposure to ionizing radiation must be increased above those values reported by UNSCEAR in 1977 an dused by ICRP to form their present recommendations. NRPB foresaw some of these changes and introduced interim advice within the UK to restrict exposures of wordkers and members of the public to levels below the existing limits. Since that advice was given, UNSCEAR has produced a 1988 report reviewing human data to provide new estimates of risks associated with exposure at high doses and high doserates. These risk figures are up to 4 times higher than when UNSCEAR reported in 1977. In this paper, the reasons for the changes in the estimates of risk will be described and the current NRPB guidelines for risk factors for protection purposes will be presented. The implications of these new risk factors for the setting of dose limits will then be discussed. (Author). 10 refs.; 2 tabs

Philosophy evolution of the dose limitation system and the issue of replacements in the 'superseded' publications; Evolução da filosofia do sistema de limitação de dose e a questão das substituições 'superseded'

Energy Technology Data Exchange (ETDEWEB)

Correa, Felipe Ramos

2016-07-01

In 1958 the International Commission on Radiological Protection (ICRP) first proposed the philosophy of the dose limitation system by introducing the Permissible Maximum Annual Limits (PMAL). The breakthrough of the nuclear age in recent decades has imposed new paradigms and the need to update the philosophy in question. This work aims to present an analysis about the philosophy evolution of the dose limitation system, from the 50’s to the present day. The first paradigm shift occurred with the creation of Allowable Maximum Annual Limits (AMAL), still in force. Through a careful study of the International Atomic Energy Agency (IAEA) publications and the ICRP recommendations, it was possible to highlight and detail the process of evolution of AMAL over the past decades. The research addresses key moments that have driven change in the philosophy of the dose limitation system, for example, the international oil crisis and its implications in the development of nuclear area. The comparison of the various publications of the two entities (IAEA and ICRP) allowed a thorough study since the emergence of these philosophies to their latest publications. The results of this study indicate important information contained in ICRP publications, now considered {sup s}uperseded{sup ,} which are not found in current publications. The IAEA, which prepares its recommendations based on the philosophy of the ICRP, also does not address such information. Through this research, it was possible clear and detail valuable information that was lost during the process of updating publications and editing recommendations of both entities. This study aims to present this information, which were studied in depth, discussing their real value, proposing to the new international community reflections on the importance and the possibility of reintroducing the lost information in future publications. (author)

Internal dose conversion factors for calculation of dose to the public

International Nuclear Information System (INIS)

1988-07-01

This publication contains 50-year committed dose equivalent factors, in tabular form. The document is intended to be used as the primary reference by the US Department of Energy (DOE) and its contractors for calculating radiation dose equivalents for members of the public, resulting from ingestion or inhalation of radioactive materials. Its application is intended specifically for such materials released to the environment during routine DOE operations, except in those instances where compliance with 40 CFR 61 (National Emission Standards for Hazardous Air Pollutants) requires otherwise. However, the calculated values may be equally applicable to unusual releases or to occupational exposures. The use of these committed dose equivalent tables should ensure that doses to members of the public from internal exposures are calculated in a consistent manner at all DOE facilities

ICRP-recommendations on dose limits for workers

International Nuclear Information System (INIS)

Beninson, D.J.

1976-01-01

Dose limits proposed by the ICRP have been incorporated in most national and international standards and their respect has caused a distribution of doses with a average not exceeding 1/10 of the maximum permissible dose. This distribution corresponds to a risk which is well within the risks in 'safe industries'. There are at present some inconsistancies in the current system of recommended limits, for example having the same limit of 5 rem for the whole-body and also for some organs. Hopefully, this incosistancy will be removed in the next recommendation of the ICRP. But the whole-body limit of 5 rem in a year has been safe and there is little ground to reduce this limit on the basis of comparisons with 'safe industries'. (orig./HP) [de

Principles of the International Commission on Radiological Protection system of dose limitation

International Nuclear Information System (INIS)

Thorne, M.C.

1987-01-01

The formulation of a quantitative system of dose limitation based on ICRP principles of 'stochastic' and 'non-stochastic' effects requires that judgements be made on several factors including: relationships between radiation dose and the induction of deleterious effects for a variety of endpoints and radiation types; acceptable levels of risk for radiation workers and members of the public; and methods of assessing whether the cost of introducing protective measures is justified by the reduction in radiation detriment which they will provide. In the case of patients deliberately exposed to ionising radiations, the objectives of radiation protection differ somewhat from those applying to radiation workers and members of the public. For patients, risks and benefits relate to the same person and upper limits on acceptable risks may differ grossly from those appropriate to normal individuals. For these reasons, and because of its historical relationship with the International Congress of Radiology, the ICRP has given special consideration to radiation protection in medicine and has published reports on protection of the patient in diagnostic radiology and in radiation therapy. (author)

When is a dose not a dose?

International Nuclear Information System (INIS)

Green, Patrick

1992-01-01

There is confusion over radiation dose limits between the International Commission on Radiological Protection, the National Radiological Protection Board and the Ministry of Agriculture, Fisheries and Food (MAFF), reports a Friends of the Earth's radiation campaigner. MAFF is suggesting the inadequate ICRP public dose limit does not apply to public exposures which arise from environmental contamination from past radioactive discharges. (author)

Practical application of the dose limitation system in a uranium fuel fabrication plant

International Nuclear Information System (INIS)

Auricchio, S.; Cantoro, N.

1982-01-01

ICRP Publication 26 was published when the nuclear operators and the different national regulatory bodies were already in a position to understand the proposed dose limitation system and to apply it to nuclear activities. In Italy the basic principle of limiting individual risks and the search for increased protection were already applied in the radiation analysis of nuclear plants. These principles were applied during design (1972-74) and operation (1974-80) of the industrial fuel-element fabrication plant of the company Fabbricazioni Nucleari (F.N.) in Bosco Marengo. The paper reports on the criteria followed in the design stage, the organization and methods adopted for reducing the doses during operation, and the results achieved after a few years of plant activity. In view of the purely technical nature of this paper, the first principle of the dose limitation system (justification), which is more a political issue, is not taken into consideration; however, an assessment of the Italian context as at the end of the 1960s shows that the principle of justification of a practice was adequately taken into account when the construction of the F.N. plant was decided on. (author)

The dose limits in radiation protection: foundations and evolution perspectives

International Nuclear Information System (INIS)

Lochard, J.

1999-01-01

The first part of this article is devoted to the evolution of dose limits in radiation protection since 1928. The second part tackles the difficulties to whom the ICRP system of limitation collides with. The notions of dose limits, ALARA principle are explained and the concept of dose constraints is introduced. (N.C.)

New dose limits and distribution of annual doses for controlled groups

International Nuclear Information System (INIS)

Vukcevic, M.; Stankovic, S.; Kovacevic, M.

1993-01-01

The new calculations of neutron doses received by the population of Hiroshima and Nagasaki, as well as the epidemiological data on the incidence of fatal cancers in the survivors, had led to the conclusion that the risk estimates should be raised by the factor 2 or 3. In this work, the distribution of monthly doses for occupationals was analysed in order to determine the percent of workers who might be considered as overexposed, on the basis of the new dose limits. (author)

Public Dose Assessment Modeling from Skyshine by Proton Accelerator

Energy Technology Data Exchange (ETDEWEB)

Mwambinga, S. A. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Yoo, S. J. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

In this paper, the skyshine dose by proton accelerator (230 MeV) has been evaluated. The amount of dose by skyshine is related to some influence factors which are emission angle (Height wall), the thickness of ceiling and distance from source to receptor (Human body). Empirical formula is made by using MCNPX code results. It can easily calculate and assess dose from skyshine by proton accelerator. The skyshine doses are calculated with MCNPX code and DCFs in ICRP 116. Thereafter, we made empirical formula which can calculate dose easily and be compared with the results of MCNPX. The maximum exposure point by skyshine is about 5 ∼ 10 m from source. Therefore, the licensee who wants to operate the proton accelerator must keep the appropriate distance from accelerator and set the fence to restrict the approach by the public. And, exposure doses by accelerator depend on operating time and proton beam intensities. Eq. (6) suggested in this study is just considered for mono energy proton accelerator. Therefore, it is necessary to expand the dose calculation to diverse proton energies. Radiations like neutron and photon generated by high energy proton accelerators over 10 MeV, are important exposure sources to be monitored to radiation workers and the public members near the facility. At that case, one of the exposure pathways to the public who are located in near the facility is skyshine. Neutrons and photons can be scattered by the atmosphere near the facility and exposed to public as scattered dose. All of the facilities using high energy radiation and NDI (Non-Destructive Inspection) which is tested at open field, skyshine dose must be taken into consideration. Skyshine dose is not related to the wall thickness of radiation shielding directly.

Dose assessment for public at the hypothetical submergence of a fresh MOX fuel package

International Nuclear Information System (INIS)

Tsumune, Daisuke; Saegusa, Toshiari; Suzuki, Hiroshi; Maruyama, Koki

2000-01-01

For the structure and equipment of transport ships for fresh MOX fuels, there is a special safety standard called the INF Code of IMO (International Maritime Organization). For transport of radioactive materials, there is a safety standard stipulated in Regulations for the Safe Transport of Radioactive Material issued by IAEA (International Atomic Energy Agency). Under those code and standard, fresh MOX fuel is transported safety on the sea. To gain the public acceptance for this transport, a dose assessment has been made by assuming that a fresh MOX fuel package might be sunk into the sea by unknown reasons. In the both cases for a package sunk at the coastal region and for that sunk at the ocean, the evaluated result of the dose equivalent by radiation exposure to the public are far below the dose equivalent limit of the ICRP recommendation (1 mSv/year). (author)

The ICRP Proposed Maximum Public Dose Constraints of o.3 mSv/y: a Major Issue for the Nuclear Industry

International Nuclear Information System (INIS)

Saint-Pierre, S.; Coates, R.

2004-01-01

The International Commission on Radiological Protection (ICRP) is currently developing a new set of Recommendations on Radiological Protection. A value of 0.3mSv/y for the maximum public dose constraint has been discussed by ICRP. This value represents a major concern for the nuclear industry at large. The primary issue arises from the lack of any new scientific evidence on public health effects from ionising radiation to support, in practice, the proposed reduction by about a factor of 3 (from 1 to 0.3 mSv/y) of the upper bound value for public dose impact from a nuclear activity or site. Such a change would create a de facto limit on public exposure from specific sources at a dose level of about one tenth of average natural background and an even smaller fraction of the typical range of background exposures and exposures from medical sources. This cannot be justified on public health grounds. The WNA supports ICRP's renewed intention, as expressed at the NEA-ICRP Stakeholder Forum in Lanzarote (April 2003), to retain the concept of a public dose limit at 1 mSv/y. We strongly believe that the current system comprising of the dose limit and the ALARA Principle provides the necessary flexibility and tools for regulators to address all situations in all countries. The WNA consider that the question of setting an upper bound dose constraint (below 1 mSv/y) at the country/site specific level is best left for discussion and agreement between the local stakeholders rather than at an international level. When considering the potential practical implications of a maximum dose constraint, it is important to look beyond the very low off-site dose impacts (on the public) resulting from annual routine radioactive discharges of nuclear industrial sites. There are many off-site and on-site practical situations, related to public exposures (both workers and the public) and worker classification as well as activities such transportation, decommissioning and site remediation, for

The ICRP Proposed Maximum Public Dose Constraints of o.3 mSv/y: a Major Issue for the Nuclear Industry

Energy Technology Data Exchange (ETDEWEB)

Saint-Pierre, S.; Coates, R.

2004-07-01

The International Commission on Radiological Protection (ICRP) is currently developing a new set of Recommendations on Radiological Protection. A value of 0.3mSv/y for the maximum public dose constraint has been discussed by ICRP. This value represents a major concern for the nuclear industry at large. The primary issue arises from the lack of any new scientific evidence on public health effects from ionising radiation to support, in practice, the proposed reduction by about a factor of 3 (from 1 to 0.3 mSv/y) of the upper bound value for public dose impact from a nuclear activity or site. Such a change would create a de facto limit on public exposure from specific sources at a dose level of about one tenth of average natural background and an even smaller fraction of the typical range of background exposures and exposures from medical sources. This cannot be justified on public health grounds. The WNA supports ICRP's renewed intention, as expressed at the NEA-ICRP Stakeholder Forum in Lanzarote (April 2003), to retain the concept of a public dose limit at 1 mSv/y. We strongly believe that the current system comprising of the dose limit and the ALARA Principle provides the necessary flexibility and tools for regulators to address all situations in all countries. The WNA consider that the question of setting an upper bound dose constraint (below 1 mSv/y) at the country/site specific level is best left for discussion and agreement between the local stakeholders rather than at an international level. When considering the potential practical implications of a maximum dose constraint, it is important to look beyond the very low off-site dose impacts (on the public) resulting from annual routine radioactive discharges of nuclear industrial sites. There are many off-site and on-site practical situations, related to public exposures (both workers and the public) and worker classification as well as activities such transportation, decommissioning and site remediation

Dose Modeling Evaluations and Technical Support Document For the Authorized Limits Request for the DOE-Owned Property Outside the Limited Area, Paducah Gaseous Diffusion Plant Paducah, Kentucky

Energy Technology Data Exchange (ETDEWEB)

Boerner, A. J. [Oak Ridge Institute for Science and Education (ORISE), Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program; Maldonado, D. G. [Oak Ridge Institute for Science and Education (ORISE), Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program; Hansen, Tom [Ameriphysics, LLC (United States)

2012-09-01

Environmental assessments and remediation activities are being conducted by the U.S. Department of Energy (DOE) at the Paducah Gaseous Diffusion Plant (PGDP), Paducah, Kentucky. The Oak Ridge Institute for Science and Education (ORISE), a DOE prime contractor, was contracted by the DOE Portsmouth/Paducah Project Office (DOE-PPPO) to conduct radiation dose modeling analyses and derive single radionuclide soil guidelines (soil guidelines) in support of the derivation of Authorized Limits (ALs) for 'DOE-Owned Property Outside the Limited Area' ('Property') at the PGDP. The ORISE evaluation specifically included the area identified by DOE restricted area postings (public use access restrictions) and areas licensed by DOE to the West Kentucky Wildlife Management Area (WKWMA). The licensed areas are available without restriction to the general public for a variety of (primarily) recreational uses. Relevant receptors impacting current and reasonably anticipated future use activities were evaluated. In support of soil guideline derivation, a Conceptual Site Model (CSM) was developed. The CSM listed radiation and contamination sources, release mechanisms, transport media, representative exposure pathways from residual radioactivity, and a total of three receptors (under present and future use scenarios). Plausible receptors included a Resident Farmer, Recreational User, and Wildlife Worker. single radionuclide soil guidelines (outputs specified by the software modeling code) were generated for three receptors and thirteen targeted radionuclides. These soil guidelines were based on satisfying the project dose constraints. For comparison, soil guidelines applicable to the basic radiation public dose limit of 100 mrem/yr were generated. Single radionuclide soil guidelines from the most limiting (restrictive) receptor based on a target dose constraint of 25 mrem/yr were then rounded and identified as the derived soil guidelines. An additional evaluation using the derived soil

Dose Modeling Evaluations and Technical Support Document For the Authorized Limits Request for the DOE-Owned Property Outside the Limited Area, Paducah Gaseous Diffusion Plant Paducah, Kentucky

International Nuclear Information System (INIS)

Boerner, A. J.

2012-01-01

Environmental assessments and remediation activities are being conducted by the U.S. Department of Energy (DOE) at the Paducah Gaseous Diffusion Plant (PGDP), Paducah, Kentucky. The Oak Ridge Institute for Science and Education (ORISE), a DOE prime contractor, was contracted by the DOE Portsmouth/Paducah Project Office (DOE-PPPO) to conduct radiation dose modeling analyses and derive single radionuclide soil guidelines (soil guidelines) in support of the derivation of Authorized Limits (ALs) for 'DOE-Owned Property Outside the Limited Area' ('Property') at the PGDP. The ORISE evaluation specifically included the area identified by DOE restricted area postings (public use access restrictions) and areas licensed by DOE to the West Kentucky Wildlife Management Area (WKWMA). The licensed areas are available without restriction to the general public for a variety of (primarily) recreational uses. Relevant receptors impacting current and reasonably anticipated future use activities were evaluated. In support of soil guideline derivation, a Conceptual Site Model (CSM) was developed. The CSM listed radiation and contamination sources, release mechanisms, transport media, representative exposure pathways from residual radioactivity, and a total of three receptors (under present and future use scenarios). Plausible receptors included a Resident Farmer, Recreational User, and Wildlife Worker. single radionuclide soil guidelines (outputs specified by the software modeling code) were generated for three receptors and thirteen targeted radionuclides. These soil guidelines were based on satisfying the project dose constraints. For comparison, soil guidelines applicable to the basic radiation public dose limit of 100 mrem/yr were generated. Single radionuclide soil guidelines from the most limiting (restrictive) receptor based on a target dose constraint of 25 mrem/yr were then rounded and identified as the derived soil guidelines. An additional evaluation using the derived soil

The revision of dose limits for exposure to ionizing radiation

International Nuclear Information System (INIS)

Hughes, D.

1990-01-01

The paper reviews the current dose limits for exposure to ionizing radiations and the risk factors on which they are based, and summarizes the revised risk factors and the draft proposals for new dose limits published by the International Commission on Radiological Protection. (author)

Dose assessment for public by packages shipping radioactive materials hypothetically sunk on the continental shelf. Annex 3

International Nuclear Information System (INIS)

Tsumune, Daisuke; Suzuki, Hiroshi; Saegusa, Toshiari; Watabe, Naohito; Asano, Hiroyuki; Maruyama, Koki; Kinehara, Yoshiki

2001-01-01

Radioactive materials such as spent fuel (SF), PuO 2 powder, high level wastes (HLW) and fresh mixed oxide (MOX) fuel have been transported by sea between Europe and Japan. Dose assessments for public have been performed in the past when the packages shipping radioactive materials were hypothetically sunk on the continental shelf. These studies employed various conditions and methods in their assessments and the results were not always the same. In this study, the dose assessment for these packages was performed under the same conditions and by the same methods. The effective dose equivalents of radiation exposure to the public for all materials become smaller than the previous evaluations due to more realistic assumption in this study. These evaluated results are far less than the effective dose equivalent limit (1 mSv year -1 ) by the ICRP recommendation. (author)

Dose. Detriment. Limit assessment

International Nuclear Information System (INIS)

Breckow, J.

2015-01-01

One goal of radiation protection is the limitation of stochastic effects due to radiation exposure. The probability of occurrence of a radiation induced stochastic effect, however, is only one of several other parameters which determine the radiation detriment. Though the ICRP-concept of detriment is a quantitative definition, the kind of detriment weighting includes somewhat subjective elements. In this sense, the detriment-concept of ICRP represents already at the stage of effective dose a kind of assessment. Thus, by comparing radiation protection standards and concepts interconvertible or with those of environment or occupational protection one should be aware of the possibly different principles of detriment assessment.

The biological basis for dose limitation to the skin

International Nuclear Information System (INIS)

Fry, R.J.M.

1992-01-01

Ionizing radiation may cause deterministic effects and cancer. It has been the policy to base dose limits for radiation protection of the skin on the prevention of deterministic effects (1). In the case of cancer in general, dose limitation for radiation protection is based on limiting excess cancer mortality to low levels of radiation. Since skin cancers are seldom lethal, the general radiation protection standards will protect against an increase in excess mortality from skin cancer. However, with the dose limits selected to prevent deterministic effects, there is a significant probability of an excess incidence of skin cancer occurring as a result of exposure during a working lifetime. The induction of skin cancer by radiation is influenced significantly by subsequent exposure to ultraviolet radiation (UVR) from sunlight. This finding raises not only interesting questions about the mechanisms involved, but also about the differences in risk of skin cancer in different populations. The amount and distribution of melanin in the skin determines the degree of the effect of UVR. This paper discusses the mechanisms of the induction of both deterministic and stochastic effects in skin exposed to radiation in relation to radiation protection. (author)

Analysis Approach and Data Package for Mayak Public Doses

Energy Technology Data Exchange (ETDEWEB)

Eslinger, Paul W.; Napier, Bruce A.

2013-09-18

Historical activities at facilities producing nuclear materials for weapons released radioactivity into the air and water. Past studies in the United States have evaluated the release, atmospheric transport and environmental accumulation of 131I from the nuclear facilities at Hanford in Washington State and the resulting dose to members of the public (Farris et al. 1994). A multi-year dose reconstruction effort (Mokrov et al. 2004) is also being conducted to produce representative dose estimates for members of the public living near Mayak, Russia, from atmospheric releases of 131I at the facilities of the Mayak Production Association. The approach to calculating individual doses to members of the public from historical releases of airborne 131I has the following general steps: • Construct estimates of releases 131I to the air from production facilities. • Model the transport of 131I in the air and subsequent deposition on the ground and vegetation. • Model the accumulation of 131I in soil, water and food products (environmental media). • Calculate the dose for an individual by matching the appropriate lifestyle and consumption data for the individual to the concentrations of 131I in environmental media at their residence location. A number of computer codes were developed to facilitate the study of airborne 131I emissions at Hanford. Of particular interest is DESCARTES code that modeled accumulation of 131I in environmental media (Miley et al. 1994). In addition, the CIDER computer code estimated annual doses to individuals (Eslinger et al. 1994) using the equations and parameters specific to Hanford (Snyder et al. 1994). Several of the computer codes developed to model 131I releases from Hanford are general enough to be used for other facilities. Additional codes have been developed, including the new individual dose code CiderF (Eslinger and Napier 2013), and applied to historical releases of 131I from Mayak. This document provides a data package that

Environmental radiation standards and risk limitation

International Nuclear Information System (INIS)

Kocher, D.C.

1987-01-01

The Environmental Protection Agency and Nuclear Regulatory Commission have established environmental radiation standards for specific practices which correspond to limits on risk to the public that vary by several orders of magnitude and often are much less than radiation risks that are essentially unregulated, e.g., risks from radon in homes. This paper discusses a proposed framework for environmental radiation standards that would improve the correspondence with limitation of risk. This framework includes the use of limits on annual effective dose equivalent averaged over a lifetime, rather than limits on dose equivalent to whole body or any organ for each year of exposure, and consideration of exposures of younger age groups as well as adults; limits on annual effective dose equivalent averaged over a lifetime no lower than 0.25 mSv (25 mrem) per practice; maintenance of all exposures as low as reasonably achievable (ALARA); and establishment of a generally applicable de minimis dose for public exposures. Implications of the proposed regulatory framework for the current system of standards for limiting public exposures are discussed. 20 refs

Doses to nurses by the technetium-99m, in private and public sector

International Nuclear Information System (INIS)

Bied, J.Ch.; Philippon, B.

1999-01-01

The global body dose due to the technetium is 1.2 and 1.9 mSv for the two nurses of the private sector. In the public sector, the level reached by the personnel is 0.75 mSv for the global body dose, and the only technetium (global body dose 1.4 and 2.1 mSv for the private sector, 0.95 for the public sector and for the whole of radiations measured by the O.P.R.I. film dosemeter. The doses received at the fingers level present higher levels in the private sector. But these values, 15.2 and 10.7 mSv by month, that is to say 180 mSv by year are the 2/5 of the maximum permissible value. The two persons of the private sector received whole body doses, higher that the doses of the public sector. These doses are about 1.2 to 1.9 these ones received in the public sector. (N.C.)

Outlines of ICRP publication 74 and new dose conversion coefficients for external radiation

International Nuclear Information System (INIS)

Yamaguchi, Yasuhiro

1998-01-01

Combined task group of ICRP and ICRU reported the ICRP Publication 74 (1996) which is a summary report of their collection, analysis and evaluation of many data and dose conversion coefficients. Concerning the new coefficients, the author described this review as follows: History until Publication 74. Doses recommended at present: for protection quantity, the mean absorption dose of organ and tissue, equivalent dose and effective dose and for operational quantity, the ambient dose equivalent, directional dose equivalent and individual dose equivalent. Changes which can have an influence on the dose evaluation; introduction of radiation weighting factor (WR), changing of tissue weighting factor (WR), changing of the equation for Q-L relation and updating of physical data. New dose conversion coefficients; for photon, neutron and electron. Comparison of new and present coefficients; concerning the quality factor Q, particularly for neutron Q. New relations of protection and operational quantities; for field and individual monitoring. General conclusion of Publication 74. The Publication gives a certain direction for problems in evaluation of external exposure dose which have been discussed since the ICRP Fundamental Recommendation 1990 was issued. However, there still remain many problems especially in validity of the WR and of equation for Q-L relation. (K.H.)

Assessing dose of the representative person for the purpose of radiation protection of the public. ICRP publication 101. Approved by the Commission in September 2005.

Science.gov (United States)

2006-01-01

The Commission intended that its revised recommendations should be based on a simple, but widely applicable, system of protection that would clarify its objectives and provide a basis for the more formal systems needed by operating managers and regulators. The recommendations would establish quantified constraints, or limits, on individual dose from specified sources. These dose constraints apply to actual or representative people who encounter occupational, medical, and public exposures. This report updates the previous guidance for estimating dose to the public. Dose to the public cannot be measured directly and, in some cases, it cannot be measured at all. Therefore, for the purpose of protection of the public, it is necessary to characterise an individual, either hypothetical or specific, whose dose can be used for determining compliance with the relevant dose constraint. This individual is defined as the 'representative person'. The Commission's goal of protection of the public is achieved if the relevant dose constraint for this individual for a single source is met and radiological protection is optimised. This report explains the process of estimating annual dose and recognises that a number of different methods are available for this purpose. These methods range from deterministic calculations to more complex probabilistic techniques. In addition, a mixture of these techniques may be applied. In selecting characteristics of the representative person, three important concepts should be borne in mind: reasonableness, sustainability, and homogeneity. Each concept is explained and examples are provided to illustrate their roles. Doses to the public are prospective (may occur in the future) or retrospective (occurred in the past). Prospective doses are for hypothetical individuals who may or may not exist in the future, while retrospective doses are generally calculated for specific individuals. The Commission recognises that the level of detail afforded by its

Effective dose of individuals from the surrounding public to the facilities of the Abadia de Goiás radioactive waste disposal

International Nuclear Information System (INIS)

Ribeiro, E.; Borges, A.F. de Almeida; Camargos, K.M.; Santos, E.E. dos; Correa, R. da S.; Ferreira, N.C.; Ribeiro, N.V.

2017-01-01

The study presents the level of effective annual dose that individuals from the public - surrounding the repository of wastes with Cs-137, located in Abadia de Goiás, GO, Brazil - have received, according to analyzes carried out from June 2015 to July 2016. It was considered reference to the annual effective radiation dose limit of 0.3 mSv / year established by the National Nuclear Energy Commission (CNEN) for the impact of repositories on individuals in the public. Cs-137 activity determinations were performed on samples of surface water (ASU), groundwater (ASB), river bottom sediments (SED), soil (SOL) and vegetation (VEG). With these results, the effective doses were estimated for ASU and BSA consumption of 6.64 x 10 -4 mSv / year and for SED exposure, 3.92 x 10 - 6 mSv / year and for ASB use, 6.22 x 10 -3 mSv / year. For SOL and VEG, activity values of Cs-137 were used as indicators of contamination. It was observed that the effective annual doses were below the limit established by the norms, which can be inferred that the installation has been operating safely, without causing a radiological impact to the environment and individuals of the public

Relationship between kidney burden and radiation dose from chronic ingestion of U: Implications for radiation standards for the public

International Nuclear Information System (INIS)

Kocher, D.C.

1989-01-01

Metabolic models for U in adults recommended by Wrenn et al. (1985) and the International Commission on Radiological Protection (ICRP 1979a) were used to study the relationship between kidney burden and radiation dose from chronic ingestion of soluble 238U or natural U and whether current radiation standards for the public provide adequate protection against chemical toxicity from U in the kidney. We assumed that the threshold concentration for chemical toxicity is 1 microgram of U g-1 of kidney and that a safety factor of 10 should be applied in limiting kidney burdens for maximally exposed individuals in the general public. We found that a limit on annual effective dose equivalent of 1 mSv (0.1 rem) for chronic exposures of the public from all sources, as recommended by the ICRP (1985) and the National Council on Radiation Protection and Measurements (NCRP 1987), corresponds to concentrations of U in the kidney from chronic ingestion that exceed the assumed threshold for chemical toxicity of 1 microgram g-1 only for 238U using the metabolic model of the ICRP (1979a). However, using either metabolic model (ICRP 1979a; Wrenn et al. 1985), the predicted concentrations of U in the kidney exceeded the limit of 0.1 microgram g-1, based on the assumed safety factor for protection of the public, for both 238U and natural U. From these results, we concluded that chemical toxicity should be considered in developing health protection standards for the public for ingestion of soluble 238U or natural U. Environmental radiation standards for certain practices established by the U.S. Environmental Protection Agency and Nuclear Regulatory Commission (EPA 1987a, 1987b, 1987c, 1987d; NRC 1988a) are consistent with a limit on annual effective dose equivalent of 0.25 mSv (25 mrem) per practice. If the metabolic model of Wrenn et al. 27 references

The limiting dose rate and its importance in radiation protection

International Nuclear Information System (INIS)

Bakkiam, D.; Sonwani, Swetha; Arul Ananthakumar, A.; Mohankumar, Mary N.

2012-01-01

The concept of defining a low dose of ionizing radiation still remains unclear. Before attempting to define a low dose, it is more important to define a low-dose rate since effects at low dose-rates are different from those observed at higher dose-rates. Hence, it follows that low dose-rates rather than a low dose is an important criteria to determine radio-biological effects and risk factors i.e. stochastic health effects. Chromosomal aberrations induced by ionizing radiations are well fitted by quadratic model Y= áD + âD 2 + C with the linear coefficient of dose predominating for high LET radiations and low doses of low LET. At higher doses and dose rates of sparsely ionizing radiation, break pairs produced by inter-track action leads to the formation of exchange type aberrations and is dependent on dose rate. Whereas at lower doses and dose rates, intra-track action produces break pairs and resulting aberrations are in direct proportion to absorbed dose and independent of dose rate. The dose rate at which inter-track ceases to be observable and where intra-track action effectively becomes the sole contributor of lesion-pair formation is referred to as limiting dose rate (LDR). Once the LDR is reached further reduction in dose rates will not affect the slope of DR since breaks produced by independent charged particle tracks are widely separated in time to interact with each other for aberration yield. This linear dependency is also noticed for acute exposures at very low doses. Existing reports emphasizes the existence of LDR likely to be e6.3cGyh -1 . However no systematic studies have been conducted so far to determine LDR. In the present investigation DR curves were constructed for the dose rates 0.002 and 0.003 Gy/min and to define LDR at which a coefficient approaches zero. Extrapolation of limiting low dose rate data can be used to predict low dose effects regardless of dose rate and its definition ought to serve as a useful index for studies pertaining

Absorbed dose thresholds and absorbed dose rate limitations for studies of electron radiation effects on polyetherimides

Science.gov (United States)

Long, Edward R., Jr.; Long, Sheila Ann T.; Gray, Stephanie L.; Collins, William D.

1989-01-01

The threshold values of total absorbed dose for causing changes in tensile properties of a polyetherimide film and the limitations of the absorbed dose rate for accelerated-exposure evaluation of the effects of electron radiation in geosynchronous orbit were studied. Total absorbed doses from 1 kGy to 100 MGy and absorbed dose rates from 0.01 MGy/hr to 100 MGy/hr were investigated, where 1 Gy equals 100 rads. Total doses less than 2.5 MGy did not significantly change the tensile properties of the film whereas doses higher than 2.5 MGy significantly reduced elongation-to-failure. There was no measurable effect of the dose rate on the tensile properties for accelerated electron exposures.

The philosophy of dose limitation

International Nuclear Information System (INIS)

Recht, P.

1981-01-01

The evolution of concepts and terms appearing in the European Rules of 15 July 1980 is briefly described. After a period where ''tolerance doses'' represent definite limits which should be respected, appears the concept of a ''as low as possible'' and ''as low as practicable'' level. The hypothesis that any exposure represents a risk which should be avoided is taken into account in the later evolution. As a consequence one has to examine the advantages and disadvantages in other words to make a cost-benefit analysis. This evolution leads to the concepts of justification and optimization used at the present time. (author)

Statement from the 1983 meeting of the International Commission on Radiological Protection: annual limits for intakes (ALI) and derived air concentrations (DAC) for members of the public

International Nuclear Information System (INIS)

1983-01-01

The limitation of the committed effective dose equivalent for members of the public is sufficient to provide compliance over a lifetime with the limit for single organs, thus avoiding non-stochastic effects. Relative values for infants and adults of the committed dose equivalent in a number of tissues per unit intake for each of a few radionuclides have been given: the values for infants are just more than 1 up to 100 times greater than those for adult workers. In each of these cases the appropriate annual dose-equivalent limits recommended by the Commission for members of the public are 10 times less than the corresponding values for workers; the resulting ALI for infants aged six months will be smaller than the values given in ICRP Publication 30 for limiting stochastic effects in workers by factors that range from just more than 10 (for caesium-137) to 1,000 (for ingested plutonium-239). Intermediate factors would apply for older members of the public. The magnitude of the range emphasises the need to consider each situation carefully, with particular reference to children and women. (author)

Occupational dose constraint

International Nuclear Information System (INIS)

Heilbron Filho, Paulo Fernando Lavalle; Xavier, Ana Maria

2005-01-01

The revision process of the international radiological protection regulations has resulted in the adoption of new concepts, such as practice, intervention, avoidable and restriction of dose (dose constraint). The latter deserving of special mention since it may involve reducing a priori of the dose limits established both for the public and to individuals occupationally exposed, values that can be further reduced, depending on the application of the principle of optimization. This article aims to present, with clarity, from the criteria adopted to define dose constraint values to the public, a methodology to establish the dose constraint values for occupationally exposed individuals, as well as an example of the application of this methodology to the practice of industrial radiography

Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Jimenez, M.A., E-mail: majg@csn.es [Consejo de Seguridad Nuclear (CSN), Pedro Justo Dorado Dellmans 11, E-28040 Madrid (Spain); Martin-Valdepenas, J.M.; Garcia-Talavera, M.; Martin-Matarranz, J.L.; Salas, M.R.; Serrano, J.I.; Ramos, L.M. [Consejo de Seguridad Nuclear (CSN), Pedro Justo Dorado Dellmans 11, E-28040 Madrid (Spain)

2011-11-15

In the frame of an epidemiological study carried out in the influence areas around the Spanish nuclear facilities (ISCIII-CSN, 2009. Epidemiological Study of The Possible Effect of Ionizing Radiations Deriving from The Operation of Spanish Nuclear Fuel Cycle Facilities on The Health of The Population Living in Their Vicinity. Final report December 2009. Ministerio de Ciencia e Innovacion, Instituto de Salud Carlos III, Consejo de Seguridad Nuclear. Madrid. Available from: (http://www.csn.es/images/stories/actualidad{sub d}atos/especiales/epidemiologico/epidemiological{sub s}tudy.pdf)), annual effective doses to public have been assessed by the Spanish Nuclear Safety Council (CSN) for over 45 years using a retrospective realistic-dose methodology. These values are compared with data from natural radiation exposure. For the affected population, natural radiation effective doses are in average 2300 times higher than effective doses due to the operation of nuclear installations (nuclear power stations and fuel cycle facilities). When considering the impact on the whole Spanish population, effective doses attributable to nuclear facilities represent in average 3.5 x 10{sup -5} mSv/y, in contrast to 1.6 mSv/y from natural radiation or 1.3 mSv/y from medical exposures. - Highlights: > Most comprehensive dose assessment to public by nuclear facilities ever done in Spain. > Dose to public is dominated by liquid effluent pathways for the power stations. > Dose to public is dominated by Rn inhalation for milling and mining facilities. > Average annual doses to public in influence areas are negligible (10 {mu}Sv/y or less). > Doses from facilities average 3.5 x 10{sup -2} {mu}Sv/y per person onto whole Spanish population.

Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities

International Nuclear Information System (INIS)

Jimenez, M.A.; Martin-Valdepenas, J.M.; Garcia-Talavera, M.; Martin-Matarranz, J.L.; Salas, M.R.; Serrano, J.I.; Ramos, L.M.

2011-01-01

In the frame of an epidemiological study carried out in the influence areas around the Spanish nuclear facilities (ISCIII-CSN, 2009. Epidemiological Study of The Possible Effect of Ionizing Radiations Deriving from The Operation of Spanish Nuclear Fuel Cycle Facilities on The Health of The Population Living in Their Vicinity. Final report December 2009. Ministerio de Ciencia e Innovacion, Instituto de Salud Carlos III, Consejo de Seguridad Nuclear. Madrid. Available from: (http://www.csn.es/images/stories/actualidad_datos/especiales/epidemiologico/epidemiological_study.pdf)), annual effective doses to public have been assessed by the Spanish Nuclear Safety Council (CSN) for over 45 years using a retrospective realistic-dose methodology. These values are compared with data from natural radiation exposure. For the affected population, natural radiation effective doses are in average 2300 times higher than effective doses due to the operation of nuclear installations (nuclear power stations and fuel cycle facilities). When considering the impact on the whole Spanish population, effective doses attributable to nuclear facilities represent in average 3.5 x 10 -5 mSv/y, in contrast to 1.6 mSv/y from natural radiation or 1.3 mSv/y from medical exposures. - Highlights: → Most comprehensive dose assessment to public by nuclear facilities ever done in Spain. → Dose to public is dominated by liquid effluent pathways for the power stations. → Dose to public is dominated by Rn inhalation for milling and mining facilities. → Average annual doses to public in influence areas are negligible (10 μSv/y or less). → Doses from facilities average 3.5 x 10 -2 μSv/y per person onto whole Spanish population.

TLD personnel monitoring dose estimation- extending the upper limit of the dose range

International Nuclear Information System (INIS)

Popli, K.L.; Sathian, Deepa; Divakaran, T.; Massand, O.P.

2001-01-01

TLD personnel monitoring was introduced in the year 1975 in India and at present nearly 41,000 radiation workers are being monitored by 13 monitoring laboratories all over India. The BARC- TLD being used for personnel monitoring is based on CaSO 4 :Dy embedded in PTFE and semi-automatic TL reader using hot N 2 Gas for heating the dosimeters. This reader has the range to measure γ dose from ten μSv to 3 μSv and x-ray dose form 1 μ Sv to 0.3 Sv due to the higher sensitivity of CaSO 4 : Dy to lower energy photons (20keV-50 keV) generated by diagnostic x-ray units. The x-ray radiation workers are at present nearly 35% of the total radiation workers monitored and this number is expected to grow as more and more number of x-ray workers are covered under this service. The upper limit of the x-ray dose range of the instrument is 0.3 Sv, whereas in the past one year it has been observed that at least 25% of the total overexposures reported in case of x-ray workers have recorded the dose more than 0.3 Sv. This paper presents the technique developed to extend the upper limit of the range from 0.3 Sv to 1 Sv for x-rays and 10 Sv for γ rays

Present dose limits and their relation to radiosensitivity of different organs and tissues

International Nuclear Information System (INIS)

Anon.

1987-01-01

Dose equivalent limits in relation to dose thresholds are considered for injury of various tissues and organs to evaluate the protection agains non-stochastic irradiation effects by the existing system of dose limitation for radiotherapeutic personnel. Data on tissue radiosensitivity in relation to non-stochastic effects, obtained from radiotherapeutic experience, are presented. Dose threshold values, derived for patients, with a correction in the direction of increase, may be applied to conditions of occupational exposure except for bone marrow, gonads and eye lens, where threshold doses are lower

Measures associated with the dose limitation system at the TVO Power Company

International Nuclear Information System (INIS)

Ruuskanen, A.T.; Sundell, R.O.

1982-01-01

The paper discusses radiation protection practices at the TVO Power Company, which owns and operates two BWR units of Asea-Atom design at Olkiluoto, Finland. The installed electric power of each unit is 660MW. The full power operation of TVO I and TVO II began in 1979 and 1980, respectively. The dose limitation system calls for an organization which is responsible for radiation protection. This organization at the plant site is described. To limit doses a good knowledge of the work activities which cause doses is needed. There is a very up-to-date microprocessor-based work dosimetry system at the TVO power plant. The system provides a practicable means of measuring personal doses from various work activities. It also makes the allocation of radiation protection measures possible. The system and experience in applying it are discussed. The dose limitation system presupposes the realization of the optimization principle. The practice applied at TVO in order to limit internal contamination is presented. Owing to this practice, workers' internal doses have remained at a considerably low level. The paper discusses the ALARA values of different kinds of respiratory equipment. These values, which vary from 2x10 4 to 1x10 6 FIM/man.Sv (1 FIM=approx. US$ 0.22), can be used in the evaluation of different measures in avoiding internal doses. The operating policy of movable lead shields is presented. The ALARA value of this activity is evaluated to be about 5x10 4 FIM/man.Sv and on that basis it can be concluded that the use of movable lead shields is very efficient. The dose statistics for TVO's plant are presented. The doses have been less than 0.001 man.Sv/MW.a. Although the dose statistics for TVO are very good it is not realistic to consider solely the optimization aspect of radiation protection. The costs must also be kept in mind; these are presented in the paper. Problems in assessing the level of radiation protection practices on an annual basis are briefly discussed

Peak Dose Assessment for Proposed DOE-PPPO Authorized Limits

International Nuclear Information System (INIS)

Maldonado, Delis

2012-01-01

The Oak Ridge Institute for Science and Education (ORISE), a U.S. Department of Energy (DOE) prime contractor, was contracted by the DOE Portsmouth/Paducah Project Office (DOE-PPPO) to conduct a peak dose assessment in support of the Authorized Limits Request for Solid Waste Disposal at Landfill C-746-U at the Paducah Gaseous Diffusion Plant (DOE-PPPO 2011a). The peak doses were calculated based on the DOE-PPPO Proposed Single Radionuclides Soil Guidelines and the DOE-PPPO Proposed Authorized Limits (AL) Volumetric Concentrations available in DOE-PPPO 2011a. This work is provided as an appendix to the Dose Modeling Evaluations and Technical Support Document for the Authorized Limits Request for the C-746-U Landfill at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky (ORISE 2012). The receptors evaluated in ORISE 2012 were selected by the DOE-PPPO for the additional peak dose evaluations. These receptors included a Landfill Worker, Trespasser, Resident Farmer (onsite), Resident Gardener, Recreational User, Outdoor Worker and an Offsite Resident Farmer. The RESRAD (Version 6.5) and RESRAD-OFFSITE (Version 2.5) computer codes were used for the peak dose assessments. Deterministic peak dose assessments were performed for all the receptors and a probabilistic dose assessment was performed only for the Offsite Resident Farmer at the request of the DOE-PPPO. In a deterministic analysis, a single input value results in a single output value. In other words, a deterministic analysis uses single parameter values for every variable in the code. By contrast, a probabilistic approach assigns parameter ranges to certain variables, and the code randomly selects the values for each variable from the parameter range each time it calculates the dose (NRC 2006). The receptor scenarios, computer codes and parameter input files were previously used in ORISE 2012. A few modifications were made to the parameter input files as appropriate for this effort. Some of these changes

Estimation of the fetal dose by dose measurement during an irradiation of a parotid tumor; Estimation de la dose foetale par mesure de dose lors d'une irradiation d'une tumeur de la parotide

Energy Technology Data Exchange (ETDEWEB)

Marchesi, V.; Graff-Cailleaud, P.; Peiffert, D. [Centre Alexis-Vautrin, 54 - Vandoeuvre-les-Nancy (France); Noel, A. [Institut National Polytechnique de Lorraine, CRAN CNRS UMR-7039, 54 - Vandoeuvre-les-Nancy (France)

2006-11-15

The irradiation of a five months pregnant patient has been made for a right parotid attack. In conformation with the legislative texts relative to radiation protection ( publication 84 of the ICRP) an estimation of the dose received for the fetus has been led by dose measurement on phantom. With the dose limit ( 100 mGy) recommended in the publication 84 of the ICRP neither modification of the treatment nor abortion was necessary. (N.C.)

Evaluation of the effective equivalent dose in the general public due to the discharge of uranium in groundwater

International Nuclear Information System (INIS)

Gordon, A.M.P.L.; Jacomino, V.M.F.

1989-12-01

Some facilities available at IPEN-CNEN/SP may discharge uranium in their liquid effluents. The uranium contents of these effluents are analyzed by photometry or fluorimetry, and according to the results obtained a decision is made, by the Environmental Monitoring Division, upon their discharge to the environment. In 1988 a total activity of 3.66x10 9 Bq of uranium was discharge in a volume of approximately 30 m 3 . The effective equivalent dose in the general public was evaluated by making a conservative assumption that all the liquid effluents containing uranium are discharged directly to the soil reaching the groundwater. The dose calculation was carried out by using a generic model which described the transport of radionuclides in the groundwater. In order to be conservative it was also assumed that the critical pathway is the direct in gestion of water through hypothetical wells around the Institute. Conservative assumptions were also made in the characterization of the local aquifer parameters such as vertical and longitudinal dispersivity, effective porosity of the soil, hydraulic conductivity etc., in roder to overestimate the effective equivalent dose. The result obtained, of 5.3x10 -10 mSv/a is far below the dose limit for the public adopted by the Radiological Protection Board. The derived limit for the discharge was also evaluated, using the same model, giving a result of 3.6x10 13 Bq/a. (author) [pt

Impact of reduced dose limits on NRC licensed activities. Major issues in the implementation of ICRP/NCRP dose limit recommendations: Final report

International Nuclear Information System (INIS)

Meinhold, C.B.

1995-05-01

This report summarizes information required to estimate, at least qualitatively, the potential impacts of reducing occupational dose limits below those given in 10 CFR 20 (Revised). For this study, a questionnaire was developed and widely distributed to the radiation protection community. The resulting data together with data from existing surveys and sources were used to estimate the impact of three dose-limit options; 10 mSv yr -1 (1 rem yr -1 ), 20 mSv yr -1 (2 rem yr -1 ), and a combination of an annual limit of 50 mSv yr -1 (5 rem yr -1 ) coupled with a cumulative limit, in rem, equal to age in years. Due to the somewhat small number of responses and the lack of data in some specific areas, a working committee of radiation protection experts from a variety of licensees was employed to ensure the exposure data were representative. The following overall conclusions were reached: (1) although 10 mSv yr -1 is a reasonable limit for many licensees, such a limit could be extraordinarily difficult to achieve and potentially destructive to the continued operation of some licensees, such as nuclear power, fuel fabrication, and medicine; (2) twenty mSv yr -1 as a limit is possible for some of these groups, but for others it would prove difficult. (3) fifty mSv yr -1 and age in 10s of mSv appear reasonable for all licensees, both in terms of the lifetime risk of cancer and severe genetic effects to the most highly exposed workers, and the practicality of operation

Radiation protection recommendations on dose limits: the role of the NCRP and the ICRP and future developments

International Nuclear Information System (INIS)

Sinclair, Warren K.

1995-01-01

The purpose of this paper is to review the role of the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP) in making recommendations on dose limits for ionizing radiation exposure for workers and for the public. The text describes the new limits for workers and public recommended by ICRP in 1991 and NCRP in 1993 and the composition of the radiation health detriment on which they are based. The main component of this detriment is the risk of radiation induced cancer which is now estimated to be about three times greater than a decade or so earlier. Uncertainties in these risk estimates are discussed. Some special radiation protection problems, such as those for the embryo or fetus are described. The article also addresses future progress in radiation protection particularly with regard to future improvements in the scientific basis for radiation protection recommendations

Public doses estimation based on effluents data and direct measurements of Tritium in environmental samples at Cernavoda

International Nuclear Information System (INIS)

Bobric, E.; Popescu, I.; Simionov, V.

2002-01-01

The release of any potential radioactive pollutant to the environment during routine operation of a Nuclear Power Plant should be the subject of appropriate controls and assessments. The layout of the Candu reactor and the design of its systems ensure that the radioactive waste quantities are minimized, but small amounts of radioisotopes are continuously discharged at very low concentrations through gaseous and liquid effluents. Radioprotection of the public is based on the principles recommended by ICRP, the protection being mainly achieved by control of the sources of exposure. Source monitoring provide a means of assessing the radiation exposure of population groups, critical groups and individual members of the public. The assessed doses are used to demonstrate the compliance with authorized dose limits - 1 mSv / year in our case - but can also be used for optimization purposes

Classification of radiation effects for dose limitation purposes: history, current situation and future prospects

Science.gov (United States)

Hamada, Nobuyuki; Fujimichi, Yuki

2014-01-01

Radiation exposure causes cancer and non-cancer health effects, each of which differs greatly in the shape of the dose–response curve, latency, persistency, recurrence, curability, fatality and impact on quality of life. In recent decades, for dose limitation purposes, the International Commission on Radiological Protection has divided such diverse effects into tissue reactions (formerly termed non-stochastic and deterministic effects) and stochastic effects. On the one hand, effective dose limits aim to reduce the risks of stochastic effects (cancer/heritable effects) and are based on the detriment-adjusted nominal risk coefficients, assuming a linear-non-threshold dose response and a dose and dose rate effectiveness factor of 2. On the other hand, equivalent dose limits aim to avoid tissue reactions (vision-impairing cataracts and cosmetically unacceptable non-cancer skin changes) and are based on a threshold dose. However, the boundary between these two categories is becoming vague. Thus, we review the changes in radiation effect classification, dose limitation concepts, and the definition of detriment and threshold. Then, the current situation is overviewed focusing on (i) stochastic effects with a threshold, (ii) tissue reactions without a threshold, (iii) target organs/tissues for circulatory disease, (iv) dose levels for limitation of cancer risks vs prevention of non-life-threatening tissue reactions vs prevention of life-threatening tissue reactions, (v) mortality or incidence of thyroid cancer, and (vi) the detriment for tissue reactions. For future discussion, one approach is suggested that classifies radiation effects according to whether effects are life threatening, and radiobiological research needs are also briefly discussed. PMID:24794798

Building credibility in public studies: Lessons learned from the Hanford environmental Dose Reconstruction project may apply to all public studies

International Nuclear Information System (INIS)

Till, J.E.

1995-01-01

This article describes the process by which the author came to recognize the importance of openness to the public in environmental studies, during the Hanford Environmental Dose Reconstruction Project. Using the Dose reconstruction public involvement, the article goes on to describe a general guide to the construction of a new, positive framework for conducting future public studies. The steps include the following: putting the public in the study; building credibility into a public study (1 -search for proof in historical records; 2-define the domain and the exposed population; 3-characterize the material released; 4-identify key materials, pathways and receptors; 5-encouraging public participation; 6 -explaining the meaning of the results) and reconciling scientific and public issues

Building credibility in public studies: Lessons learned from the Hanford environmental Dose Reconstruction project may apply to all public studies

Energy Technology Data Exchange (ETDEWEB)

Till, J.E. [Radiological Assessment Corp., Neeses, SC (United States)

1995-09-01

This article describes the process by which the author came to recognize the importance of openness to the public in environmental studies, during the Hanford Environmental Dose Reconstruction Project. Using the Dose reconstruction public involvement, the article goes on to describe a general guide to the construction of a new, positive framework for conducting future public studies. The steps include the following: putting the public in the study; building credibility into a public study (1 -search for proof in historical records; 2-define the domain and the exposed population; 3-characterize the material released; 4-identify key materials, pathways and receptors; 5-encouraging public participation; 6 -explaining the meaning of the results) and reconciling scientific and public issues.

Impact of reduced dose limits on NRC licensed activities. Major issues in the implementation of ICRP/NCRP dose limit recommendations: Final report

Energy Technology Data Exchange (ETDEWEB)

Meinhold, C.B. [Brookhaven National Lab., Upton, NY (United States)

1995-05-01

This report summarizes information required to estimate, at least qualitatively, the potential impacts of reducing occupational dose limits below those given in 10 CFR 20 (Revised). For this study, a questionnaire was developed and widely distributed to the radiation protection community. The resulting data together with data from existing surveys and sources were used to estimate the impact of three dose-limit options; 10 mSv yr{sup {minus}1} (1 rem yr{sup {minus}1}), 20 mSv yr{sup {minus}1} (2 rem yr{sup {minus}1}), and a combination of an annual limit of 50 mSv yr{sup {minus}1} (5 rem yr{sup {minus}1}) coupled with a cumulative limit, in rem, equal to age in years. Due to the somewhat small number of responses and the lack of data in some specific areas, a working committee of radiation protection experts from a variety of licensees was employed to ensure the exposure data were representative. The following overall conclusions were reached: (1) although 10 mSv yr{sup {minus}1} is a reasonable limit for many licensees, such a limit could be extraordinarily difficult to achieve and potentially destructive to the continued operation of some licensees, such as nuclear power, fuel fabrication, and medicine; (2) twenty mSv yr{sup {minus}1} as a limit is possible for some of these groups, but for others it would prove difficult. (3) fifty mSv yr{sup {minus}1} and age in 10s of mSv appear reasonable for all licensees, both in terms of the lifetime risk of cancer and severe genetic effects to the most highly exposed workers, and the practicality of operation.

Decreasing Irradiated Rat Lung Volume Changes Dose-Limiting Toxicity From Early to Late Effects

Energy Technology Data Exchange (ETDEWEB)

Veen, Sonja J. van der; Faber, Hette; Ghobadi, Ghazaleh [Department of Cell Biology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands); Department of Radiation Oncology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands); Brandenburg, Sytze [KVI Center for Advanced Radiation Research, University of Groningen, Groningen (Netherlands); Langendijk, Johannes A. [Department of Radiation Oncology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands); Coppes, Robert P. [Department of Cell Biology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands); Department of Radiation Oncology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands); Luijk, Peter van, E-mail: p.van.luijk@umcg.nl [Department of Radiation Oncology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands)

2016-01-01

Purpose: Technological developments in radiation therapy result in smaller irradiated volumes of normal tissue. Because the risk of radiation therapy-induced toxicity generally depends on irradiated volume, changing volume could change the dose-limiting toxicity of a treatment. Recently, in our rat model, we found that early radiation-induced lung dysfunction (RILD) was closely related to irradiated volume dependent vascular remodeling besides inflammation. The exact relationship between early and late RILD is still unknown. Therefore, in this preclinical study we investigated the dose-volume relationship of late RILD, assessed its dependence on early and late pathologies and studied if decreasing irradiated volume changed the dose-limiting toxicity. Methods and Materials: A volume of 25%, 32%, 50%, 63%, 88%, or 100% of the rat lung was irradiated using protons. Until 26 weeks after irradiation, respiratory rates were measured. Macrovascular remodeling, pulmonary inflammation, and fibrosis were assessed at 26 weeks after irradiation. For all endpoints dose-volume response curves were made. These results were compared to our previously published early lung effects. Results: Early vascular remodeling and inflammation correlated significantly with early RILD. Late RILD correlated with inflammation and fibrosis, but not with vascular remodeling. In contrast to the early effects, late vascular remodeling, inflammation and fibrosis showed a primarily dose but not volume dependence. Comparison of respiratory rate increases early and late after irradiation for the different dose-distributions indicated that with decreasing irradiated volumes, the dose-limiting toxicity changed from early to late RILD. Conclusions: In our rat model, different pathologies underlie early and late RILD with different dose-volume dependencies. Consequently, the dose-limiting toxicity changed from early to late dysfunction when the irradiated volume was reduced. In patients, early and late

Practical low dose limits for passive personal dosemeters and the implications for uncertainties close to the limit of detection

International Nuclear Information System (INIS)

Gilvin, P. J.; Perks, C. A.

2011-01-01

Recent years have seen the increasing use of passive dosemeters that have high sensitivities and, in laboratory conditions, detection limits of <10 μSv. However, in real operational use the detection limits will be markedly higher, because a large fraction of the accrued dose will be due to natural background, and this must be subtracted in order to obtain the desired occupational dose. No matter how well known the natural background is, the measurement uncertainty on doses of a few tens of microsieverts will be large. Individual monitoring services need to recognise this and manage the expectations of their clients by providing sufficient information. (authors)

Radiation doses to members of the public near to Sellafield, Cumbria, from liquid discharges 1952-98.

Science.gov (United States)

Jackson, D; Lambers, B; Gray, J

2000-06-01

Liquid wastes containing low levels of radioactivity have been discharged to the Irish Sea from the nuclear fuel reprocessing site at Sellafield since operations began in the early 1950s, and monitoring of radioactivity in foodstuffs has been undertaken over many years. Based on the best available monitoring data, supplemented by modelled values where necessary, doses to local critical groups have been reassessed using the most recent dosimetry. Contemporary habits data have been used where available, again supplemented by assumed habits where necessary. During the 1950s and 1960s the highest doses were received by individuals consuming Cumbrian Porphyra as laverbread, and peak doses around 0.8 to 1.0 mSv year(-1) have been estimated. During the 1970s and 1980s the critical exposure group switched to consumers of local fish and shellfish, with peak doses possibly reaching 2.5 to 3.0 mSv year(-1). Latterly, doses to all marine-related groups have declined to less than 150 to 200 microSv year(-1). At all times, doses have been within the appropriate limits set for members of the public.

Methods for estimation of internal dose of the public from dietary

International Nuclear Information System (INIS)

Zhu Hongda

1987-01-01

Following the issue of its Publication 26, ICRP has successively published its Publication 30 to meet the great changes and improvements made in the Basic Recommendations since July of 1979. In Part 1 of Publcation 30, ICRP recommended a new method for internal dose estimation and pressented some important data. In this report, comparison is made among methods for estimation of internal dose for the public from dietary. They include: (1) the new method suggested by ICRP; (2) the simple and convenient method using transfer factors under equilibrium conditions; (3) the methods based on the similarities of several radionuclides to their chemical analogs. It is concluded that the first method is better than the others and should be used from now on

Limits of dose escalation in lung cancer: a dose-volume histogram analysis comparing coplanar and non-coplanar techniques

Energy Technology Data Exchange (ETDEWEB)

Derycke, S; Van Duyse, B; Schelfhout, J; De Neve, W

1995-12-01

To evaluate the feasibility of dose escalation in radiotherapy of inoperable lung cancer, a dose-volume histogram analysis was performed comparing standard coplanar (2D) with non-coplanar (3D) beam arrangements on a non-selected group of 20 patients planned by Sherouse`s GRATISTM 3D-planning system. Serial CT-scanning was performed and 2 Target Volumes (Tvs) were defined. Gross Tumor Volume (GTV) defined a high-dose Target Volume (TV-1). GTV plus location of node stations with > 10% probability of invasion (Minet et al.) defined an intermediate-dose Target Volume (TV-2). However, nodal regions which are incompatible with cure were excluded from TV-2. These are ATS-regions 1, 8, 9 and 14 all left and right as well as heterolateral regions. For 3D-planning, Beam`s Eye View selected (by an experienced planner) beam arrangements were optimised using Superdot, a method of target dose-gradient annihilation developed by Sherouse. A second 3D-planning was performed using 4 beam incidences with maximal angular separation. The linac`s isocenter for the optimal arrangement was located at the geometrical center of gravity of a tetraheder, the tetraheder`s comers being the consecutive positions of the virtual source. This ideal beam arrangement was approximated as close as possible, taking into account technical limitations (patient-couch-gantry collisions). Criteria for tolerance were met if no points inside the spinal cord exceeded 50 Gy and if at least 50% of the lung volume received less than 20Gy. If dose regions below 50 Gy were judged acceptable at TV-2, 2D- as well as 3D-plans allow safe escalation to 80 Gy at TV-1. When TV-2 needed to be encompassed by isodose surfaces exceeding 50Gy, 3D-plans were necessary to limit dose at the spinal cord below tolerance. For large TVs dose is limited by lung tolerance for 3D-plans. An analysis (including NTCP-TCP as cost functions) of rival 3D-plans is being performed.

The possibility of the dose limitation system application non-ionizing radiation protection

International Nuclear Information System (INIS)

Ranisavljevic, M., Markovic, S.

1997-01-01

Modern conception of the ionizing radiation protection is based on Dose Limitation System. In the base of every human decision lies compromise. Balance between positive and negative factors, benefit and detriment, profit and expense includes the decision about possibilities for realization any defined radiation practice. The optimal option for the given value of the varying parameter gives the maximum benefit and the minimum detriment. In radiation protection field, detriment is related with human health or expenses, and varying parameter is level of radiation protection (for example dimensions of the installed shielding). The problem lies in fact that for the given value of the varying shielding parameter the maximum benefit and the minimum detriment are not achievable simultaneously because the greater benefit includes the greater expense. The problems which have to be solved because of introducing Dose Limitation System, in regard to create Modified Dose Limitation System, are presented. (author)

Collective dose, conceptual basis and practical applications

International Nuclear Information System (INIS)

Bonka, H.

1985-01-01

In the ICRP Publications no. 22(1973) and no. 26(1977), the ICRP recommends that the maximum permissible whole-body dose by kept below the dose limits corresponding to the sum of all effective dose equivalents of the persons concerned, i.e. the collective dose. The effective dose equivalent is recommended by the ICRP for use as a new quantity for evaluating the stochastic radiation dose for individual persons. Examples are given by the author explaining cost-benefit analyses according to ICRP recommendations, especially discussing the definition of optimum local dose limits with regard to shielding design in nuclear installations. (DG) [de

Implications for Occupational Radiation Protection of the New Dose Limit for the Lens of the Eye. Interim Guidance for Use and Comment

International Nuclear Information System (INIS)

2013-12-01

The IAEA Safety Requirements Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, was approved by the IAEA Board of Governors at its meeting in September 2011 and published in November 2011. The equivalent dose limit for the lens of the eye for occupational exposure in planned exposure situations was reduced from 150 mSv per year to 20 mSv per year, averaged over defined periods of five years, with no annual dose in a single year exceeding 50 mSv. This reduction in the dose limit for the lens of the eye follows the recommendation of the International Commission on Radiological Protection (ICRP) in its statement on tissue reactions on 21 April 2011. At the time when the draft General Safety Requirements (GSR) Part 3 was approved by the Commission on Safety Standards, the Secretariat was asked to develop guidance as early as possible to assist Member States in the observance of the new dose limit. In the longer term, the guidance provided in this TECDOC will form the basis for the consensus guidance in relation to the new dose limit for the lens of the eye that is to be provided in two safety guides currently being developed, Occupational Radiation Protection and Radiation Safety in the Medical Uses of Ionizing Radiation. It is expected that these will be published in 2015-2016. It is recognized that guidance material is required before the two safety guides are finalized in order to give Member States the opportunity to put appropriate actions in place and to plan for the introduction of the new dose limit for the lens of the eye. The purpose of the current publication is to provide advice on the implications for occupational radiation protection of the new dose limit for the lens of the eye and to allow comment on detailed recommendations that may be incorporated into the safety guides

EMP Attachment 3 DOE-SC PNNL Site Dose Assessment Guidance

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F.

2011-12-21

This Dose Assessment Guidance (DAG) describes methods to use to determine the Maximally-Exposed Individual (MEI) location and to estimate dose impact to that individual under the U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest National Laboratory (PNNL) Site Environmental Monitoring Plan (EMP). This guidance applies to public dose from radioactive material releases to the air from PNNL Site operations. This document is an attachment to the Pacific Northwest National Laboratory (PNNL) Environmental Monitoring Plan (EMP) and describes dose assessment guidance for radiological air emissions. The impact of radiological air emissions from the U.S. Department of Energy Office of Science (DOE-SC) PNNL Site is indicated by dose estimates to a maximally exposed member of the public, referred to as the maximally exposed individual (MEI). Reporting requirements associated with dose to members of the public from radiological air emissions are in 40 CFR Part 61.94, WAC 246-247-080, and DOE Order 458.1. The DOE Order and state standards for dose from radioactive air emissions are consistent with U.S. Environmental Protection Agency (EPA) dose standards in 40 CFR 61.92 (i.e., 10 mrem/yr to a MEI). Despite the fact that the current Contract Requirements Document (CRD) for the DOE-SC PNNL Site operations does not include the requirement to meet DOE CRD 458.1, paragraph 2.b, public dose limits, the DOE dose limits would be met when EPA limits are met.

Dose limits and licensing requirements for the limitation of the emission of radioactive materials from nuclear power stations in the FRG and the USA

Energy Technology Data Exchange (ETDEWEB)

Schwibach, J; Huber, O

1975-08-01

In licensing the operation of nuclear power plants in the FRG and USA, particular limitations of the release of radioactive materials in the air and water are layed down to correspond to the protective laws of radiation and environmental protection. The first limiting recommendations for the removal of radioactive waste waters were worked out in 1965 in the FRG and in 1968/69 for the removal of radioactive exhaust air of nuclear power plants. Based on this, in 1975 these relevant regulations were included in the draft of the new radiation protection specification. In 1971, these type of guidelines were put to discussion in the USA and were dismissed in 1975 in a licensing regulation of the NRC. These regulations or guidelines differ in their various dose limits. For example, the German dose limits of 30 mrem/a whole body dose for radioactive materials in the exhaust air of nuclear power plants and of 90 mrem/a for the thyroid dose through radioiodine via the exposure exhaust air-pasture-cow-milk-infant are often compared to the American dose limits of 5 mrem/a whole body dose and 15 mrem/a skin dose as well as 15 mrem/a thyroid dose. Such a numerical comparison is, howewer, wrong. The dose limits used in the FRG are, e.g., not to be exceeded. Furthermore, in the FRG, all contributions to be calculated on one site are to be considered. In the USA, the corresponding values are only valid for actual exposure paths due to the emission of a power reactor. They can be multiply exceeded. Thus the German licensing practise is clearly more restrictive.

Age-dependent dose factors and dose limits of annual radioactivity uptake with unsealed radioactive substances by occupationally exposed persons

International Nuclear Information System (INIS)

Kaul, A.; Nosske, D; Elsasser, U; Roedler, H.D.; Henrichs, K.

1986-01-01

The dose factors have been calculated on the basis of the ICRP models for dosimetric and metabolistic assessment, and are laid open in accordance with Annex XI ( to sec. 45 sub-section (2)) of the amended version of the Radiation Protection Ordinance. The contribution in hand explains the scientific fundamentals and results of the calculations of dose factors relating to inhalation and ingestion of unsealed radioactive substances by adult reference man, and age-dependent factors calculated for children and adolescents. Further, annual limits of uptake by occupationally exposed persons, as calculated on the basis of primary dose limits pursunant to the draft amendment presented by the Federal Interior Minister, are compared with relevant data given by the ICRP and EC institutions. (orig./DG) [de

The cost of occupational dose

International Nuclear Information System (INIS)

Fleishman, A.B.; Clark, M.J.

1980-01-01

The optimization of radiological protection will routinely involve the balancing of public and occupational exposure, particularly within the nuclear fuel cycle. For example the reduction of public exposure from an effluent stream could lead to increases in occupational exposure from treatment, storage and disposal operations. A methodology is propased for the estimation of the cost of occupational exposure in the UK (Pound man-Sv -1 ) based on valuations of changes in risk. A variable value for the cost of the occupational man-Sv is obtained depending on per caput dose levels. The values at particular per caput dose levels are different for occupational workers and the general public, because of different demography and assumptions on risk perception and aversion. They are however approximately the same when the per caput doses are expressed as percentages of the dose limits for workers and the general public respectively. An example of the application of the derived cost of the occupational man-Sv to an optimisation problem is given. (author)

Public effective doses from environmental natural gamma exposures indoors and outdoors in Iran

International Nuclear Information System (INIS)

Sohrabi, Mehdi; Roositalab, Jalil; Mohammadi, Jahangir

2015-01-01

The effective doses of public in Iran due to external gamma exposures from terrestrial radionuclides and from cosmic radiation indoors and outdoors of normal natural background radiation areas were determined by measurements and by calculations. For direct measurements, three measurement methods were used including a NaI(TI) scintillation survey meter for preliminary screening, a pressurised ionising chamber for more precise measurements and early warning measurement equipment systems. Measurements were carried out in a large number of locations indoors and outdoors ∼1000 houses selected randomly in 36 large cities of Iran. The external gamma doses of public from living indoors and outdoors were also calculated based on the radioactivity measurements of samples taken from soil and building materials by gamma spectrometry using a high-resolution HPGe system. The national mean background gamma dose rates in air indoors and outdoors based on measurements are 126.9±24.3 and 111.7±17.72 nGy h -1 , respectively. When the contribution from cosmic rays was excluded, the values indoors and outdoors are 109.2±20.2 and 70.2±20.59.4 nGy h -1 , respectively. The dose rates determined for indoors and outdoors by calculations are 101.5±9.2 and 72.2±9.4 nGy h -1 , respectively, which are in good agreement with directly measured dose rates within statistical variations. By considering a population-weighted mean for terrestrial radiation, the ratio of indoor to outdoor dose rates is 1.55. The mean annual effective dose of each individual member of the public from terrestrial radionuclides and cosmic radiation, indoors and outdoors, is 0.86±0.16 mSv y -1 by measurements and 0.8±0.2 mSv y -1 by calculations. The results of this national survey of public annual effective doses from national natural background external gamma radiation determined by measurements and calculations indoors and outdoors of 1000 houses in 36 cities of Iran are presented and discussed. (authors)

Patient dose rate: An ultimate limit for spatial and density resolution of scanning systems

International Nuclear Information System (INIS)

Kowalski, G.; Wagner, W.

1979-01-01

In X-ray scanning systems, picture quality of the reconstructed slices is limited to a maximum spatial as well as density resolution by the applied radiation dose. Density resolution can be improved in proportion to the root of the patient dose, whereas a doubled spatial resolving power requires an eight times higher patient dose, assuming a fixed slice thickness. Only a careful trade-off between the applied patient dose, density resolution and spatial resolution yields a maximal diagnostic value for the physician. Specifications of a scanning system have to take into account these ultimate restrictions, so that picture quality really is limited by the patient's dose rather than by technical constraints. In addition a method is given by which the applied dose can be reduced by focusing the main intensity onto the region of interest, in case that region is known a priori. (orig.) [de

Age-dependent doses to members of the public from intake of radionuclides: Pt. 5. Compilation of ingestion and inhalation dose coefficients

International Nuclear Information System (INIS)

1996-01-01

The present report is a compilation of age-dependent committed effective dose coefficients for ingestion and inhalation of radionuclides of the 31 elements covered in previous CRP Publications. The biokinetic models for adults given in ICRP Publication 30 are applied to calculate these dose coefficients, except that age-specific excretion rates are used and increased gastrointestinal absorption in infants is assurred. Changes in body mass, and tissue geometry in children are also taken into account. (UK)

Limited Releases of Krsko NPP

International Nuclear Information System (INIS)

Breznik, B.; Kovac, A.

2001-01-01

Full text: Krsko Nuclear Power Plant is about 700 MW Pressurised Water Reactor plant located in Slovenia close to the border with Croatia. The authorised limit for the radioactive releases is basically set to 50 μSv effective dose per year to the members of the public. There is also additional limitation of total activities released in a year and concentration. The poster presents the effluents of the year 2000 and evaluated dose referring to the limits and to the natural and other sources of radiation around the plant. (author)

User Guide for GoldSim Model to Calculate PA/CA Doses and Limits

Energy Technology Data Exchange (ETDEWEB)

Smith, F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-10-31

A model to calculate doses for solid waste disposal at the Savannah River Site (SRS) and corresponding disposal limits has been developed using the GoldSim commercial software. The model implements the dose calculations documented in SRNL-STI-2015-00056, Rev. 0 “Dose Calculation Methodology and Data for Solid Waste Performance Assessment (PA) and Composite Analysis (CA) at the Savannah River Site”.

Environmental aspects and public exposure doses of airborne radioactive effluents from a PWR-power plant

International Nuclear Information System (INIS)

Song Miaofa; Zhang Jin; Fu Rongchu; Hu Yinxiu

1989-04-01

It is estimated that the environmental aspects and public exposure doses of airborne radioactive effluents from a imaginary 0.3 GW PWR-power plant which sited on the site of a large coalfired power plant estimated before. The major contributor to public exposure is found to be the release of 14 C and the critical pathway is food ingestion. A maximum annual individual body effective dose equivalent of 7.112 x 10 -6 Sv · (GW · a) -1 is found at the point of 0.5 km southeast of the source. The collective dose equivalent in the area around the plant within a radius of 100 km is to be 0.5974 man-Sv · a) -1 . Both maximum individual and collective effective dose equivalents of the PWR-power plant are much lower than those of the coal-fired one. If the ash emission ratio of the latter decreases from 24.6% to 1%, public exposure doses of the two plants would be nearly equal

Evaluation of doses received by personnel occupationally exposed based on the dose limits established in European Directive 96/26. Reclassification of personnel

International Nuclear Information System (INIS)

Prieto, C.; Espana, M.L.; Perez, L.; Tomasi, L.; Lopez Franco, P.

1997-01-01

The recommendations of ICRP-60 of 1990 provide the basis of the European Directive 96/26/Euratom in which new dose limits of radiation for workers have been established. These new dose limits assume important reductions compared to the previous limits, which are still in force in Spain, and might entail the reclassification of some of these workers. In the present work it is shown that the majority of the workers exposed to areas under our responsibility could be classified under Category B

User Guide for GoldSim Model to Calculate PA/CA Doses and Limits

International Nuclear Information System (INIS)

Smith, F.

2016-01-01

A model to calculate doses for solid waste disposal at the Savannah River Site (SRS) and corresponding disposal limits has been developed using the GoldSim commercial software. The model implements the dose calculations documented in SRNL-STI-2015-00056, Rev. 0 ''Dose Calculation Methodology and Data for Solid Waste Performance Assessment (PA) and Composite Analysis (CA) at the Savannah River Site''.

Systematic study on the radiation exposure of flora and fauna in case of compliance with the dose limits of the StrlSchV (radiation protection regulation) for men. Final report

International Nuclear Information System (INIS)

Kueppers, Christian; Ustohalova, Veronika; Ulanovsky, Alexander

2012-01-01

Dose limits for members of the public exposed to the discharge of radioactive substances into the air or water bodies are defined in the German Radiation Protection Ordinance. This study tested whether non-human species are protected within the human dose limits for all 750 radionuclides as compared to a set of reference biota. External and, where possible, internal doses were calculated for the reference biota. In addition new exposure pathways such as submersion and inhalation (for rat and deer) were incorporated. The upper limit as ordered for adequate biota protection is 10 μGy/h. This study found that radionuclide discharges into the air never exceeded the reference dose rate limit. However, violations were detected for discharges of some very short-lived radionuclides into freshwater or seawater, if the maximum water contamination is assumed. Protection of non-human species is guaranteed for more realistic emission and immission situations. This means that damage to populations living in small water volumes cannot be excluded solely on the basis of regulations for the human dose limit. Therefore, it is necessary to judge the individual case in very unfavourable immission situations. (orig.)

Value of public health and safety actions and radiation dose avoided

Energy Technology Data Exchange (ETDEWEB)

Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1994-05-01

The values judged best to reflect the willingness of society to pay for the avoidance or reduction of risk were deduced from studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-risk compensation, consumer behavior (market) studies, and willingness-to-pay surveys. The results ranged from $1,400,000 to $2,700,000 per life saved. Applying the mean of these values ($2,100,000) and the latest risk per unit dose coefficients used by the ICRP (1991), which take into account risks to the general public, including genetic effects and nonfatal cancers, yields a value of dose avoided of $750 to $1,500 per person-cSv for public exposures. The lower value applies if adjustments are made for years of life lost per fatality. A nominal value of $1,000 per person-cSv seems appropriate in light of the many uncertainties involved in deducing these values. These values are consistent with values recommended by several European countries for individual doses in the region of 1 mSv/y (100 mrem/y). Below this dose rate, most countries have values a factor of 7 to 10 lower, based on the assumption that society is less concerned with fatality risks below about 10{sup {minus}4}/y.

Value of public health and safety actions and radiation dose avoided

International Nuclear Information System (INIS)

Baum, J.W.

1994-05-01

The values judged best to reflect the willingness of society to pay for the avoidance or reduction of risk were deduced from studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-risk compensation, consumer behavior (market) studies, and willingness-to-pay surveys. The results ranged from $1,400,000 to $2,700,000 per life saved. Applying the mean of these values ($2,100,000) and the latest risk per unit dose coefficients used by the ICRP (1991), which take into account risks to the general public, including genetic effects and nonfatal cancers, yields a value of dose avoided of $750 to $1,500 per person-cSv for public exposures. The lower value applies if adjustments are made for years of life lost per fatality. A nominal value of $1,000 per person-cSv seems appropriate in light of the many uncertainties involved in deducing these values. These values are consistent with values recommended by several European countries for individual doses in the region of 1 mSv/y (100 mrem/y). Below this dose rate, most countries have values a factor of 7 to 10 lower, based on the assumption that society is less concerned with fatality risks below about 10 -4 /y

Evolution of authorised limits for environmental releases from nuclear facilities in India

International Nuclear Information System (INIS)

Subramanian, Chitra; Narayanan, K.K.; Sharma, R.M.

2002-01-01

Full text: The controlled environmental releases of radioactive effluents from any nuclear facility is primarily based on the effective dose limits for the general public, recommended by the international commission on radiation protection (ICRP). To meet the dose limit criteria for members of the public, regulatory-limits are set for the discharges of radioactive effluents from nuclear facilities, which are known as the authorised limits (ALs). The paper presents the evolution of ALs in India applicable to nuclear power plant sites, starting from Tarapur Atomic Power Station (TAPS) commissioned in 1969, when the dose limit used to be 5 mSv/yr for the public, to the present generation pressurised heavy water reactors, when the population dose limit has been revised downward to 1 mSv/yr. The paper also presents the changes in the philosophy of dose apportionment for multifacility sites like Tarapur, Rawatbhata and Kalpakkam over the years. The operating experience with respect to environmental discharges from operating nuclear power plants (NPPs) in the country was reviewed vis-a-vis the applicable discharge limits, which shows that the actual releases constitute only a small percentage of the discharge limits. A strong case for lowering the dose apportionment for NPPs is suggested on the basis of latest data on site meteorology, dosimetry of radionuclides and environmental dose assessment methodology and operating experience. It is established in the paper that there is scope for reduction in the dose apportionment of NPPs for most of the radionuclides, without major changes in the existing discharge limits. The lowering of dose apportionment will be critically important at multifacility sites like Tarapur, Rawatbhata and Kalpakkam where many new facilities are being planned. At present the dose reserve available at these sites is only 0.14 mSv/yr, 0.06 mSv/yr and 0.16 mSv/yr, respectively at Tarapur, Rawatbhata and Kalpakkam. With the programme of siting

Dose constraints, what are they now?

International Nuclear Information System (INIS)

Lazo, T.

2005-01-01

The concept of a source-related dose constraint was first introduced in ICPR publication 60. The idea was to provide a number that individual exposures from a single, specific source should not exceed, and below which optimisation of protection should take place. Dose constraints were applied to occupational and public exposures from practices. In order to simplify and clarify the ICRP's recommendations, the latest draft, RPO5, presents dose constraints again, and with the same meaning as in publication 60. However, the dose constraints are now applied in all situations, not just practices. This new approach does provide simplification, in that a single concept is applied to all types of exposures (normal situations, accident situations, and existing situations). However, the approach and numerical values that are selected by regulatory authorities for the application of the concept, particularly in normal situations which are also subject to dose limits, will be crucial to the implementation of the system of radiological protection. (author)

Work plan for the Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

1989-12-01

The primary objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that populations could have received from nuclear operations at the Hanford Site since 1944, with descriptions of uncertainties inherent in such estimates. The secondary objective is to make project records--information that HEDR staff members used to estimate radiation doses--available to the public. Preliminary dose estimates for a limited geographic area and time period, certain radionuclides, and certain populations are planned to be available in 1990; complete results are planned to be reported in 1993. Project reports and references used in the reports are available to the public in the DOE Public Reading Room in Richland, Washington. Project progress is documented in monthly reports, which are also available to the public in the DOE Public Reading Room.

A radiological dose assessment for the Port Hope conversion facility

International Nuclear Information System (INIS)

Garisto, N.C.; Cooper, F.; Janes, A.; Stager, R.; Peters, R.

2011-01-01

The Port Hope Conversion Facility (PHCF) receives uranium trioxide for conversion to uranium hexafluoride (UF 6 ) or uranium dioxide (UO 2 ). The PHCF Site has a long history of industrial use. A Radiological Dose Assessment was undertaken as part of a Site Wide Risk Assessment. This assessment took into account all possible human receptors, both workers and members of the public. This paper focuses on a radiological assessment of dose to members of the public. The doses to members of the public from terrestrial pathways were added to the doses from aquatic pathways to obtain overall dose to receptors. The benchmark used in the assessment is 1 mSv/y. The estimated doses related to PHCF operations are much lower than the dose limit. (author)

Dose limits, constraints, reference levels. What does it mean for radiation protection?

International Nuclear Information System (INIS)

Breckow, J.

2016-01-01

The established concept of radiation protection with its basic principles justification, optimization, and limitation has proved its value and is going to be continued. In its deeper meaning, however, the concept is rather subtle and complex. Furthermore, in some aspects there remain some breaches or inconsistencies. This is just true for the terms dose limit, reference lever, and constraint that are tightly associated with the radiation protection principles. In order to guarantee the ability of radiation protection in whole extent, the subtle differences of meaning have to be communicated. There is a permanent need to defend the conceptual function of these terms against deliberate or undeliberate misinterpretations. Reference levels are definitely not the same as dose limits and they may not be misused as such. Any attempt to misinterpret fundamental radiation protection principles for selfish purposes should discouraged vigorously.

Dose. Detriment. Limit assessment; Dosis. Schadensmass. Grenzwertsetzung

Energy Technology Data Exchange (ETDEWEB)

Breckow, J. [Technische Hochschule Mittelhessen, Giessen (Germany). Inst. fuer Medizinische Physik und Strahlenschutz (IMPS)

2015-07-01

One goal of radiation protection is the limitation of stochastic effects due to radiation exposure. The probability of occurrence of a radiation induced stochastic effect, however, is only one of several other parameters which determine the radiation detriment. Though the ICRP-concept of detriment is a quantitative definition, the kind of detriment weighting includes somewhat subjective elements. In this sense, the detriment-concept of ICRP represents already at the stage of effective dose a kind of assessment. Thus, by comparing radiation protection standards and concepts interconvertible or with those of environment or occupational protection one should be aware of the possibly different principles of detriment assessment.

Occupational exposures and the case for reducing dose limits

International Nuclear Information System (INIS)

Gee, David

1987-01-01

This chapter describes the General, Municipal, Boilermakers and Allied Trades Union approach to all harmful agents encountered in either the workplace or the general environment; summarizes current radiation exposures in the UK and their arguments for a five-fold reduction in dose limits; and concludes with a summary of the only agreed compensation scheme in the world for radiation-induced cancer amongst workers. (author)

The Limitations of Quantitative Social Science for Informing Public Policy

Science.gov (United States)

Jerrim, John; de Vries, Robert

2017-01-01

Quantitative social science (QSS) has the potential to make an important contribution to public policy. However it also has a number of limitations. The aim of this paper is to explain these limitations to a non-specialist audience and to identify a number of ways in which QSS research could be improved to better inform public policy.

Rethinking basic concepts in ICRP's system of dose limitation

International Nuclear Information System (INIS)

Mills, W.A.; Mossman, K.L.

1991-01-01

The present criterion for radiation protection appears to be exposure reduction rather than adequate protection of health. The 1990 ICRP draft recommendations for a system of dose limitation would further implement this more restrictive criterion by implementing certain academic concepts and assumptions. These concepts and assumptions are discussed and the suggestion is made that the radiation protection community needs to carefully examine the need for the complex system proposed

Implementation of a safety action plan: reduction of the dose limits in a research centre

International Nuclear Information System (INIS)

Deworm, J.P.

1992-01-01

The Belgian Regulations require an annual Action Plan to improve the Safety and health conditions of works. Taking into consideration the preliminary versions of the new ICRP-recommendations, the 1990 Action Plan of the Belgian research Centre aimed to reduce the personal dose limit to 20 mSv/year and the annual collective dose by 10%. Major means used in the campaign were sensibility through information, consultation between hierarchy and executors and the application of a policy of discouragement at certain limits. As a result, the maximum level reaches was 16.5 mSv, while only 7 people received a dose above 10 mSv (of 219 who received a measurable dose, mean value 3,4 mSv). This success is due to the commitment at all levels of responsibilities. In 1991, the 20 mSv-limit is imposed as an obligation by the management, and a feasibility study to impose 10 mSv in near future is being undertaken. (author)

Deriving staff and public doses in a PET/CT facility from measured radiation levels using thermoluminescent dosimetry

International Nuclear Information System (INIS)

Al-Haj, A. N.; Lobriguito, A. M.; Arafah, A.; Parker, R.

2011-01-01

The introduction of PET/CT at King Faisal Specialist Hospital and Research Centre for whole body and brain imaging has become favourable for diagnosis of cancer. There is no data available on the PET/CT dose to staff and members of the public for different activities of 18 F [fluorodeoxyglucose (FDG)] and for longer patient holding time. The study aims to determine and evaluate staff and public doses by using thermoluminescent dosemeters monthly readings for a 7-month deployment period and by using direct measurements of dose rates at 30 cm and 1 m distances from the patients after injection. The whole body doses per procedure and per administered activity of 18 F (FDG) were estimated. A dose map inside the PET/CT was generated to provide information of the dose levels in different locations. The Pearson correlation showed a strong correlation (r 2 = 0.71) between the dose per activity and the number of patients. Optimisation of radiation protection of staff and members of the public was investigated and recommendations were given. (authors)

Estimated radiation dose from timepieces containing tritium

International Nuclear Information System (INIS)

McDowell-Boyer, L.M.

1980-01-01

Luminescent timepieces containing radioactive tritium, either in elemental form or incorporated into paint, are available to the general public. The purpose of this study was to estimate potential radiation dose commitments received by the public annually as a result of exposure to tritium which may escape from the timepieces during their distribution, use, repair, and disposal. Much uncertainty is associated with final dose estimates due to limitations of empirical data from which exposure parameters were derived. Maximum individual dose estimates were generally less than 3 μSv/yr, but ranged up to 2 mSv under worst-case conditions postulated. Estimated annual collective (population) doses were less than 5 person/Sv per million timepieces distributed

Estimation of population dose from all sources in Japan

International Nuclear Information System (INIS)

Kusama, Tomoko; Nakagawa, Takeo; Kai, Michiaki; Yoshizawa, Yasuo

1988-01-01

The purposes of estimation of population doses are to understand the per-caput doses of the public member from each artificial radiation source and to determine the proportion contributed of the doses from each individual source to the total irradiated population. We divided the population doses into two categories: individual-related and source-related population doses. The individual-related population dose is estimated based on the maximum assumption for use in allocation of the dose limits for members of the public. The source-related population dose is estimated both to justify the sources and practices and to optimize radiation protection. The source-related population dose, therefore, should be estimated as realistically as possible. We investigated all sources that caused exposure to the population in Japan from the above points of view

Recommendations of the International Commission on Radiological Protecion (1977) ICRP Publication 26

International Nuclear Information System (INIS)

1977-07-01

The subject is dealt with under the following headings: principles of radiation protection (the reports of ICRP; basis for establishing dose limits; types of radiation harm; occupational dose limits; estimates of tissue dose equivalent; uniformity of tissue dose equivalent; systems of dose limitation; protection of members of the public; exposure of the population); radiation protection in practice (protection standards, types of exposure). (U.K.)

Effective dose of individuals from the surrounding public to the facilities of the Abadia de Goiás radioactive waste disposal; Dose efetiva dos indivíduos do público circunvizinho às instalações dos repositórios de rejeitos radioativos de Abadia de Goiás

Energy Technology Data Exchange (ETDEWEB)

Ribeiro, E.; Borges, A.F. de Almeida; Camargos, K.M.; Santos, E.E. dos; Correa, R. da S., E-mail: rcorrea@cnen.gov.br [Centro Regional de Ciências Nucleares do Centro-Oeste (CRCN-CO/CNEN-GO), Abadia de Goiás, GO (Brazil); Ferreira, N.C., E-mail: nclferreira@gmail.com [Universidade Federal de Goias (UFG), Goiânia, GO (Brazil). Escola de Engenharia Civil e Ambiental; Ribeiro, N.V., E-mail: noely.ribeiro@uol.com.br [Universidade Federal de Goias (UFG), Goiânia, GO (Brazil). Instituto de Estudos Socioambientais

2017-07-01

The study presents the level of effective annual dose that individuals from the public - surrounding the repository of wastes with Cs-137, located in Abadia de Goiás, GO, Brazil - have received, according to analyzes carried out from June 2015 to July 2016. It was considered reference to the annual effective radiation dose limit of 0.3 mSv / year established by the National Nuclear Energy Commission (CNEN) for the impact of repositories on individuals in the public. Cs-137 activity determinations were performed on samples of surface water (ASU), groundwater (ASB), river bottom sediments (SED), soil (SOL) and vegetation (VEG). With these results, the effective doses were estimated for ASU and BSA consumption of 6.64 x 10{sup -4} mSv / year and for SED exposure, 3.92 x 10{sup -}6 mSv / year and for ASB use, 6.22 x 10{sup -3} mSv / year. For SOL and VEG, activity values of Cs-137 were used as indicators of contamination. It was observed that the effective annual doses were below the limit established by the norms, which can be inferred that the installation has been operating safely, without causing a radiological impact to the environment and individuals of the public.

The estimation of derived limits

International Nuclear Information System (INIS)

Harrison, N.T.; Bryant, P.M.; Clarke, R.H.; Morley, F.

1979-08-01

In practical radiation protection, it is often necessary to calculate limits of intake of radionuclides associated with various quantities; such limits are needed, for example, to assess the adequacy of the control of environmental contamination. In publication 26 of the International Commission on Radiological Protection (ICRP), these limits, when related to the basic limits of dose-equivalent by a defined model, are referred to as Derived Limits (DLs). In the present report the principles to be adopted by the Board in calculating DLs to be recommended for general application within the United Kingdom are outlined. DLs will be recommended for a wide range of radionuclides and for circumstances relevant to the workplace, and, more frequently, the general environment. The latter will include DLs in foodstuffs and associated environmental materials, such as soil and grass, and DLs for discharges from stacks. DLs will be related to dose equivalents for workers or members of the public for stochastic or non-stochastic effects as appropriate. Consideration will be given to relevant data on radiosensitivity, metabolism and dosimetry for children and to the physicochemical forms of radionuclides. (author)

78 FR 26112 - Limitation on Claims Against Proposed Public Transportation Projects; Correction

Science.gov (United States)

2013-05-03

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Limitation on Claims Against Proposed Public Transportation Projects; Correction AGENCY: Federal Transit Administration (FTA), DOT. ACTION... Register on April 22, 2013, concerning a limitation on claims for certain specified public transportation...

Contribution of maternal radionuclide burdens to prenatal radiation doses: Relationships between annual limits on intake and prenatal doses

International Nuclear Information System (INIS)

Sikov, M.R.; Hui, T.E.

1993-10-01

This addendum describes approaches for calculating and expressing radiation doses to the embryo/fetus from maternal intakes of radionuclides at levels corresponding to fractions or multiples of the Annual Limits on Intake (ALI). Information, concerning metabolic or dosimetric characteristics and the placental transfer of selected, occupationally significant radionuclides was presented in NUREG/CR-5631, Revision 1. That information was used to estimate levels of radioactivity in the embryo/fetus as a function of stage of pregnancy and time after entry. Extension of MIRD methodology to accommodate gestational-stage-dependent characteristics allowed dose calculations for the simplified situation based on introduction of 1 μCi into the woman's transfer compartment (blood). The expanded scenarios in this addendum include repeated or chronic ingestion or inhalation intakes by a woman during pregnancy and body burdens at the beginning of pregnancy. Tables present dose equivalent to the embryo/fetus relative to intakes of these radionuclides in various chemical or physical forms and from preexisting maternal burdens corresponding to ALI; complementary intake values (fraction of an ALI and μCi) that yield a dose equivalent of 0.05 rem are included. Similar tables give these measures of dose equivalency to the uterus from intakes of radionuclides for use as surrogates for embryo/fetus dose when biokinetic information is not available

The principles of dose limitation in radiation protection

International Nuclear Information System (INIS)

Kaul, A.

1988-01-01

The aim of radiation protection is to protect individuals, their offspring and the population as a whole against harmful effects from ionizing radiation and radioactive substances. Harmful effects may be either somatic, i.e. occurring in the exposed person himself/herself, or hereditary, i.e. occurring in the exposed person's offspring. Successful radiation protection involves (a) protective measures based on the results of research into the biological and biophysical effects of radiation and (b) ensuring that activities necessitating exposure are justified and that the degree of exposure is minimal. This benefit/risk principle ceases to apply if a radiation source is out of control, since the main aim is then to introduce risk limitation measures, provided that these are of positive net benefit to the individual and the population as a whole. This paper discusses the principles of dose limitation as a function of exposure conditions, i.e. controlled or uncontrolled exposure to a source of radiation

Radiation dose reduction: comparative assessment of publication volume between interventional and diagnostic radiology.

Science.gov (United States)

Hansmann, Jan; Henzler, Thomas; Gaba, Ron C; Morelli, John N

2017-01-01

We aimed to quantify and compare awareness regarding radiation dose reduction within the interventional radiology and diagnostic radiology communities. Abstracts accepted to the annual meetings of the Society of Interventional Radiology (SIR), the Cardiovascular and Interventional Radiological Society of Europe (CIRSE), the Radiological Society of North America (RSNA), and the European Congress of Radiology (ECR) between 2005 and 2015 were analyzed using the search terms "interventional/computed tomography" and "radiation dose/radiation dose reduction." A PubMed query using the above-mentioned search terms for the years of 2005-2015 was performed. Between 2005 and 2015, a total of 14 520 abstracts (mean, 660±297 abstracts) and 80 614 abstracts (mean, 3664±1025 abstracts) were presented at interventional and diagnostic radiology meetings, respectively. Significantly fewer abstracts related to radiation dose were presented at the interventional radiology meetings compared with the diagnostic radiology meetings (162 abstracts [1% of total] vs. 2706 [3% of total]; P radiology abstracts (range, 6-27) and 246±105 diagnostic radiology abstracts (range, 112-389) pertaining to radiation dose were presented at each meeting. The PubMed query revealed an average of 124±39 publications (range, 79-187) and 1205±307 publications (range, 829-1672) related to interventional and diagnostic radiology dose reduction per year, respectively (P radiology community over the past 10 years has not mirrored the increased volume seen within diagnostic radiology, suggesting that increased education and discussion about this topic may be warranted.

Public Health England survey of eye lens doses in the UK medical sector

International Nuclear Information System (INIS)

Ainsbury, E A; Bouffler, S; Gilvin, P; Peters, S; Slack, K; Cocker, M; Holt, E; Williamson, A

2014-01-01

The ICRP has recently recommended that the occupational exposure limit for the lens of the eye be reduced to 20 mSv in a year, averaged over defined periods of 5 years, with no single year exceeding 50 mSv. There has been concern amongst some groups of individuals, particularly interventional cardiologists and radiologists as well as relevant professional bodies, that implementation of these recommendations into UK law will adversely affect working patterns. However, despite a number of informative European studies, there is currently little UK dosimetry data available upon which judgements can effectively be based. In order to address this knowledge gap, Public Health England has carried out a small, targeted survey of UK lens doses to medical staff undertaking procedures likely to involve the highest levels of radiation exposure. Two out of a total of 61 individuals surveyed had projected annual doses which could be close to 20 mSv, measured outside lead glasses. Use of protective equipment was generally good; however, lead glasses were only used by 9 participants. The results of this survey suggest that compliance with the ICRP recommendations is likely to be possible for most individuals in the UK medical sector. (paper)

Accuracy and Radiation Dose Reduction of Limited-Range CT in the Evaluation of Acute Appendicitis in Pediatric Patients.

Science.gov (United States)

Jin, Michael; Sanchez, Thomas R; Lamba, Ramit; Fananapazir, Ghaneh; Corwin, Michael T

2017-09-01

The purpose of this article is to determine the accuracy and radiation dose reduction of limited-range CT prescribed from the top of L2 to the top of the pubic symphysis in children with suspected acute appendicitis. We performed a retrospective study of 210 consecutive pediatric patients from December 11, 2012, through December 11, 2014, who underwent abdominopelvic CT for suspected acute appendicitis. Two radiologists independently reviewed the theoretic limited scans from the superior L2 vertebral body to the top of the pubic symphysis, to assess for visualization of the appendix, acute appendicitis, alternative diagnoses, and incidental findings. Separately, the same parameters were assessed on the full scan by the same two reviewers. Whole-body effective doses were determined for the full- and limited-range scans and were compared using the paired t test. The appendix or entire cecum was visualized on the limited scan in all cases, and no cases of acute appendicitis were missed on the simulated limited scan compared with the full scan. Two alternative diagnoses were missed with the limited scan: one case of hydronephrosis and one of acute acalculous cholecystitis. The mean effective dose for the original scan was 5.6 mSv and that for the simulated limited scan was 3.0 mSv, resulting in a dose reduction of 46.4% (p appendicitis and reduces the dose by approximately 46%.

The system of dose limitation and its optimization requirement: Present status and future outlook

International Nuclear Information System (INIS)

Gonzalez, A.J.

1984-01-01

Optimization of radiation protection is a relevant and controversial requirement of the system of dose limitation currently recommended by the International Commission on Radiological Protection (ICRP). Since the first European Scientific Seminar on Experience and Methods on Optimization - held by the Commission of the European Communities in 1979 - and several related seminars and symposia organized by the IAEA, many international efforts have been made to promote the practical implementation of the requirement. Recently, the ICRP published a report of ICRP Committee 4 on cost-benefit analysis in the optimization of radiation protection (ICRP Publication 37); it provides guidance on the principles and methods of application of the requirement. Ultimately, this seminar demonstrates the continuous interest of the international community in the proper use of optimization. This paper is intended to contribute to the seminar's objective, discussing the current issues concerning the implementation of the requirement and exploring perspectives for future applications of the principles involved in optimization

Estimation of the individual and collective doses received by workers and the public during the transport of radioactive materials in france between 1981 and 1990

International Nuclear Information System (INIS)

Hamard, J.; Ringot, C.; Bernard, H.; Connat, R.; Lecoq, P.; Morin, P.

1993-01-01

The monitoring of the exposure of workers and the public during the transport of radioactive materials is complicated by the mobile nature of the sources and by the fact that, up to now, a large proportion of workers have not been considered to be at risk and their exposure has therefore not been the subject of surveillance. Likewise, in the case of the public, the mobile nature of the sources makes it difficult to define a critical group which could be the subject of dose evaluation. For this reason, the IAEA transport regulations recommend periodic evaluations of exposure to verify that it remains below an acceptable level, in accordance with the principle of optimization and to ensure that dose limits are complied with. In France, an inquiry covering the workers of the main companies engaged in the transport of radioactive materials has been conducted on a two-yearly basis since 1980, and the results have been published at each PATRAM meeting. This inquiry now spans a period of ten years (1980 to 1990) and it is possible to see how exposure has evolved as a function of the development of the French nuclear power programme and the consequent increase in a number of transport operations. As concerns the public, a comparison is made between the exposure levels estimated in the study and the exposure levels calculated by application of the RADTRAN model developed for the purpose by the IAEA. The results show the evolution of the maximum annual doses, the average doses and the collective doses received by workers during the transport of different radio-pharmaceutical and fuel cycle products, as well as the collective dose for the public during the period covered. (author)

The significance of water hammer events to public dose from reactor accidents: A probabilistic assessment

International Nuclear Information System (INIS)

Amico, P.J.; Ferrell, W.L.; Rubin, M.P.

1984-01-01

A probabilistic assessment was made of the effects on public dose of water hammer events in LWRs. The analysis utilized actual historical water hammer data to determine if the water hammer events contributed either to system failure rates or initiating event frequencies. Representative PRAs were used to see if changes in initiating events and/or system failures caused by water hammer resulted in new values for the dominant sequences in the PRAs. New core melt frequencies were determined and carried out to the subsequent increase in public dose. It is concluded that water hammer is not a significant problem with respect to risk to the public for either BWRs or PWRs. (orig./HP)

The issue concerning the use of an annual as opposed to a committed dose limit for internal radiation protection

International Nuclear Information System (INIS)

Skrable, K.W.; Chabot, G.E.; Alexander, E.L.; French, C.S.

1985-01-01

The scientific, technical, practical, and ethical considerations that relate to the use of an annual as opposed to a committed dose limitation system for internal radiation protection are evaluated and presented. The concerns about problems associated with the more recent ICRP committed dose recommendations that have been expressed by persons who are currently operating under an annual dose limitation system are reviewed and discussed in terms of the radiation protection programme elements that are required for an effective ALARA programme. We include in this and a follow-up article a comparison of how these alternative dose limitation systems affect the economic and professional livelihood of radiation workers and the requirements that they impose upon employers. Finally, we recommend the use of an ICRP based committed dose limitation system that provides protection of workers over an entire occupational lifetime without undue impact on their livelihood and without undue requirements for employers. (author)

Assessment of the benefits and impacts in the U.S. Nuclear Power Industry of hypothesized lower occupational dose limits

Energy Technology Data Exchange (ETDEWEB)

Andersen, R.L.; Schmitt, J.F. [Nuclear Energy Institute, Washington, DC (United States)

1995-03-01

The International Commission on Radiological Protection and the National Council on Radiation Protection and Measurements have issued recommendations that would limit occupational exposure of individuals to doses lower than regulatory limits contained in the Nuclear Regulatory Commission`s 10 CFR Part 20, {open_quotes}Standards for Protection Against Radiation{close_quotes}. Because of this situation, there is interest in the potential benefits and impacts that would be associated with movement of the NRC regulatory limits toward the advisory bodies recommendations. The records of occupational worker doses in the U.S. commercial nuclear power industry show that the vast majority of these workers have doses that are significantly below the regulatory limit of 50 mSv (5 rem) per year. Some workers doses do approach the limits, however. This is most common in the case of specially skilled workers, especially those with skills utilized in support of plant outage work. Any consideration of the potential benefits and impacts of hypothesized lower dose limits must address these workers as an important input to the overall assessment. There are also, of course, many other areas in which the benefits and impacts must be evaluated. To prepare to provide valid, constructive input on this matter, the U.S. nuclear power industry is undertaking an assessment, facilitated by the Nuclear Energy Institute (NEI), of the potential benefits and impacts at its facilities associated with hypothesized lower occupational dose limits. Some preliminary results available to date from this assessment are provided.

Assessment of the benefits and impacts in the U.S. Nuclear Power Industry of hypothesized lower occupational dose limits

International Nuclear Information System (INIS)

Andersen, R.L.; Schmitt, J.F.

1995-01-01

The International Commission on Radiological Protection and the National Council on Radiation Protection and Measurements have issued recommendations that would limit occupational exposure of individuals to doses lower than regulatory limits contained in the Nuclear Regulatory Commission's 10 CFR Part 20, open-quotes Standards for Protection Against Radiationclose quotes. Because of this situation, there is interest in the potential benefits and impacts that would be associated with movement of the NRC regulatory limits toward the advisory bodies recommendations. The records of occupational worker doses in the U.S. commercial nuclear power industry show that the vast majority of these workers have doses that are significantly below the regulatory limit of 50 mSv (5 rem) per year. Some workers doses do approach the limits, however. This is most common in the case of specially skilled workers, especially those with skills utilized in support of plant outage work. Any consideration of the potential benefits and impacts of hypothesized lower dose limits must address these workers as an important input to the overall assessment. There are also, of course, many other areas in which the benefits and impacts must be evaluated. To prepare to provide valid, constructive input on this matter, the U.S. nuclear power industry is undertaking an assessment, facilitated by the Nuclear Energy Institute (NEI), of the potential benefits and impacts at its facilities associated with hypothesized lower occupational dose limits. Some preliminary results available to date from this assessment are provided

Implications of dose limit modification for radioactive installations dedicated to research

International Nuclear Information System (INIS)

Lumbreras, J.M.; Fernandez, G.M.; Marana, D.

1992-01-01

The reduced dose limits proposed in the ICRP recommendations affect the Spanish Regulations on Sanitary Protection against Ionizing Radiation. Some implications of this for radioactive installations dedicated to research are pointed out. A very simple statistical study shows that dosimetric data might be used to adopt new criteria for classification of personnel, and even of working areas. (author)

Use of dose constraints for occupational exposure

International Nuclear Information System (INIS)

Kaijage, Tunu

2015-02-01

The use of dose constraints for occupational exposure was reviewed in this project. The role of dose constraints as used in optimization of protection of workers was described. Different issues to be considered in application of the concept and challenges associated with their implementation were also discussed. The situation where dose constraints could be misinterpreted to dose limits is also explained as the two are clearly differentiated by the International Commission of Radiological Protection (ICRP) Publication 103. Moreover, recommendations to all parties responsible for protection and safety of workers were discussed. (au)

Time-dependent, low-dose reporting limit for dosimeters that are taken home at the end of the workday

International Nuclear Information System (INIS)

Sonder, E.

1994-01-01

In routine personnel dosimetry, it is usual to report doses only where th occupational dose (measured dose with background subtracted) is greater than previously determined reporting limit. The reporting limit, although se administratively, should be justified by an assessment of the errors inherent in th personnel and background dose measurements, and estimates of the probability that a zero exposure will yield a dosimeter response equal to the reporting limit. For background subtraction and reporting limits, it was realized that the source of low-dose uncertainty is very much dependent on whether dosimeters are held in racks at the work site or remain with the employee. The External dosimetry Program for the DOE facilities at Oak Ridge, Tennessee, is operated such that dosimeters are taken home by the employee at the end of each workday. This report is a summary measurements of background radiation in a variety of home locations, and calculations of the effect of the variation of this background on the uncertainty low-level occupational dose and on the reporting level. When dosimeters are stored at a given location (e.g., the facility gate), it theoretically possible to determine the background there to any desired accuracy; the errors in occupational dose are then those due to measurement noise and dosimeter calibration. However, when different dosimeters are stored in different homes, th difference in background between a particular location and the average for a locations appears as an added uncertainty in the occupational dose. Since this difference is not random, but fixed for a given location, the error due to this difference increases linearly with assignment time. From the background measurements, time-dependent values of the standard deviation of occupational do and critical levels are derived and used to define an expression for the reporting limit

A study on evaluation of public dose for hypothetical exposure from industrial sources in major Indian cities

International Nuclear Information System (INIS)

Chandrasekaran, S.; Sivasubramanian, K.; Venkatraman, B.

2016-01-01

With expanding industrial establishments in India, the requirements for quality Assurance (QA) have become stringent at every stages of process including selection of raw material, manufacturing process and packing and transport. Radiography, a non-destructive method is widely employed for QA testing. Inadvertent handling or loss of these sources may result in exposure of public/workers to higher levels of ionizing radiation. A well planned emergency preparedness is essential to manage any such untoward incidents. Dose estimation to members of public involved is the major challenge as the time available is very short and eases of availability/labs surrounding the location. This paper determines the dose up to 30m distance as prescribed in AERB safety guidelines and using the population data of four major metropolitan cities in India, public dose is also estimated

Review of NCRP radiation dose limit for embryo and fetus in occupationally-exposed women

International Nuclear Information System (INIS)

Anon.

1977-01-01

On the basis of the current review, the NCRP has decided to make no change in the current recommendation of its radiation dose limit to the unborn. The NCRP recommendation is restated here as follows: During the entire gestation period, the maximum permissible dose equivalent to the embryo-fetus from occupational exposure of the expectant mother should be 0.5 rem. Since the preparation of the 1971 report there has been no new evidence concerning teratogenic or carcinogenic effects of irradiation of the embryo-fetus that would justify a change in the limit in either direction. It is implicit in this position and recommendation that women who can reasonably be expected to be pregnant should not, in certain instances, be exposed to the same radiation environment as women who are not considered fertile or as men. This applies particularly to conditions where radiation workers can receive dose equivalents of 0.5 rem or more in short periods

Risk of eye lens radiation exposure for members of the public

International Nuclear Information System (INIS)

Chevallier, M.-A.; Rannou, A.; Villagrasa, C.; Clairand, I.

2016-01-01

In 2011, the International Commission on Radiological Protection (ICRP) reviewed its recommendation concerning the equivalent dose limit for the eye lens, lowering it to 20 mSv in a year, for occupational exposure in planned exposure situations. The ICRP's statement does not contain any explicit recommendations regarding the organ dose limit for the eye lens for public exposure. For the moment, no change is proposed. But, to be coherent in the overall approach, the current equivalent limit for the public might be lowered. A similar yardstick than in the former recommendation may be used, that is to say a reduction of 10 times lower than that for occupational exposure. In this context, additional data on potential scenarios for public exposure of the eye lens are necessary. This paper, mainly based on a literature study, aims to provide, as far as possible, an exhaustive list of the situations in which members of the public can be exposed at the level of the eye lens. Once these situations have been defined, some calculations, made to assess the associated doses to the eye lens, are presented. This literature study did not reveal any current situations where members of the public would receive significant radiation doses to the eye lens. Indeed, the situations in which the dose to the eye lens might reach around 1 mSv per year for the public are extremely rare. (authors)

The governance of publicly traded limited liability companies

NARCIS (Netherlands)

Gomtsyan, S.

The limited liability company is not only a widespread business form for non-listed firms but also is used by listed companies. There were 20 publicly traded Delaware LLCs in September 2013. Given the policy of the Delaware legislators and courts to give a maximum effect to the principle of freedom

78 FR 16764 - Limitation on Claims Against Proposed Public Transportation Projects

Science.gov (United States)

2013-03-18

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Limitation on Claims Against Proposed Public Transportation Projects AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice. SUMMARY... advising the public of final agency actions subject to Section 139(l) of Title 23, United States Code (U.S...

78 FR 4191 - Limitation on Claims Against Proposed Public Transportation Projects

Science.gov (United States)

2013-01-18

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Limitation on Claims Against Proposed Public Transportation Projects AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice. SUMMARY... advising the public of final agency actions subject to Section 139(l) of Title 23, United States Code (U.S...

78 FR 33890 - Limitation on Claims Against Proposed Public Transportation Projects

Science.gov (United States)

2013-06-05

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Limitation on Claims Against Proposed Public Transportation Projects AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice. SUMMARY... advising the public of final agency actions subject to Section 139(l) of Title 23, United States Code (U.S...

Limit of the radionuclides in granite

International Nuclear Information System (INIS)

Wang Shaling; Jiang Rangrong

2003-01-01

Granite is an important sort of building materials. Their radionuclide contents are limited by the national standard GB6566-2001 just as other building materials. This standard divides them into main materials and decorative materials, and relaxes the limit of the latter obviously. Owing to the consideration of public dose limit and environment protection, this method needs discussion. Otherwise, red granite contains high radionuclide contents relatively, especially the sort of Indian Red, and need be paid more attention

Dose limit for emergency workers. Application of Fukushima-Daiichi NPP accident and problems for the future

International Nuclear Information System (INIS)

Sugai, Kenji

2012-01-01

Described are details of management for workers' personal exposure dose, of problems raised and of their solutions taken under various complicated conditions of Fukushima Daiichi Nuclear Power Plant (NPP) Accident (Mar. 2011). As the entrance/exit (en/ex) for the NPP site with regular control were impossible due to the hydrogen explosion which expanded the control area to 20 km distance from the site, Japan Football Village (J-Village) localizing at the border and Important Anti-seismic Building in the site were defined to be the bases of en/ex and of their control, respectively. Flooded 5,000 alarm pocket dosimeters (APD) by tsunami were not usable and only 320 APD remained available. At the quite early stage of working at the site, one representative worker in a group had only one APD. Management of internal exposure was also difficult essentially because the power source of the whole body counter was unavailable. At an early emergent stage alone, workers with higher dose than the limit (100 mSv for emergency) were observed, but >90% of workers were exposed to <50 mSv (the limit for the radiation worker). Six male Tokyo Electric Power Company (TEPCO) personnel were exposed to 250 mSv (specially defined dose limit) or more with the maximum 678.80 mSv, in whom the internal exposure due to radioiodine largely attributed. They were examined for their health by the expert doctors in National Institute of Radiological Sciences, were found free of abnormality and were to be followed up thereafter. Out of 19 female TEPCO personnel, two had exceeded the dose limit 5 mSv/3 mo and other 2, the annual limit 1 mSv. They received the examination by the industrial doctor, were found free of abnormality, but were decided not to work at the site. Recently, about 5,000 APD have been purchased for personal usage and dose management is conducted by bar-coding of individual workers, and internal exposure is managed with 11 whole body counters by once a month measurement in J

Application of the dose limitation system to the control of carbon-14 releases from heavy-water-moderated reactors

International Nuclear Information System (INIS)

Beninson, D.; Gonzalez, A.J.

1982-01-01

Heavy-water-moderated reactors produce substantially more carbon-14 than light-water reactors. Applying the principles of the systems of dose limitation, the paper presents the rationale used for establishing the release limit for effluents containing this nuclide and for the decisions made regarding the effluent treatment in the third nuclear power station in Argentina. Production of carbon-14 in PHWR and the release routes are analysed in the light of the different effluent treatment possibilities. An optimization assessment is presented, taking into account effluent treatment and waste management costs, and the collective effective dose commitment due to the releases. The contribution of present carbon-14 releases to future individual doses is also analysed in the light of an upper bound for the contribution, representing a fraction of the individual dose limits. The paper presents the resulting requirements for the effluent treatment regarding carbon-14 and the corresponding regulatory aspects used in Argentina. (author)

Estimated dose rates to members of the public from external exposure to patients with 131I thyroid treatment

International Nuclear Information System (INIS)

Dewji, S.; Bellamy, M.; Leggett, R.; Eckerman, K.; Hertel, N.; Sherbini, S.; Saba, M.

2015-01-01

Purpose: Estimated dose rates that may result from exposure to patients who had been administered iodine-131 ( 131 I) as part of medical therapy were calculated. These effective dose rate estimates were compared with simplified assumptions under United States Nuclear Regulatory Commission Regulatory Guide 8.39, which does not consider body tissue attenuation nor time-dependent redistribution and excretion of the administered 131 I. Methods: Dose rates were estimated for members of the public potentially exposed to external irradiation from patients recently treated with 131 I. Tissue attenuation and iodine biokinetics were considered in the patient in a larger comprehensive effort to improve external dose rate estimates. The external dose rate estimates are based on Monte Carlo simulations using the Phantom with Movable Arms and Legs (PIMAL), previously developed by Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission. PIMAL was employed to model the relative positions of the 131 I patient and members of the public in three exposure scenarios: (1) traveling on a bus in a total of six seated or standing permutations, (2) two nursing home cases where a caregiver is seated at 30 cm from the patient’s bedside and a nursing home resident seated 250 cm away from the patient in an adjacent bed, and (3) two hotel cases where the patient and a guest are in adjacent rooms with beds on opposite sides of the common wall, with the patient and guest both in bed and either seated back-to-back or lying head to head. The biokinetic model predictions of the retention and distribution of 131 I in the patient assumed a single voiding of urinary bladder contents that occurred during the trip at 2, 4, or 8 h after 131 I administration for the public transportation cases, continuous first-order voiding for the nursing home cases, and regular periodic voiding at 4, 8, or 12 h after administration for the hotel room cases. Organ specific activities of 131 I

Age and sex dependent inhalation doses to members of the public from indoor thoron progeny

Energy Technology Data Exchange (ETDEWEB)

Bi, L; Tschiersch, J [Helmholtz Zentrum Muenchen-German Research Center for Environmental Health, Institute of Radiation Protection, D-85764, Neuherberg (Germany); Li, W B [Helmholtz Zentrum Muenchen-German Research Center for Environmental Health, Department of Medical Radiation Physics and Diagnostics, D-85764, Neuherberg (Germany); Li, J L, E-mail: bilei1983@gmail.com [Department of Engineering Physics, Tsinghua University, Beijing 100084 (China)

2010-12-01

The increased indoor thoron level in Europe, North America and Asia has shown that the exposure to thoron and its decay products cannot be ignored in some environments. The contribution of thoron and its progeny can be a significant component of the total exposure from radon and thoron. In the present paper, radiation dose assessment of members of the public of different age and sex exposed to {sup 220}Rn progeny under different daily life activities is performed through a dosimetric approach. Dose conversion coefficients under typical indoor conditions were estimated to be in the range of 107 nSv (Bq h m{sup -3}){sup -1} for infant to 81.7 nSv (Bq h m{sup -3}){sup -1} for adult. The results of this work emphasized that small children receive a radiation dose of 25% more than adults under the same conditions, and people performing exercise receive a radiation dose 100% more than when sleeping. The results of this work are appropriate to the risk assessment of thoron exposure to members of the public who live in areas with high radon and thoron concentrations.

Towards a new dose and dose-rate effectiveness factor (DDREF)? Some comments.

Science.gov (United States)

Chadwick, K H

2017-06-26

The aim of this article is to offer a broader, mechanism-based, analytical tool than that used by (Rühm et al 2016 Ann. ICRP 45 262-79) for the interpretation of cancer induction relationships. The article explains the limitations of this broader analytical tool and the implications of its use in view of the publications by Leuraud et al 2015 (Lancet Haematol. 2 e276-81) and Richardson et al 2015 (Br. Med. J. 351 h5359). The publication by Rühm et al 2016 (Ann. ICRP 45 262-79), which is clearly work in progress, reviews the current status of the dose and dose-rate effectiveness factor (DDREF) as recommended by the ICRP. It also considers the issues which might influence a reassessment of both the value of the DDREF as well as its application in radiological protection. In this article, the problem is approached from a different perspective and starts by commenting on the limited scientific data used by Rühm et al 2016 (Ann. ICRP 45 262-79) to develop their analysis which ultimately leads them to use a linear-quadratic dose effect relationship to fit solid cancer mortality data from the Japanese life span study of atomic bomb survivors. The approach taken here includes more data on the induction of DNA double strand breaks and, using experimental data taken from the literature, directly relates the breaks to cell killing, chromosomal aberrations and somatic mutations. The relationships are expanded to describe the induction of cancer as arising from radiation induced cytological damage coupled to cell killing since the cancer mutated cell has to survive to express its malignant nature. Equations are derived for the induction of cancer after both acute and chronic exposure to sparsely ionising radiation. The equations are fitted to the induction of cancer in mice to illustrate a dose effect relationship over the total dose range. The 'DDREF' derived from the two equations varies with dose and the DDREF concept is called into question. Although the equation for

Consequences of the Chernobyl reactor accident for the dose commitment of the general public

Energy Technology Data Exchange (ETDEWEB)

Kiefer, H

1986-01-01

The cumulative effective equipment dose from external radiation and by inhalation was about 5.10/sup -5/ Sv (5 mrem) for the adults monitored and about 7.10/sup -5/ Sv (7 mrem) for small children by the beginning of June. The inhalation dose has already reached its limit, but the external dose could rise by another 1 to 2.10/sup -5/ Sv (1-2 mrem) during the year. Another 2.5.10/sup -5/ Sv (2.5 mrem) effective equivalent dose was measured in children and 1.10/sup -5/ Sv (1 mrem) in adults, due to ingestion. The dose from Cs 137 received by the population in food will remain small during the next few years.

Method for calculation of upper limit internal alpha dose rates to aquatic organisms with application of plutonium-239 in plankton

International Nuclear Information System (INIS)

Paschoa, A.S.; Baptista, G.B.

1977-01-01

A method for the calculation of upper limit internal alpha dose rates to aquatic organisms is presented. The mean alpha energies per disintegration of radionuclides of interest are listed to be used in standard methodologies to calculate dose to aquatic biota. As an application, the upper limits for the alpha dose rates from 239 Pu to the total body of plankton are estimated based on data available in open literature [pt

On the constitutionality of dose limiting values

International Nuclear Information System (INIS)

Goetz, V.

1976-01-01

The fundamental right according to Art. 2 par. 2 sentence 1 of the German Constitution is relevant for the set-up and application of radiation protection law. Resulting from Art. 2 par. 2 sentence 1 of the Constitution it is a general obligation of the state to protect life (Federal Constitutional Court, judgment of 25th Feb., 1975, BVerfGE 39.1) and physical soundness. The subjective basic right of everybody to defend against official encroachments his personal integrity corresponds to the right of the individual within the framework of the official obligation for protection from the state (to ward off danger). The term of danger, as to the degree of its determination, corresponds to that of the encroachment. To speak of danger in a legal sense, the causal connection between a certain source of danger and certain damage must be ascertained and proved. Topical controversies as to the admissibility of activity discharges of low doses range in the field of risk reduction and thus in the field of the duty of the state to take precautionary steps against risks (Art. 2 par. 2 sentence 1 of the Constitution). The constitution, however, does not contain any basic right that every risk has to be avoided. On the other hand, the necessity of cautions valuation of radiation risks can be derived from the Constitution. The fixation of dose limits and their application in connection with general radiation protection principles (paragraph 28 E of the Radiation Protection Ordinance) do not contain any 'interference' with the basic right in the sense of Art. 2 par. 2 sentence 3 of the Constitution. Neither from aspects of the principle of the legal state nor from Art. 80 par. 1 of the Constitution can the use of the legal form of the Ordinance be doubted. (orig./HP) [de

New safety standards of nuclear power station with no requirements of site evaluation. No public dose limit published with possible inappropriateness of reactor site

International Nuclear Information System (INIS)

Takitani, Koichi

2013-01-01

Nuclear Regulation Authority was preparing new safety standards in order to aim at starting safety reviews of existing nuclear power station in July 2013. This article commented on issues of major accident, which was defined as severely damaged core event. Accumulated dose at the site boundary of the Fukushima Daiichi Nuclear Power Station totaled to about 234 mSv on March just after the accident with rare gas of 500 PBq, iodine 131 of 500 PBq, cesium 134 of 10 PBq and cesium 137 of 10 PBq released to the atmosphere, which was beyond 100 mSv. As measures for preventing containment vessel failure after core severely damaged, filtered venting system was required to be installed for low radiological risk to the public. However filter was not effective to rare gas. Accumulated doses at the site boundary of several nuclear power stations after filtered venting with 100% release of rare gas could be estimated to be 2-37 Sv mostly depending on the site condition, which might be surely greater than 100 mSv. Omitting site evaluation for major accident, which was beyond design basis accident, was great concern. (T. Tanaka)

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)

Ahmet, E. Osmanlioglu

2006-01-01

Full text: Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides. Near surface disposal term includes broad range of facilities from simple trenches to concrete vaults. Principally, disposal of radioactive waste requires the implementation of measures that will provide safety for human health and environment now and in the future. For this reason preliminary activity limits should be determined to avoid radioecological problems. Radioactive waste has to be safely disposed in a regulated manner, consistent with internationally agreed principles and standards and with national legislations to avoid serious radioecological problems. The purpose of this study, presents a safety assessment approach to derive operational and post-closure radioecological activity limits for the disposal of radioactive waste. Disposal system has three components; the waste, the facility (incl. engineered barriers) and the site (natural barriers). Form of the waste (unconditioned or conditioned) is effective at the beginning of the migration scenerio. Existence of the engineered barriers in the facility will provide long term isolation of the waste from environment. The site characteristics (geology, groundwater, seismicity, climate etc.) are important for the safety of the system. Occupational exposure of a worker shall be controlled so that the following dose limits are not exceeded: an effective dose of 20mSv/y averaged over 5 consecutive years; and an effective dose of 50mSv in any single year. The effective dose limit for members of the public recommended by ICRP and IAEA is 1 mSv/y for exposures from all man-made sources [1,2]. Dose constraints are typically a fraction of the dose limit and ICRP recommendations (0.3 mSv/y) could be applied [3,4]. Radioecological activity concentration limits of each radionuclide in the waste (Bq/kg) were calculated. As a result of this study radioecological activity

A summary of estimated doses to members of the public from atmospheric nuclear tests at the Nevada test site

International Nuclear Information System (INIS)

Simon, S.L.; Bouville, A.; Luckyanov, N.; Miller, C.W.; Beck, H.L.; Anspaugh, L.R.

2002-01-01

This paper discusses estimates of radiation dose to representative members of the public of the United States (U.S.) from atmospheric nuclear tests conducted from 1951 through 1962 at the Nevada Test Site. The estimates provided here summarize five studies conducted over the past two decades. From those studies, an estimate of the average deposition of 137 Cs within each of the more than 3,000 counties across the country has been derived as well as doses to representative persons in each county and to specific subpopulations. The years of the largest contributions to the collective external dose were 1952, 1953, and 1957. Those years accounted for about 70% of the 84,000 person-Gy received by the U.S. public. Irradiation of the thyroid gland of members of the U.S. public was also a consequence of dispersion of radioiodine in the fallout. Thyroid doses varied by location and by birth year. The population weighted thyroid dose for a child born in 1951 and for an adult in 1951 were 30 and 5 mGy, respectively. Maps are provided to show the geographic distribution of 137 Cs as well as the average thyroid dose received in each county from the Nevada tests. (author)

Analysis of occupational doses in radioactive and nuclear facilities

International Nuclear Information System (INIS)

Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

1996-01-01

Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

Experience with respect to dose limitation in nuclear fuel service operations in the United Kingdom supporting civil nuclear power programmes

International Nuclear Information System (INIS)

Kennedy, J.W.

1983-01-01

Within the United Kingdom, the nuclear power generation programme is supported by nuclear fuel services including uranium enrichment, fuel fabrication and reprocessing, operated by British Nuclear Fuels Limited (BNFL). These have entailed the processing of large quantities of uranium and of plutonium and fission products arising in the course of irradiation of fuel in nuclear power stations and have necessitated substantial programmes for the radiological protection of the public and of the workers employed in the industry. This paper presents and reviews the statistics of doses recorded in the various sectors of nuclear fuel services operations against the background of the standards to which the industry is required to operate. A description is given of the development of BNFL policy in keeping with the objective of being recognized as among those industries regarded as safe and the resource implications of measures to reduce doses received by workers are reviewed in the light of experience. Finally, the paper reviews the epidemiological data which have been, and continue to be, collected for workers who have been employed in these nuclear fuel services. (author)

Measurement of doses to aviator pilots using thermoluminescent dosemeters

International Nuclear Information System (INIS)

Azorin N, J.; Cruz C, D.; Rivera M, T.

2004-01-01

During the development of their work, the aviator pilots are exposed at high levels of natural radiation of bottom caused mainly by the cosmic radiation of galactic origin and lot. For such reason, the Metropolitan Autonomous University (UAM) and the Union Association of Aviator Pilots (ASPA), subscribed an agreement with the purpose of to measure the doses of ionizing radiation received by the aviator pilots of diverse air companies that man different types of airships and to determine if these doses surpass the one limit of 0.11 mSv/h settled down by the IAEA for the public in general; and if therefore, these workers should be considered as personnel occupationally exposed. In this work the obtained results when measuring the absorbed dose received by Mexican civil aviator pilots during the development of their work, using thermoluminescent dosemeters of LiF:Mg,Cu,P + Ptfe of national production are presented. The obtained results during the years of 2001 and 2002 show that the monthly doses received by the pilots surpass the one it limits established for the public in general, for what they should be considered as personnel occupationally exposed. (Author)

Problems arising in the evaluation of collective dose commitment

International Nuclear Information System (INIS)

Coulon, R.; Beau, P.

1979-01-01

In order to apply the concept of optimization it is necessary to evaluate the collective dose commitment for the population as a whole. This is found by summing the dose commitments for the different population groups involved, including persons occupationally exposed and members of the public both locally and globally. The average dose received by each of these groups can vary considerably: for occupational exposure it is about one order of magnitude below the limits, whereas for the general public it is far below, although certain local groups may be subjected to a much higher exposure than the overall average. The question arises, therefore, whether certain groups should not be weighted differently in order to take into account the heterogeneity of the distribution of exposure. As far as the validity of forecast evaluations is concerned, one may assume that for occupational exposure the dose commitment over the whole period of operation of a facility can be estimated fairly accurately. The overall collective dose commitment for the public is relatively insensitive to local variations in the environment and in the public itself but is strongly dependent on long-term developments which cannot at present be forecast. For the evaluation of dose equivalent to the critical group, local variations are of considerable importance and need to be foreseen, which is not always possible. By taking into account a period which includes the annual maximum collective dose equivalent one can make some of these difficulties less severe. (author)

On the new recommendation of the International Commission on Radiological Protection. Publication 60

International Nuclear Information System (INIS)

Chukhin, S.G.

1994-01-01

The International Commission on Radioligical Protection (ICRP) published in 1990 new main recommendations (Publication 60), in which the recommendations of 1977 (Publication 26) were revised and noticeable changes were introduced. The main changes in ICRP recommendations important for practical personnel are discussed. These important changes include introduction of two protection systems, which are the protection system in practice and that during intervention, conception of potential irradiation, dose and risk limits, changes in dose limits and risk coefficients, determination of the effective dose and its numerical values by changing the weighting coefficients. The problems open to arguments are formulated

National and international considerations of a de minimis dose

International Nuclear Information System (INIS)

Kocher, D.C.

1986-01-01

This paper reviews current efforts by national and international agencies to establish a generally applicable de minimis radiation dose. A de minimis dose is derived from a level of risk that is widely regarded as negligible by the general public, and defines a level below which control of radiation exposures would be deliberately and specifically curtailed. A de minimis dose can be used to derive quantities of radionuclides in various materials that would be exempt or below regulatory concern for such purposes as resale, recycling, or disposal. The specification of exempt levels of radioactivity could lead to significant reductions in the required capacity of radioactive waste storage and disposal facilities and in the costs associated with management of slightly contaminated materials. A de minimis dose must be set well below the limit on acceptable dose for public exposures. A de minimis dose in the range 0.1-30 mrem (0.001-0.3 mSv) per year committed effective dose equivalent has been considered by various agencies, with most recommendations at 1 or 5 mrem per year. A value of 30 mrem per year may be too high for a de minimis dose, because a dose limit of 25 mrem per year is widely used in the US for regulating specific practices (e.g., low-level waste disposal). A value as low as 0.1 mrem per year could lead to great difficulties in measuring associated levels of radioactivity. We propose a de minimis dose of 1 mrem (0.01 mSv) per year committed effective dose equivalent averaged over a lifetime and 5 mrem (0.05 mSv) in any year

Implementation of ICRP-60 recommendations on dose limits to radiation workers in India

International Nuclear Information System (INIS)

Parthasarathy, K.S.

2000-01-01

The handling of radioactive material and radiation generating plants in India is regulated by the Atomic Energy Act, 1962 and rules issued under the Act. The Atomic Energy Regulatory Board enforces the rules. Currently, there are about 40,000 radiation workers in the country. Nearly half of them are employed in nuclear installations. During 1989, the Board considered the impact of restricting the maximum individual exposure to different values of dose limits. Through this analysis, the Board alerted all radiation users including persons responsible for radiation safety in nuclear facilities. When ICRP published ICRP-60, the Board issued directives to all radiation installations reducing the dose limit to occupational workers in a phased manner (40 mSv for 1991, 35 mSv for 1992 and 30 mSv for 1993). To meet the recommendations of ICRP-60, AERB issued a directive for the five year block 1994-1998, restricting the cumulative effective dose constraint to one hundred milliSievert (100 mSv) for individual radiation workers. Also, the annual effective dose to individual workers in any calendar year during the five-year block was restricted to thirty milliSievert (30 mSv). The stipulations of AERB are thus more conservative than those of ICRP. There was near total compliance with the dose limits by radiation installations in the country. For instance, in 1989, the number of radiation workers in nuclear power plants, who exceeded the dose level of 20 mSv/year was 9% of the total. This declined gradually to 2.2% in 1993 and 0.3% in 1997. During 1998, only 9 out of 10,145 exceeded 20 mSv/year. This has been achieved by the concerted efforts of the management, health physics staff and radiation workers. The health physicists regulated the radiation doses to workers by issuing work permits when the workers are assigned any job in high radiation areas. Appropriate training programmes are also in place. The broad guidelines to regulate radiation exposures in nuclear facilities

Dose assessment and approach to the safety for the public in the emergency. Proceedings

International Nuclear Information System (INIS)

Nakajima, Toshiyuki

1994-03-01

This issue is the collection of the papers presented at the 21st NIRS seminar on Dose Assessment and Approach to the Safety for the Public in the Emergency. The 16 of the presented papers are indexed individually. (J.P.N.)

Overview of the use of dose constraints in medical exposures

International Nuclear Information System (INIS)

Tuyisenge, J. D.

2014-01-01

The project overviewed the use of dose constraints in medical exposure in literature. Different documents on the establishment, the development and the application of this concept are reviewed with regard to the use of medical exposure of patients, including their comforters and carers or helpers, and volunteers in biomedical research. It has been showed that the concept of Dose Constraints along with many other concepts of radiation protection is widely applied in the optimisation of exposure to radiation. These concepts include Dose Limits, Dose References levels and Guidance levels among others. With regard to medical exposure of patients, it is not appropriate to apply dose limits or dose constraints, because such limits would often do more harm than good as far as benefits from such an exposure is concerned. Dose constraints do not apply with regard to any exposure of patient for his/her diagnostic or therapeutic purposes. With regard to patient comforters, carers or helpers, and volunteers in biomedical research, the benefits of such an exposure are not direct to the exposed individuals; therefore dose constraints will be appropriately applied. From the beginning of the establishment of Dose Constraints as a concept in radiation protection, the International Commission of Radiological Protection (ICRP) has published a number of documents that provide detailed application related to radiological protection and safety in the medical applications of ionising radiation. Each of these publications addresses a specific topic defined by the type of radiation source and the medical discipline in which the source is applied. This is done in the intention of communicating directly to the relevant medical radiation users, competent radiation authorities and health related institutions concerns with radiation protection and safe use of radiation sources in medical applications. This project provides an overview of such publications and related documents. (author)

Estimated dose rates to members of the public from external exposure to patients with {sup 131}I thyroid treatment

Energy Technology Data Exchange (ETDEWEB)

Dewji, S., E-mail: dewjisa@ornl.gov; Bellamy, M.; Leggett, R.; Eckerman, K. [Oak Ridge National Laboratory, 1 Bethel Valley Road, MS-6335, Oak Ridge, Tennessee 37831 (United States); Hertel, N. [Oak Ridge National Laboratory, 1 Bethel Valley Road, MS-6335, Oak Ridge, Tennessee 37831 and Georgia Institute of Technology, 770 State Street, Atlanta, Georgia 30332-0745 (United States); Sherbini, S.; Saba, M. [United States Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States)

2015-04-15

Purpose: Estimated dose rates that may result from exposure to patients who had been administered iodine-131 ({sup 131}I) as part of medical therapy were calculated. These effective dose rate estimates were compared with simplified assumptions under United States Nuclear Regulatory Commission Regulatory Guide 8.39, which does not consider body tissue attenuation nor time-dependent redistribution and excretion of the administered {sup 131}I. Methods: Dose rates were estimated for members of the public potentially exposed to external irradiation from patients recently treated with {sup 131}I. Tissue attenuation and iodine biokinetics were considered in the patient in a larger comprehensive effort to improve external dose rate estimates. The external dose rate estimates are based on Monte Carlo simulations using the Phantom with Movable Arms and Legs (PIMAL), previously developed by Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission. PIMAL was employed to model the relative positions of the {sup 131}I patient and members of the public in three exposure scenarios: (1) traveling on a bus in a total of six seated or standing permutations, (2) two nursing home cases where a caregiver is seated at 30 cm from the patient’s bedside and a nursing home resident seated 250 cm away from the patient in an adjacent bed, and (3) two hotel cases where the patient and a guest are in adjacent rooms with beds on opposite sides of the common wall, with the patient and guest both in bed and either seated back-to-back or lying head to head. The biokinetic model predictions of the retention and distribution of {sup 131}I in the patient assumed a single voiding of urinary bladder contents that occurred during the trip at 2, 4, or 8 h after {sup 131}I administration for the public transportation cases, continuous first-order voiding for the nursing home cases, and regular periodic voiding at 4, 8, or 12 h after administration for the hotel room cases. Organ

Patient and staff dose during hysterosalpinography

International Nuclear Information System (INIS)

Buls, N.; Osteaux, M.

2001-01-01

Hysterosalpingography (HSG) is a useful and widely employed technique which uses X-ray fluoroscopy to investigate the female genital tract. Fluoroscopy is assessed by a gynaecologist, a physician who is not always trained to work with ionising radiation. Dose-area product measurements in a group of 34 patients allowed an estimation of the median effective dose (0,83 mSv) and the median dose to the ovaries (1,63 mGy) of the patient per procedure. The dose to the staff was estimated using thermoluminescent dosimetry. The following median entrance surface doses were estimated per procedure: 0,22 mGy to the lens of the eye, 0,15 mGy to the neck at thyroid level and 0,19 mGy to the back of the hand. The annual eye dose limit could be exceeded if the gynaecologist is a member of the public. (author)

The concept of the effective dose

International Nuclear Information System (INIS)

Jacobi, W.

1975-01-01

Irradiation of the human body by external or internal sources leads mostly to a simultaneous exposure of several organs. However, so far no clear and consistent recommendations for the combination of organ doses and the assessment of an exposure limit under such irradiation conditions are available. Following a proposal described in ICRP-publication 14 one possible concept for the combination of organ doses is discussed in this paper. This concept is based on the assumption that at low doses the total radiation detriment to the exposed person is given by the sum of radiation detriments to the single organs. Taking into account a linear dose-risk relationship, the sum of weighted organ doses leads to the definition of an 'Effective Dose'. The applicability and consequences of this 'Effective Dose Concept' are discussed especially with regard to the assessment of the maximum permissible intake of radionuclides into the human body and the combination of external and internal exposure. (orig.) [de

Review of NCRP radiation dose limit for embryo and fetus in occupationally-exposed women - approved 1977

International Nuclear Information System (INIS)

Anon.

1978-01-01

On the basis of the current review, the NCRP has decided to make no change in the current recommendation of its radiation dose limit to the unborn. The NCRP recommendation is restated here as follows: During the entire gestation period, the maximum permissible dose equivalent to the embryo-fetus from occupational exposure of the expectant mother should be 0.5 rem. Since the preparation of the 1971 report there has been no new evidence concerning teratogenic or carcinogenic effects of irradiation of the embryo-fetus that would justify a change in the limit in either direction. It is implicit in this position and recommendation that women who can reasonably be expected to be pregnant should not, in certain instances, be exposed to the same radiation environment as women who are not considered fertile or as men. This applies particularly to conditions where radiation workers can receive dose equivalents of 0.5 rem or more in short periods

Effective dose evaluation of NORM-added consumer products using Monte Carlo simulations and the ICRP computational human phantoms

International Nuclear Information System (INIS)

Lee, Hyun Cheol; Yoo, Do Hyeon; Testa, Mauro; Shin, Wook-Geun; Choi, Hyun Joon; Ha, Wi-Ho; Yoo, Jaeryong; Yoon, Seokwon; Min, Chul Hee

2016-01-01

The aim of this study is to evaluate the potential hazard of naturally occurring radioactive material (NORM) added consumer products. Using the Monte Carlo method, the radioactive products were simulated with ICRP reference phantom and the organ doses were calculated with the usage scenario. Finally, the annual effective doses were evaluated as lower than the public dose limit of 1 mSv y"−"1 for 44 products. It was demonstrated that NORM-added consumer products could be quantitatively assessed for the safety regulation. - Highlights: • Consumer products considered that NORM would be included should be regulated. • 44 products were collected and its gamma activities were measured with HPGe detector. • Through Monte Carlo simulation, organ equivalent doses and effective doses on human phantom were calculated. • All annual effective doses for the products were evaluated as lower than dose limit for the public.

Transuranium element toxicity: dose-response relationships at low exposure levels. Summary and speculative interpretation relative to exposure limits

International Nuclear Information System (INIS)

Thompson, R.C.

1975-01-01

A summary is given of information on transuranium element toxicity and the correlation of this information with current established exposure limits. It is difficult to calculate a biologically relevant radiation dose from deposited plutonium; it is exposure that must be controlled in order to prevent biological effect, and if the relationship between exposure and effect is known, then radiation dose is of no concern. There are extensive data on the effects of plutonium in bone. Results of studies at the University of Utah indicate that plutonium in beagles may be as much as ten times more toxic than radium. It has been suggested that this toxicity ratio may be even higher in man than in the beagle dog because of differences in surface-to-volume ratios and differences in the rate of burial of surface-deposited plutonium. The present capabilities for extrapolating dose-effect relationships seem to be limited to the setting of upper limits, based on assumptions of linearity and considerations related to natural background

Comments about the application of the dose limitation system in Spain

International Nuclear Information System (INIS)

Diaz de la Cruz, F.; Gil Lopez, E.

1982-01-01

The problems arising from the application of the Dose Limitation System (DLS) established by ICRP and recommended by I.A.E.A. are presented. The Spanish Nuclear Regulatory Body has tried to set numerical guides to develop the criteria included in the DLS concept during the licensing process of nuclear instalations and isotopes uses in order to guarantee to the population not only the respect of the authorised limits but also that the instalations and practices are justified and optimised. All efforts have been useless. The cost quantification of the protection systems present marketing and maintenance problems that lead to meaningless estimations. Besides the evaluation of the radiological detriment as function of the collective dose by means of the price of the sievert-person adds two more difficulties: the first one is intrinsic to the hypothesis made and the second one is the discrimination over different population groups resulting from monetary fluctuations in inflation ist economies. The authors have developped a method spanding the detriment concept to the whole environment (not only the man) arriving to an easy way to make an effective optimization. The method is based in the quantification of the degradation energy released to the surroundings by means of a price assigned to the kw-hr. This price can dissuade the licensee and oblige him for economical reasons to select a more effective retention systems and/or a better operation.(author)

Radiation protection principles as applied to the disposal of long-lived solid radioactive waste and protection of the public. Commentary of ICRP publication 81 and publication 82

International Nuclear Information System (INIS)

Kosako, Toshiso

2001-01-01

This commentary is for ICRP Publication 81 concerning the disposal of long-lived solid radioactive waste to which the Publication 82 giving theoretical basis for protection of the public exposed for a long period. The primary object for prevention is the public in this disposal, which is quite different from the concept hitherto where the object is the facility. The essential points in the prevention are the definition and direction for the protection of future generations, critical group, potential exposures, protection optimization, principles in the technology and management, consistency of the principle, and evidence of observance to radiological standards. Dose constraint of 0.3 mSv/y or 10 -5 risk, reasonable measures taken for reduction of probable human invasion of its influence and observance to technological and control principles are recommended. Publication 82 principally describes and discusses the reference level for intervention and dose limits to the public due to action.(K.H.)

Determination of carcinogenic threshold limit values using the tumorigenic dose rate 50% (TD50)

International Nuclear Information System (INIS)

Bonvalot, Y.; Oudiz, A.; Hubert, P.; Abenhaim, L.

1989-01-01

The objective of the present study is to propose a simple procedure for the determination of Occupational Limit Values (OLVs) based on the TD 50 concept (Tumorigenic Dose Rate 50%). The TD 50 concept was introduced by Peto R. and al. to help classify chemical substances according to their carcinogenic potency. The TD 50 is that dose rate (in mg/KXg body weight/day) which, if administered chronically for the standard lifespan of the species will halve the probability of remaining tumorless throughout that period. Using TD 50 values available for 776 substances, the procedure presented here allows one to determine OLVs corresponding to a fixed excess risk. It is based on a mathematical high-to-low doses extrapolation of the TD 50 . OLVs obtained with this procedure are compared with currently available TLVs and other occupational guidelines. (author)

Assessment of prospective foodchain doses from radioactive discharges from BNFL Sellafield

International Nuclear Information System (INIS)

Ould-Dada, Z.; Tucker, S.; Webbe-Wood, D.; Mondon, K.; Hunt, J.

2002-01-01

This paper presents the method used by the UK Food Standards Agency (FSA) to assess the potential impact of proposed radioactive discharges from the Sellafield nuclear site on food and determine their acceptability. It explains aspects of a cautious method that has been adopted to reflect the UK government policy and uncertainties related to people's habits with regard to food production and consumption. Two types of ingestion doses are considered in this method: 'possible' and 'probable' doses. The method is specifically applied to Sellafield discharge limits and calculated possible and probable ingestion doses are presented and discussed. Estimated critical group ingestion doses are below the dose limit and constraint set for members of the public. The method may be subject to future amendments to take account of changes in government policy and the outcome of a recent Consultative Exercise on Dose Assessments carried out by FSA. Uncertainties inherent in dose assessments are discussed and quantified wherever possible

Annual limits on intake of radionuclides by workers based on the 1990 recommendations

International Nuclear Information System (INIS)

1991-01-01

The Commission's new radiation protection recommendations (ICRP, 1991) were developed to take into account new biological information related to the detriment associated with radiation exposures and supersede earlier recommendations in Publication 26 (ICRP, 1977). Adoption of the recommendations necessitates a revision in the Commission's secondary limits contained in Publication 30, Parts 1-4 (ICRP, 1979a, 1980, 1981b, 1988). In order to permit immediate application of these new recommendations, new values of the Annual Limits on Intake (ALIs) which incorporate the new dose limits, radiation weighting factors, and tissue weighting factors and the metabolic and biokinetic information from Publication 30 have been calculated. Presented here are secondary limits for the 1990 Recommendations based on the dosimetric data assembled during the preparation of Publication 30. (author)

76 FR 46357 - Notice of Limitation on Claims Against Proposed Public Transportation Projects

Science.gov (United States)

2011-08-02

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Notice of Limitation on Claims Against Proposed Public Transportation Projects AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice... that FTA has taken final agency actions by issuing certain approvals for the public transportation...

Radiation dose to Sri Lankan infants from Caesium-137 in contaminated milk

International Nuclear Information System (INIS)

Hewamanna, R.; Dias, M.P.

1999-01-01

The radiation dose to infants due to ingestion of milk containing the maximum limit of radioactivity in milk powder imported to Sri Lanka has been calculated. The radioactivity of Cs-137 was used as an index of fission products for setting radioactivity limits. The computation for milk powder was based on an average daily intake of 125 g by infants, (a critical group of population) during the first year after birth. The recommended dose commitment to the general public is 1 mSv/y. The maximum permissible limit of 20 Bq/kg of Cs-137 in milk powder as stipulated by the Atomic Energy Authority for milk powder imported to Sri Lanka would yield a dose equivalent of 12.6 micro seivert/y from Cs-137

External contamination and skin dose. From ICRP and regulations to skin dose evaluation in practice

International Nuclear Information System (INIS)

Le Coulteulx, I.; Apretna, D.; Beaugerie, M.; Fenolland, J.; Frey, R.; Gonin, M.; Landry, B.; Laporte, E.; Le Guen, B.; Leval, D.

2006-01-01

Dose limitation to the skin is an objective of radiation protection. Our aim is to propose in case of skin contamination in EDF NPPs a simply, quickly and reproducible procedure for evaluating skin dose. French regulation admit an annual limit for skin dose over one square centimeter equal to 500 mSv. ICRP Publication 26 and 60 recommend that dose assessment be performed only if skin dose might be equal to or more than 50 mSv at basal cells. To respect this recommendation, an alert value (A) must be determined. This value is the lowest value of measurement from which dose assessment has to be made, based on the hypothesis that uninterrupted work time in controlled area is no more than four hours. This alert value (A) has been established for three external detection equipments, and for the ten radionuclides commonly detected. In case of external contamination, a first measurement is performed. If the value exceeds value (A), other measurements are instituted because skin dose evaluation needs to know other parameters as: - the radioactivity of the most contaminated square centimeter of the skin, - the identity of the radionuclides and their relative proportion. At the same time, we have to evaluate the length of the exposure. At last, we use different compiled results in a program developed from excel software which allow to calculate automatically the skin dose. This work has allowed us to publish an occupational health guideline about the assessment of skin dose in case of external contamination in EDF NPPs and to create an information booklet for workers. The authors propose to examine used methodology and to demonstrate the software. (authors)

77 FR 26818 - Notice of Limitation on Claims Against Proposed Public Transportation Projects

Science.gov (United States)

2012-05-07

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Notice of Limitation on Claims Against Proposed Public Transportation Projects AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice... public transportation projects listed below. The actions on these projects, as well as the laws under...

Estimating the increment of dose in members of the public due to discharges from norm facilities located in high background areas

International Nuclear Information System (INIS)

Lauria, Dejanira da Costa; Rochedo, Elaine R.R.

2008-01-01

Focusing on the environmental monitoring of a monazite facility located in a region which environmental media contain a large range of values of natural radionuclide concentration, this paper addresses the challenge of applying radiological protection standards to facilities when considering the heterogeneous radionuclides distribution in the environment. By side of the dose due immersion in its water, the conceptual model pointed out the lagoon water as the main route for the contamination of fish, milk and beef. However, in the lagoon watercourse the contents of 228 Ra and 226 Ra vary from 0.08 to 0.36 Bq/l and 0.12 to 1.52 Bq/l, respectively; additionally, natural variability on the content of the main radionuclides in food ranges, e.g., from 226 Ra and 0.01 to 0.60 Bq/l for 228 Ra in milk, and from 0.15 to 1.37 Bq/kg for 226 Ra and 0.20 to 2.88 Bq/kg for 228 Ra in fish. To comply with an optimised dose level below a dose constraint that is lower than the dose limit for the public, as defined in Brazilian standards, may be a difficult task as dose sums up over several different exposure pathways. The total natural variability, including several environmental pathways, such as external exposure and ingestion of water, milk and fish, is far larger (values ranging from 0.5 to 2.7 mSv/y) than the increment of dose to comply with (value of 0.3 mSy/y). (author)

The history of critical group doses from the consumption of freshwater fish at Trawsfynydd, North Wales

International Nuclear Information System (INIS)

Leonard, D.R.P.

1992-01-01

Radionuclides discharged into the aquatic environment from Trawsfynydd power station are, as for all UK facilities, subject to statutory controls to ensure that the resulting public radiation exposure complies with nationally-accepted criteria. Environmental monitoring by MAFF has shown that near this facility the consumption of freshwater fish is radiologically the most important pathway with Cs-137 the dominant radionuclide. Information gathered from consumers over a twenty-five year period has been interpreted so as to derive doses to the public. Committed effective doses (CEDs) are presented using ICRP 1990 methodology and compared with the recommended dose limit of 1 mSv year -1 . Doses to the critical group are shown to have exceeded 1 mSv year -1 for two years but do not exceed this limit when averaged over a period of 5 years. Because of the changing habits of the consumers it is suggested that the average annual CED over the lifetime of any member of the public will not exceed 1 mSv year -1 during the operation of the station. (author)

Forming perceptions and the limits to public participation on ocean commons

DEFF Research Database (Denmark)

Hadjimichael, Maria; Delaney, Alyne

2017-01-01

Public views of, and public participation in, the management of commons are increasingly being recommended and sought after in environmental management processes. Yet, given the limits of today’s liberal democracy, what are the weaknesses? This article presents data from a citizens jury......-inspired deliberative workshop held to tease out stakeholder views of management priorities for a section of the North Sea: the Dogger Bank. As this article reveals, the lessons learned from the Dogger Bank workshop advocate not simply what is required for managing one particular ocean commons, but also highlight some...... of the public participation research design failings, taking public participation in resource management further by adding to the literature and theoretical discussions on the public sphere (Habermas 1989). Analysis of the citizens jury-inspired deliberative workshop also highlights the critical issue of power...

76 FR 4150 - Notice of Limitation on Claims Against Proposed Public Transportation Projects

Science.gov (United States)

2011-01-24

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Notice of Limitation on Claims Against Proposed Public Transportation Projects AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice... public transportation project will be barred unless the claim is filed on or before July 25, 2011. FOR...

76 FR 55470 - Notice of Limitation on Claims Against Proposed Public Transportation Project

Science.gov (United States)

2011-09-07

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Notice of Limitation on Claims Against Proposed Public Transportation Project AGENCY: Federal Transit Administration (FTA), DOT. ACTION: Notice... announced herein for the listed public transportation project will be barred unless the claim is filed on or...

Means of control of the public authorities as participants in public limited energy supply companies

International Nuclear Information System (INIS)

Kermel, C.

1994-01-01

Despite the fundamental studies by Emmerich and Puettner, the control of publicly owned companies by the state as a majority shareholder has not evolved to a generally accepted form. With a mind to the discussion on a nuclear phase-out at Hamburgische Electrizitaetswerke AG the author examines the scope offered by the law on public limited companies for realising the interests of the state as a shareholder. She arrives at interesting conclusions regarding the means to this end and the legal consequences of a phase-out decision. Lower supply companies are an ideal object of study for the purposes of this work. (orig./UA) [de

Aquatic toxicity testing of liquid hydrophobic chemicals – Passive dosing exactly at the saturation limit

DEFF Research Database (Denmark)

Stibany, Felix; Nørgaard Schmidt, Stine; Schäffer, Andreas

2017-01-01

The aims of the present study were (1) to develop a passive dosing approach for aquatic toxicity testing of liquid substances with very high Kow values and (2) to apply this approach to the model substance dodecylbenzene (DDB, Log Kow = 8.65). The first step was to design a new passive dosing...... format for testing DDB exactly at its saturation limit. Silicone O-rings were saturated by direct immersion in pure liquid DDB, which resulted in swelling of >14%. These saturated O-rings were used to establish and maintain DDB exposure exactly at the saturation limit throughout 72-h algal growth...... at chemical activity of unity was higher than expected relative to a reported hydrophobicity cut-off in toxicity, but lower than expected relative to a reported chemical activity range for baseline toxicity. The present study introduces a new effective approach for toxicity testing of an important group...

Methods of assessment of individual and collective doses to transport workers and members of the public during the transport of radioactive material

International Nuclear Information System (INIS)

Vohra, K.G.; Subrahmanian, G.; Nandakumar, A.N.; Kher, R.K.; Iyer, S.R.K.

1986-01-01

Transport workers handling radioactive cargoes are generally exposed to the highest dose rates of any population group. Methods of assessment of dose received by transport workers are studied to arrive at a useful method. An empirical model based on a detailed work study of individuals handling radioactive cargoes and the exposure rates at various distances from specific individual packages is developed. The personnel doses thus calculated compared reasonably well with the doses recorded on personnel monitoring badges. The personnel doses were also evaluated with reference to the total transport index handled by the workers, yielding results consistent with those reported elsewhere by earlier researchers. For assessing the collective dose to the public due to urban transport of radioactive material, the space around the vehicle transporting cargo was divided into a number of cells of dimensions 1mx1m. The radiation level in each cell was measured and the pedestrian density along the route was obtained. Using the pedestrian occupancy in the cells and the measured radiation levels, the total dose to the public was assessed. A similar assessment was made with respect to the passengers in the neighbouring vehicles. The suggested method of calculation may aid determination of the route and time of transport and the preferable traffic configuration for the vehicle carrying the radioactive consignments for optimizing the dose to the urban public

Dose apportionment using statistical modeling of the effluent release

International Nuclear Information System (INIS)

Datta, D.

2011-01-01

Nuclear power plants are always operated under the guidelines stipulated by the regulatory body. These guidelines basically contain the technical specifications of the specific power plant and provide the knowledge of the discharge limit of the radioactive effluent into the environment through atmospheric and aquatic route. However, operational constraints sometimes may violate the technical specification due to which there may be a failure to satisfy the stipulated dose apportioned to that plant. In a site having multi facilities sum total of the dose apportioned to all the facilities should be constrained to 1 mSv/year to the members of the public. Dose apportionment scheme basically stipulates the limit of the gaseous and liquid effluent released into the environment. Existing methodology of dose apportionment is subjective in nature that may result the discharge limit of the effluent in atmospheric and aquatic route in an adhoc manner. Appropriate scientific basis for dose apportionment is always preferable rather than judicial basis from the point of harmonization of establishing the dose apportionment. This paper presents an attempt of establishing the discharge limit of the gaseous and liquid effluent first on the basis of the existing value of the release of the same. Existing release data for a few years (for example 10 years) for any nuclear power station have taken into consideration. Bootstrap, a resampling technique, has been adopted on this data sets to generate the population which subsequently provide the corresponding population distribution of the effluent release. Cumulative distribution of the population distribution obtained is constructed and using this cumulative distribution, 95th percentile (upper bound) of the discharge limit of the radioactive effluents is computed. Dose apportioned for a facility is evaluated using this estimated upper bound of the release limit. Paper describes the detail of the bootstrap method in evaluating the

Ethical issues related to professional exposure of pregnant women in the medical field: monitoring and limiting effective dose.

Science.gov (United States)

Santos, J A M; Nunes, R

2011-03-01

The International Commission on Radiological Protection recommendations for occupational exposed pregnant women do not imply necessarily the complete avoidance of work with radiation or radioactive materials. Instead, a careful review of the exposure conditions, once the pregnancy is declared, as part of the exercise of the ICRP optimisation principle (based in a teleological ethics point of view) is suggested. The dose limitation (following a deontological ethics point of view) of the fetus/embryo is, however, not clearly well established as happens in the case of workers or members of the public. Also, the justification of practices (to continue to work or not with radiation or radioactive materials) is not clearly addressed in most national or international recommendations. An analysis of this justification (bearing in mind both teleological and deontological ethics) is examined in this work having in mind the best interest of the child-to-be as well as other existing social and economical factors.

Ethical issues related to professional exposure of pregnant women in the medical field: Monitoring and limiting effective dose

International Nuclear Information System (INIS)

Santos, J. A. M.; Nunes, R.

2011-01-01

The International Commission on Radiological Protection recommendations for occupational exposed pregnant women do not imply necessarily the complete avoidance of work with radiation or radioactive materials. Instead, a careful review of the exposure conditions, once the pregnancy is declared, as part of the exercise of the ICRP optimisation principle (based in a teleological ethics point of view) is suggested. The dose limitation (following a deontological ethics point of view) of the fetus/embryo is, however, not clearly well established as happens in the case of workers or members of the public. Also, the justification of practices (to continue to work or not with radiation or radioactive materials) is not clearly addressed in most national or international recommendations. An analysis of this justification (bearing in mind both teleological and deontological ethics) is examined in this work having in mind the best interest of the child-to-be as well as other existing social and economical factors. (authors)

Implications of the new dose limit crystalline in operational radiation protection in interventional medicine

International Nuclear Information System (INIS)

Roch Gonzalez, M.; Garcia Castanon, P.; Giner Sala, M.; Rodriguez Martin, G.; Espana Lopez, M. L.

2013-01-01

The objective of this study is to evaluate the implications of this new limit of equivalent dose in the lens can be assumed in the radiation protection of cardiologists, radiologists, nursing professionals, etc. that perform their work in units of intervention, both in terms of additional protective measures and the classification of them as workers exposed. (Author)

Reappraisal of the reference dose distribution in the UNSCEAR 1977 report

International Nuclear Information System (INIS)

Kumazawa, Shigeru

2008-01-01

This paper provides the update of the reference dose distribution proposed by G.A.M. Web and D. Beninson in Annex E to the UNSCEAR 1977 Report. To demonstrate compliance with regulatory obligations regarding doses to individuals, they defined it with the following properties: 1) The distribution of annual doses is log-normal; 2) The mean of the annual dose distribution is 5 m Gy (10% of the ICRP 1977 dose limit); 3) The proportion of workers exceeding 50 m Gy is 0.1%. The concept of the reference dose distribution is still important to understand the inherent variation of individual doses to workers controlled by source-related and individual-related efforts of best dose reduction. In the commercial nuclear power plant, the dose distribution becomes the more apart from the log-normal due to the stronger ALARA efforts and the revised dose limits. The monitored workers show about 1 m Sv of annual mean and far less than 0.1% of workers above 20 m Sv. The updated models of dose distribution consist of log-normal (no feedback on dose X) ln(X)∼N(μ,σ 2 ), hybrid log-normal (feedback on higher X by ρ) hyb(ρX)=ρX+ln(ρX)∼N(μ,σ 2 ), hybrid S B (feedback on higher dose quotient X/(D-X) not close to D by ρ) hyb[ρX/(D.X)]∼N(μ,σ 2 ) and Johnson's S B (limit to D) ln[X/(D-X)]∼N(μ,σ 2 ). These models afford interpreting the degree of dose control including dose constraint/limit to the reference distribution. Some of distributions are examined to characterize the variation of doses to members of the public with uncertainty. (author)

New ICRP recommendations on occupational limits for radon daughters

International Nuclear Information System (INIS)

Jacobi, W.

1981-01-01

The ICRP has recommended in 1959 for the first time a maximum permissible concentration (MPC) for the occupational exposure to radon and its short-lived daughters. Since this time more realistic dosimetric models for radon daughters have been developed. Taking into account epidemiological and new dosimetric findings the ICRP has adopted in March this year new recommendations on occupational limits for inhalation of 222 Rn, 220 Rn and their short-lived daughters. This report will be published this year as ICRP Publication 32 (ICRP 1981). The recommended limits for radon daughters were derived from the basic dose and risk limits as they were proposed by ICRP in its new basic recommendations (ICRP Publ. 26, 1977). In the following this basic system of dose limitation is shortly outlined before the special recommendations for radon daughters are described

Dose apportionment for BARC facilities

International Nuclear Information System (INIS)

Preetha, J.; Sundar, D.; Munshi, S.K.; Pradeepkumar, K.S.

2017-01-01

One of the important responsibilities of BARC Safety Council (BSC) is to ensure that appropriate measures are in place to protect the members of the public and the environment from the undue effects of radioactive releases from the facilities regulated by BSC. It is with this aim in mind that a Standing Committee for Dose Apportionment (DAC) was constituted by BSC in 2005, to ensure that the limits are set by the regulatory body for release of low-level gaseous and liquid effluents into the environment from BARC facilities. There are three Committees for dose apportionment constituted by the Chairman, BSC, viz, DAC-TK for Tarapur and Kalpakkam facilities, DAC-TV for Trombay and DACSF for specific faculties

Application of the Dose Limitation System to the Mining and Milling of Radioactive Ores

International Nuclear Information System (INIS)

1987-01-01

This publication is one of the Safety Guides to the Code of Practice on Radiation Protection of Workers in the Mining and Milling of Radioactive Ores, 1983 Edition, which was published as a joint IAEA/ILO/WHO publication (IAEA Safety Series No.26). This Safety Guide is intended to demonstrate as well as facilitate the application of the principles of optimization in the control of risk among the workers engaged in the mining and milling of radioactive ores and to give some guidance on suitable technology. The International Atomic Energy Agency, jointly with the World Health Organization, the International Labour Organisation and the OECD Nuclear Energy Agency, published the Basic Safety Standards for Radiation Protection, 1982 Edition (IAEA Safety Series No. 9). The Basic Safety Standards outline the principles of radiation protection and also the basic requirements to be followed in the implementation of radiation protection control. These principles are further developed in the case of mining and milling of radioactive ores in the joint IAEA/ILO/WHO Code of Practice on Radiation Protection of Workers in the Mining and Milling of Radioactive Ores (IAEA Safety Series No. 26). This Safety Guide on the Application of the Dose Limitation System to the Mining and Milling of Radioactive Ores was prepared by an Advisory Group which met for the first time in Portoroz, Yugoslavia, from 22 to 26 August 1983, and then again from 6 to 10 August 1984, in Vienna. Following the second Advisory Group meeting the draft was further reviewed by A. Dory from Canada who also was a participant of the two Advisory Group meetings held earlier. After the consultant's review the draft was circulated among the members of the Advisory Group for a further check. The final version of the draft was prepared by the Secretariat with the help of a consultant

Age-dependent conversion coefficients for organ doses and effective doses for external neutron irradiation

International Nuclear Information System (INIS)

Nishizaki, Chihiro; Endo, Akira; Takahashi, Fumiaki

2006-06-01

To utilize dose assessment of the public for external neutron irradiation, conversion coefficients of absorbed doses of organs and effective doses were calculated using the numerical simulation technique for six different ages (adult, 15, 10, 5 and 1 years and newborn), which represent the member of the public. Calculations were performed using six age-specific anthropomorphic phantoms and a Monte Carlo radiation transport code for two irradiation geometries, anterior-posterior and rotational geometries, for 20 incident energies from thermal to 20 MeV. Effective doses defined by the 1990 Recommendation of ICRP were calculated from the absorbed doses in 21 organs. The calculated results were tabulated in the form of absorbed doses and effective doses per unit neutron fluence. The calculated conversion coefficients are used for dose assessment of the public around nuclear facilities and accelerator facilities. (author)

Autoblocking dose-limiting normal structures within a radiation treatment field: 3-D computer optimization of 'unconventional' field arrangements

International Nuclear Information System (INIS)

Bates, Brian A.; Cullip, Timothy J.; Rosenman, Julian G.

1995-01-01

Purpose/Objective: To demonstrate that one can obtain a homogeneous dose distribution within a specified gross tumor volume (GTV) while severely limiting the dose to a structure surrounded by that tumor volume. We present three clinical examples below. Materials and Methods: Using planning CT scans from previously treated patients, we designed variety of radiation treatment plans in which the dose-critical normal structure was blocked, even if it meant blocking some of the tumor. To deal with the resulting dose inhomogeneities within the tumor, we introduced 3D compensation. Examples presented here include (1) blocking the spinal cord segment while treating an entire vertebral body, (2) blocking both kidneys while treating the entire peritoneal cavity, and (3) blocking one parotid gland while treating the oropharynx in its entirety along with regional nodes. A series of multiple planar and non-coplanar beam templates with automatic anatomic blocking and field shaping were designed for each scenario. Three-dimensional compensators were designed that gave the most homogeneous dose-distribution for the GTV. For each beam, rays were cast from the beam source through a 2D compensator grid and out through the tumor. The average tumor dose along each ray was then used to adjust the compensator thickness over successive iterations to achieve a uniform average dose. DVH calculations for the GTV, normal structures, and the 'auto-blocked' structure were made and used for inter-plan comparisons. Results: These optimized treatment plans successfully decreased dose to the dose-limiting structure while at the same time preserving or even improving the dose distribution to the tumor volume as compared to traditional treatment plans. Conclusion: The use of 3D compensation allows one to obtain dose distributions that are, theoretically, at least, far superior to those in common clinical use. Sensible beam templates, auto-blocking, auto-field shaping, and 3D compensators form a

Public involvement in the dose reconstruction study: the colorado story

International Nuclear Information System (INIS)

Morin, Norma C.; Lockhart, Ann J.

2000-01-01

Public involvement was a critical component for building awareness, trust, and credibility for the dose reconstruction study for the Rocky Flats Nuclear Weapons Facility in Colorado. The research team developed a process to inform, involve, and encourage public participation over the nine-year study period. Key affected and interested groups with a legitimate stake in the study were identified and invited to identify concerns and offer suggestions for the study. In many cases, the public actually provided direction for the research. Many issues were studied more in-depth as result of public concern. Proactive community outreach was undertaken; quarterly public meetings and workshops were held to inform the public about the study's progress and to hear their comments. Quarterly newsletters were mailed to stake holders. A speaker's bureau was established and more than 50 presentations were made to 1,500 community members in various civic, business, neighborhood, and technical groups. Fact sheets, citizen summaries of technical reports, technical topic papers, and a video were developed to provide a complete overview of the studies and the findings at the conclusion of the project. The video was provided to local cable television stations, and publications were taken to local libraries. A web site was developed to allow the public to readily access information and to order technical reports. Public comments on draft technical reports were solicited; questions and concerns were addressed and investigated. The staff answered citizen calls, and the research team responded in writing to more than 200 issues raised by very concerned citizens. In addition, a citizen's group was formed in 1992 to conduct an independent study of plutonium levels found in soil samples collected around Rocky Flats. Made up of homeowners, public interest groups, local health departments, interested citizens, and Health Advisory Panel members, the committee arranged for sampling and analysis of

Estimation of effective dose to public from external exposure to natural background radiation in saudi arabia

International Nuclear Information System (INIS)

Khalid, A. A.

2003-01-01

The effective dose values in sixteen cities in Saudi Arabia due to external exposure to natural radiation were evaluated. These doses are based on natural background components including external exposure to terrestrial radiation and cosmic rays. The importance of evaluating the effective dose to the public due to external exposure to natural background radiation lies in its epidemiological and dosimetric importance and in forming a basis for the assessment of the level of radioactive contamination or pollution in the environment in the future. The exposure to terrestrial radiation was measured using thermoluminescent dosimeters (TLD). The exposure from cosmic radiation was determined using empirical correlation. The values evaluated for the total annual effective dose in all cities were within the world average values. The highest total annual effective dose measured in Al-Khamis city was 802 μSv/y, as compared to 305 μSv/y in Dammam city, which was considered the lowest value

Estimation of Collective Effective Dose Due to Cosmic Ray Exposures to Members of The Public and to Airline Passenger

International Nuclear Information System (INIS)

Sayed, N.S.; Salah Eldin, T.; Gomaa, M.A.; El Dosoky, T.M.

2011-01-01

Using UNSCEAR 2000 report to United Nation General Assembly and its appendices, Annual collective dose to Egyptian members of the public (75097301). Was estimated to be 252.5 man Sv , hence the average collective effective dose to air line passenger for 10 million is estimated as 25.25 micro Sievert. Furthermore using hypothetical approach for Egyptian passengers who fly locally, regionally and internationally, the collective dose was estimated to be 252.5 man Sv , hence the average average collective effective dose for Egyptian passenger is due to Aviation is 3.36 micro Sievert

Luminescence dose reconstruction using personal objects and material available in the environment and public domain

International Nuclear Information System (INIS)

Goeksu, H. Y.

2006-01-01

There is a growing concern in the public about accidental radiation exposures due to the ageing of the nuclear power industry, illegal dumping of nuclear waste, or terrorist activities which may increase the health risks to individuals or large numbers of public. In cases where no direct radiation monitoring data are available, luminescence dose reconstruction obtained using material from the immediate environment of population or persons can be used to validate values obtained from the numerical simulations. In recent years, especially after the Chernobyl accident, techniques and methodology of luminescence dose reconstruction using fired building material have advanced to such an extent that radiation from anthropogenic sources as low as 10 mGy can be resolved within two years after the event. It was demonstrated that luminescence measurements using bricks combined with Monte-Carlo simulations of photon transport for a given source geometry and distribution can provide quantities to derive doses for populations or groups of people living in contaminated areas that can be used for epidemiological studies. In this presentation, recent approaches in luminescence dose reconstruction using un-fired building materials such as concrete and silica brick will be reviewed and the possible use of personal artefacts such as telephone chip cards or prosthetic and restorative teeth will be discussed. The review will include the results of the joint efforts of the international team supported by the EU at the Chernobyl affected territories, areas affected due to activities of Plutonium production facilities in Southern Urals (Russia), and settlements around the Semipalatinsk nuclear bomb test sites

The practical application of ICRP recommendations regarding dose-equivalent limits for workers to staff in diagnostic X-ray departments

International Nuclear Information System (INIS)

Gill, J.R.; Beaver, P.F.; Dennis, J.A.

1980-01-01

Members of hospital staff who work in the X-ray room with patients, wear lead aprons to protect their bodies. These aprons greatly reduce the radiation dose rate at the surface of the body underneath the apron, but do not give any protection to parts of the body not covered by the apron, especially the head, neck, arms and legs. The ICRP's system of dose limitation for non-uniform irradiation of the body has been applied to exposure of this kind and a simple formula has been derived that permits the calculation of a good approximation to the effective dose-equivalent, using two dosemeters. One dosemeter is worn at chest or waist level under the apron to monitor the dose-equivalent received by protected organs while the other is worn on the collar or forehead to monitor the head and neck. Evidence based on published data is presented that suggests that in work of this nature, contrary to earlier opinion, the limiting factor is the dose equivalent received by the organs of the head and neck. The implications of this conclusion for routine personal monitoring are discussed. (H.K.)

Regulatory actions towards dose reduction at Atucha 1 NPS

International Nuclear Information System (INIS)

Spano, F.; Curti, A.R.; Telleria, D.M.; Rudelli, M.D.

1998-01-01

Atucha 1, a nuclear power plant designed in the late sixties, is in commercial operation since June 1974. In some internal components such as the coolant channels, the station has Stellite-6, a high cobalt content alloy (up to 60%) for hard-facing application. The erosion and corrosion processes on the surfaces of the piping components of the primary coolant and moderator systems generate a varied type of particles oxides called 'crud'. The crud and cobalt 60 produced by neutron activation of cobalt are transferred by the water along the circuit of the coolant and moderator systems, producing deposits on internal surfaces. The cobalt deposits are dominant in radiation fields at working locations. For years, the Authority allowed a considerable number of station workers incurring doses near the limit since that installation had been built previously to introduction of the optimisation concept by ICRP publication 26. The recommendations included in ICRP publication 60 made more than difficult the radiological situation at the Atucha 1. For the facility, to comply with the new limit established by the Authority in January 1995, meant to carry out a substantial modification of the radiological conditions, specially the radiation fields due to cobalt 60. Some options to reduce individual and collective doses were analysed by the Authority. To carry out the evaluation of the deposit mechanisms and the real activity level of cobalt 60, a model of compartments connected by means of constant transfer coefficients was designed. It was concluded that there was a necessity to the change of coolant channels by new ones free of cobalt. It has been shown experimentally that radiation fields and occupational doses were reduced, due to the replacement programme carried out by the utility, in a similar way to the model predictions. At present after more than three years from the beginning of the application of the new limits, and after carrying out partially the tasks for the

Controllable dose: the ICRP discussion paper does not go far enough

International Nuclear Information System (INIS)

Carter, M.W.

2000-01-01

The current ICRP recommendations and the associated dosimetry have confused the public, lawyers and politicians and have been the subject of dissension within the Health Physics Community. Currently recommended limits are different for occupational exposure, exposure of the public, exposure to radon in dwellings and exposure to radon in workplaces. Current recommendations do not cover exposure in accident situations. The recommended limits do not apply to natural background radiation exposures. This suggests that the unit of radiation dose is variable depending on the circumstances and that artificially produced radiation is more harmful than natural radiation. The use of collective dose and the LNT model has resulted, in the opinion of some, in waste of money spent in trying to reduce doses that may be already too small to produce detectable harm. The recent discussion papers (Clarke, 1998, Clarke 1999), introducing the concept of controllable dose, are a valuable starting point for changing and improving the basis on which regulations are made. It is the author's opinion that the discussion paper does not go far enough and that the confusion is largely the result of failing to separate the scientific aspects from the regulatory aspects of controlling radiation dose. Only by making such a separation can we provide understandable regulations without compromising scientific research into radiation risks. Copyright (2000) Australasian Radiation Protection Society Inc

76 FR 78332 - Amended Notice of Limitation on Claims Against Proposed Public Transportation Project

Science.gov (United States)

2011-12-16

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Amended Notice of Limitation on Claims Against Proposed Public Transportation Project AGENCY: Federal Transit Administration (FTA), DOT. ACTION... actions announced herein for the listed public transportation project will be barred unless the claim is...

OCCUPATIONAL DOSE DURING ADULT INTERVENTIONAL CARDIOLOGY: FIRST VALUES WITH PERSONAL ACTIVE DOSIMETERS IN CHILE.

Science.gov (United States)

Ubeda, Carlos; Morales, Claudio; Gutiérrez, Diego; Oliveira, Marcus; Manterola, Carlos

2018-05-11

The objective of this article is to present initial occupational dose values using digital active personal dosimeters for medical staff during adult interventional cardiology procedures in a public hospital in Chile. Personal dose equivalent Hp(10) over the lead apron of physician, nurse and radiographer were measured during 59 procedures. Mean values of occupational dose Hp(10) per procedure were 47.6, 6.2 and 4.3 μSv for physician, nurse and radiographer, respectively. If no protective tools are used, physician dose can exceed the new eye lens dose limit.

Case study on implementation of the dose constraint concept in optimization in working environment

Energy Technology Data Exchange (ETDEWEB)

Krajewska, Grazyna; Krajewski, Pawel [Central Laboratory for Radiological Protection, PL-03194, Warsaw (Poland)

2014-07-01

A case study of already fixed dose constrain values in nuclear medicine sector, indicated that, the practical implementation of ICRP principle of optimization ( Publication 103, ICRP, 2007) still hit on methodology problems due to lack of adequate numerous monitoring data of internal contamination and complicated mathematical formalism. In practice, to ensure that 'the likelihood of incurring exposure, the number of people exposed, and the magnitude of their individual doses are kept as low as reasonably achievable', the baseline of effective doses together with statistical distribution is required. Furthermore, as it has revealed in this study, doses PHP's generated with MC methods had un-regularly shapes, depending on random operations rather than routine procedures. The role of dose constraints for occupational exposures, was further elaborated in Publication 101 (ICRP, 2006) as 'the dose constraint is a value of individual dose used to limit the range of options considered in the process of optimization'. The revisions of the International Basic Safety Standards as well as the Euratom Basic Safety Standard Directive both aim to implement new ICRP recommendations and have requirements to use dose constraints, defined broadly along the lines provided by the ICRP, and suggest that values be selected from the bands recommended by the ICRP. These will be obligatory adopted in the national regulations by regulatory authorities of EU countries. However, due to accidental characteristics of monitoring data, the 95% confidence tail of the doses for the most highly exposed individuals is near the limit of 20 mSv per year. This is apparently observed in the particular endocrinology units dealing with I-131 therapy. One might concluded that dose limitation and optimization are viewed as sufficient for the management of occupational exposures and reasonably be achieved. (authors)

Doses from radiation exposure

International Nuclear Information System (INIS)

Menzel, H-G.; Harrison, J.D.

2012-01-01

Practical implementation of the International Commission on Radiological Protection’s (ICRP) system of protection requires the availability of appropriate methods and data. The work of Committee 2 is concerned with the development of reference data and methods for the assessment of internal and external radiation exposure of workers and members of the public. This involves the development of reference biokinetic and dosimetric models, reference anatomical models of the human body, and reference anatomical and physiological data. Following ICRP’s 2007 Recommendations, Committee 2 has focused on the provision of new reference dose coefficients for external and internal exposure. As well as specifying changes to the radiation and tissue weighting factors used in the calculation of protection quantities, the 2007 Recommendations introduced the use of reference anatomical phantoms based on medical imaging data, requiring explicit sex averaging of male and female organ-equivalent doses in the calculation of effective dose. In preparation for the calculation of new dose coefficients, Committee 2 and its task groups have provided updated nuclear decay data (ICRP Publication 107) and adult reference computational phantoms (ICRP Publication 110). New dose coefficients for external exposures of workers are complete (ICRP Publication 116), and work is in progress on a series of reports on internal dose coefficients to workers from inhaled and ingested radionuclides. Reference phantoms for children will also be provided and used in the calculation of dose coefficients for public exposures. Committee 2 also has task groups on exposures to radiation in space and on the use of effective dose.

Dose evaluation due to the effluent liberation by medical installations at city of Rio de Janeiro, Brazil; Avaliacao de doses devido a liberacao de efluentes por instalacoes medicas na cidade do Rio de Janeiro

Energy Technology Data Exchange (ETDEWEB)

Shu, Jane; Rochedo, Elaine R.R., E-mail: jshu@cnen.gov.b, E-mail: erochedo@cnen.gov.b [Comissao Nacional de Energia Nuclear (CODIN/CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Instalacoes Nucleares; Heilbron, Paulo F.L., E-mail: paulo@cnen.gov.b [Comissao Nacional de Energia Nuclear (COREJ/CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Rejeitos; Crispim, Verginia R., E-mail: verginia@con.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2011-10-26

This paper, the city of Rio de Janeiro was taken as a case study. It was processed deterministic and probabilistic simulations vor evaluation of the dose in two exposure sceneries, one of them referring to public members exposure and the other relative to exposure of sewage sanitary treatment plant workers. The results showed that at present the doses for inhabitants of the city and operators of treatment station are lower to dose limit established for the public, the approach presently in use in Brazil is not sufficient to accomplish whit international requirements and the regulation should be revised to be adopted specific values for each radionuclide

New-doses limits introduction analysis for the design and operation of teletherapy facilities established by IAEA

International Nuclear Information System (INIS)

Castaneda M, A.; Jimenez C, I.; Ramirez M, J.C.; Sanchez V, H.F.

1996-01-01

A design of a typical teletherapy facility was made considering a Co-60 rotating unit and using critical parameters, taking into account as a design base the dose limits established in the Safety Series No. 9 (1), and Safety Series No.115-I (2), shielding thickness when the dose limits were changed. An increment in the required thickness of 1,35 CHR for controlled areas and 2,37 CHR for non-controlled areas were found. This work considered the selection of four different types of teletherapy facilities using Co-60 sources, with different design and type of used unit. An analysis of thickness was made taking into account both the original values for the design and the real operation values in each facility. In order to determine the necessary changes for the wall thicknesses when the new recommendations are applied. (authors). 4 refs., 3 tabs

Development of evaluation method of collective dose of general public considering the daily life activity and time use

International Nuclear Information System (INIS)

Nagaoka, Toshi; Saito, Kimiaki; Sakamoto, Ryuichi; Tsutsumi, Masahiro; Moriuchi, Shigeru

1994-11-01

A code for evaluation of collective dose of general public to natural radiation has been developed, in which the variation of dose rate due to place of stay is taken into consideration. Only external exposure to natural radiation is subject to discussion in this report. Strict manner of dose evaluation requires the dose rate and the time period of stay for each place and for each person. It is possible to know (measure) them all, but not practicable. In this code, dose rate information was obtained from actually measured data by the authors and estimation based on the environmental conditions. Information on the time period of stay was obtained from a Survey Data on Time Use and Leisure Activities by Management and Coordination Agency, and from Statistical Yearbook of Tokyo with some realistic assumptions. By using them, collective dose was evaluated taking both the daily life style and dose rate varying place by place into consideration. In this report, the dose evaluation code and the results about doses for Tokyo citizens are mentioned. (author)

American National Standard: neutron and gamma-ray flux-to-dose rate factors

International Nuclear Information System (INIS)

Anon.

1977-01-01

This Standard presents data recommended for computing biological dose rates due to neutron and gamma-ray radiation fields. Neutron flux-to-dose-rate conversion factors for energies from 2.5 x 10 -8 to 20 MeV are given; the energy range for the gamma-ray conversion factors is 0.01 to 15 MeV. Specifically, this Standard is intended for use by shield designers to calculate wholebody dose rates to radiation workers and the general public. Establishing dose-rate limits is outside the scope of this Standard. Use of this Standard in cases where the dose equivalents are far in excess of occupational exposure guidelines is not recommended

Limiting value definition in radiation protection physics, legislation and toxicology. Fundamentals, contrasts, perspectives

International Nuclear Information System (INIS)

Smeddinck, Ulrich; Koenig, Claudia

2016-01-01

The volume is the documentation of an ENTRIA workshop discussion on limiting value definition in radiation protection including the following contributions: Introduction in radiation protection -fundamentals concepts of limiting values, heterogeneity; evaluation standards for dose in radiation protection in the context of final repository search; definition of limiting values in toxicology; public participation to limiting value definition - a perspective for the radiation protection regulation; actual developments in radiation protection.

Design safety limits in prototype fast breeder reactor

International Nuclear Information System (INIS)

Puthiyavinayagam, P.; Roychowdhury, D.G.; Govindarajan, S.; Chellapandi, P.; Singh, Om Pal; Chetal, S.C.

2002-01-01

Full text: PFBR is designed to operate at 450 W/cm peak linear heat rating to a peak burn up of 100,000 MWd/t which corresponds to a damage dose of 85 dpa. The targetted reliability is to restrict pin failure to 1 in 10,000. All the design basis events are classified into four categories. Design safety limits imposed for DBE are in terms of temperatures, radiation doses and structural design parameters. Radiation limits are imposed in relation to RCB from the plant personnel and public point of view. Fuel pin integrity is assured with a detailed damage analysis by adopting cumulative damage concept for fixing clad temperature limits. Fuel temperatures are limited to melting point to preclude fuel slumping for events up to category 3. Partial melting is allowed for events in category 4 and the results obtained from transients experiments show that partial melting up to 50% of pellet area does not result in clad failure. Coolant temperatures are limited to boiling point to avoid burnout and reactivity effects

Dose rate in the reactor room and environment during maintenance in fusion reactors

International Nuclear Information System (INIS)

Maki, Koichi; Satoh, Satoshi; Takatsu, Hideyuki; Seki, Yasushi

1995-01-01

According to the International Thermonuclear Experimental Reactor (ITER) conceptual design activity, after reactor shutdown, damaged segments are pulled up from the reactor and hung from the reactor room ceiling by a remote handling device. The dose rate in the reactor room and the environment is estimated for this situation, and the following results are obtained. First, the dose rate in the room is > 10 8 μSv/h. Since this dose rate is 10 7 times greater than the biological radiation shielding design limit of 25 μSv/h, workers cannot enter the room. Second, lenses and optical fiber composed of glass that is radiation resistant up to 10 6 Gy would be damaged after <100 h near the segment, and devices using semiconductors could not work after several hours or so in the aforementioned dose-rate conditions. Third, during suspension of one blanket segment from the ceiling, the dose rate in the site boundary can be reduced by one order by a 23-cm-thicker reactor building roof. To reduce dose rate in public exposure to a value that is less than one-tenth of the public exposure radiation shielding design limit of 100 μSv/yr, the distance of the site boundary from the reactor must be greater than 200 m for a reactor building with a 160-cm-thick concrete roof. 9 refs., 6 figs., 2 tabs

Monitoring of high-radiation areas for the assessment of operational and body doses

International Nuclear Information System (INIS)

Chen, T.J.; Tung, C.J.; Yeh, W.W.; Liao, R.Y.

2004-01-01

protection quantities should be applied. For significant exposures that are deemed abnormal, according to the recommendations in ICRP Publication 28, actual doses in the body, from an assessment of the accident, should be used.' In order to assess radiation protection quantities and actual absorbed doses in the body stated above, information on the energy and irradiation geometry of the incident radiation is required. ICRP in its Publication 35 recommended that: 'In minor accidents, when the deep dose equivalent index is only slightly above the limit, the organ and tissue dose equivalents themselves may still comply with the annual limit for effective dose equivalent. Information on the energy spectrum and orientation of the incident radiation may then allow more realistic estimates of these dose equivalents to be made.' In this work, we surveyed high radiation areas in the nuclear power plants in Taiwan. We measured energy and angular distributions of photons in these areas by a portable Nal detector. We then analyzed the irradiation geometries using the ICRU classifications. Applying these results, the Taiwan Power Company should be able to evaluate actual body doses more accurately for workers exposed to high-levels of radiation

The software program Peridose to calculate the fetal dose or dose to other critical structures outside the target area in radiation therapy

International Nuclear Information System (INIS)

Giessen, P.H. van der

2001-01-01

An accurate estimate of the dose outside the target area is of utmost importance when pregnant patients have to undergo radiotherapy, something that occurs in every radiotherapy department once in a while. Such peripheral doses (PD) are also of interest for late effects risk estimations for doses to specific organs as well as estimations of dose to pacemakers. A software program, Peridose, is described to allow easy calculation of this peripheral dose. The calculation is based on data from many publications on peripheral dose measurements, including those by the author. Clinical measurements have shown that by using data averaged over many measurements and different machine types PDs can be estimated with an accuracy of ± 60% (2 standard deviations). The program allows easy and fairly accurate estimates of peripheral doses in patients. Further development to overcome some of the constraints and limitations is desirable. The use of average data is to be preferred if general applicability is to be maintained. (author)

Occupational dose equivalent limits

International Nuclear Information System (INIS)

Goldfinch, E.P.

1980-01-01

This paper considers methods of limiting individual radiation risks by recognizing the variation of risk with age at exposure, taking into account both somatic and genetic risks and proposes a simple formula for controlling individual cumulative exposure and hence risk. (Author)

The use of the effective dose equivalent, Hsub(E), as a risk parameter in computed tomography

International Nuclear Information System (INIS)

Huda, W.; Sandison, G.A.

1986-01-01

This note employs the concept of the effective dose equivalent, Hsub(E) to overcome the problems of comparing the non-uniform radiation doses encountered in CT examinations with the whole-body dose-equivalent limits imposed for non-medical exposures for members of the public (5 mSv/year), or with the risks from familiar everyday activities such as smoking cigarettes or driving cars. (U.K.)

76 FR 40755 - Impact of Reduced Dose Limits on NRC Licensed Activities; Solicitation of Public Comment

Science.gov (United States)

2011-07-11

... scientifically justified, to achieve greater alignment with the 2007 recommendations of the International... and image files of the NRC's public documents. If you do not have access to ADAMS or if there are... informed of all the benefits and burdens associated with further alignment of NRC's current radiation...

Assessment of tritium dose around Rajasthan Atomic Power Station (1989-1997)

International Nuclear Information System (INIS)

Verma, P.C.; Vijaykumar, B.; George, Thomas; Sankhla, Rajesh; Roy, Alpana; Vyas, P.V.; Gurg, R.P.

1999-01-01

Tritium monitoring in the atmospheric and aquatic environment forms an integral part of the environmental radiological measurements conducted around PHWR type Nuclear Power Plant sites as tritium is one of the predominantly produced radionuclides in such systems. This paper presents the tritium concentration levels in the atmospheric and aquatic environs of Rajasthan Atomic Power Station (RAPS) during 1989-1997. The committed effective doses due to tritium are computed on annual basis for different radial zones around RAPS. It is observed that the maximum dose due to tritium at 1.6 km post fence has been less than 1% of the dose limit (1 mSv) set by regulatory body for the members of the public and beyond 5 km distance it is only 0.4% of the limit. (author)

High-Dose Atomoxetine Treatment of ADHD in Youths with Limited Response to Standard Doses

Science.gov (United States)

Kratochvil, Christopher J.; Michelson, David; Newcorn, Jeffrey H.; Weiss, Margaret D.; Busner, Joan; Moore, Rodney J.; Ruff, Dustin D.; Ramsey, Janet; Dickson, Ruth; Turgay, Atilla; Saylor, Keith E.; Luber, Stephen; Vaughan, Brigette; Allen, Albert J.

2007-01-01

Objective: To assess the utility and tolerability of higher than standard atomoxetine doses to treat attention-deficit/hyperactivity disorder (ADHD). Method: Two randomized, double-blind trials of atomoxetine nonresponders ages 6 to 16 years were conducted comparing continued treatment with same-dose atomoxetine to treatment using greater than…

Health conditions and role limitation in three European Regions: a public-health perspective

Directory of Open Access Journals (Sweden)

Gabriela Barbaglia

2017-01-01

Conclusion: The contribution of health conditions to role limitation in the three European regions studied is high. Mental disorders are associated with the largest impact in most of the regions. There is a need for mainstreaming disability in the public health agenda to reduce the role limitation associated with health conditions. The cross-regional differences found require further investigation.

Offsite radiation doses summarized from Hanford environmental monitoring reports for the years 1957-1984

International Nuclear Information System (INIS)

Soldat, J.K.; Price, K.R.; McCormack, W.D.

1986-02-01

Since 1957, evaluations of offsite impacts from each year of operation have been summarized in publicly available, annual environmental reports. These evaluations included estimates of potential radiation exposure to members of the public, either in terms of percentages of the then permissible limits or in terms of radiation dose. The estimated potential radiation doses to maximally exposed individuals from each year of Hanford operations are summarized in a series of tables and figures. The applicable standard for radiation dose to an individual for whom the maximum exposure was estimated is also shown. Although the estimates address potential radiation doses to the public from each year of operations at Hanford between 1957 and 1984, their sum will not produce an accurate estimate of doses accumulated over this time period. The estimates were the best evaluations available at the time to assess potential dose from the current year of operation as well as from any radionuclides still present in the environment from previous years of operation. There was a constant striving for improved evaluation of the potential radiation doses received by members of the public, and as a result the methods and assumptions used to estimate doses were periodically modified to add new pathways of exposure and to increase the accuracy of the dose calculations. Three conclusions were reached from this review: radiation doses reported for the years 1957 through 1984 for the maximum individual did not exceed the applicable dose standards; radiation doses reported over the past 27 years are not additive because of the changing and inconsistent methods used; and results from environmental monitoring and the associated dose calculations reported over the 27 years from 1957 through 1984 do not suggest a significant dose contribution from the buildup in the environment of radioactive materials associated with Hanford operations

Dose rate survey inside and outside three public buildings located approximately 40 km northwest of the Fukushima Daiichi Nuclear Power Stations

International Nuclear Information System (INIS)

Yajima, Kazuaki; Iwaoka, Kazuki; Kamada, So

2013-01-01

We surveyed the reduction of the dose rate inside three public buildings compared to the dose rate outside in Kawamata-machi, Fukushima Prefecture. The three buildings—a wooden construction district meeting place, a steel construction public hall, and a reinforced concrete school building—are located approximately 40 km northwest of TEPCO's Fukushima Daiichi Nuclear Power Stations. The dose rate measurement, performed with a NaI(Tl) scintillation survey meter, was carried out on January 19, 2012. We evaluated the reduction of the dose rate inside the building using the reduction factor, which was determined to be the ratio of the dose rate inside the building to that outside the building. The reduction factors 1 m inside from the window were 0.51-0.56 for the wooden building, 0.34-0.51 for the steel construction building, and 0.27-0.31 for the concrete building. The reduction factors at the center of the room were 0.48 for the wooden building, 0.23-0.34 for the steel construction building, and 0.10-0.16 for the concrete building. (author)

Development of mathematical pediatric phantoms for internal dose calculations: designs, limitations, and prospects

International Nuclear Information System (INIS)

Cristy, M.

1980-01-01

Mathematical phantoms of the human body at various ages are employed with Monte Carlo radiation transport codes for calculation of photon specific absorbed fractions. The author has developed a pediatric phantom series based on the design of the adult phantom, but with explicit equations for each organ so that organ sizes and marrow distributions could be assigned properly. Since the phantoms comprise simple geometric shapes, predictive dose capability is limited when geometry is critical to the calculation. Hence, there is a demand for better phantom design in situations where geometry is critical, such as for external irradiation or for internal emitters with low energy photons. Recent advances in computerized axial tomography (CAT) present the potential for derivation of anatomical information, which is so critical to development of phantoms, and ongoing developmental work on compuer architecture to handle large arrays for Monte Carlo calculations should make complex-geometry dose calculations economically feasible within this decade

Discussion on the methods for calculation release limits for low-level radioactive waste

International Nuclear Information System (INIS)

Cao Fengbo; Liu Xiaochao

2012-01-01

The release request for low-level radioactive waste are briefly described in this paper. Associating with the conditions of low-level radioactive waste of some radioactive waste processing station, the methods and gist for calculating release limits for low-level radioactive waste with national release limits and annual effective dose limit for the public or the occupation are discussed. Then release limits for the low-level radioactive waste are also proposed. (authors)

Radiation-induced cataracts: the Health Protection Agency's response to the ICRP statement on tissue reactions and recommendation on the dose limit for the eye lens.

Science.gov (United States)

Bouffler, Simon; Ainsbury, Elizabeth; Gilvin, Phil; Harrison, John

2012-12-01

This paper presents the response of the Health Protection Agency (HPA) to the 2011 statement from the International Commission on Radiological Protection (ICRP) on tissue reactions and recommendation of a reduced dose limit for the lens of the eye. The response takes the form of a brief review of the most recent epidemiological and mechanistic evidence. This is presented together with a discussion of dose limits in the context of the related risk and the current status of eye dosimetry, which is relevant for implementation of the limits. It is concluded that although further work is desirable to quantify better the risk at low doses and following protracted exposures, along with research into the mechanistic basis for radiation cataractogenesis to inform selection of risk projection models, the HPA endorses the conclusion reached by the ICRP in their 2011 statement that the equivalent dose limit for the lens of the eye should be reduced from 150 to 20 mSv per year, averaged over a five year period, with no year's dose exceeding 50 mSv.

Radionuclides and radiation doses in heavy mineral sands and other mining operations in Mozambique

International Nuclear Information System (INIS)

Carvalho, F. P.; Matine, O. F.; Taimo, S.; Oliveira, J. M.; Silva, L.; Malta, M.

2014-01-01

Sites at the littoral of Mozambique with heavy mineral sands exploited for ilmenite, rutile and zircon and inland mineral deposits exploited for tantalite, uranium and bauxite were surveyed for ambient radiation doses, and samples were collected for the determination of radionuclide concentrations. In heavy mineral sands, 238 U and 232 Th concentrations were 70±2 and 308±9 Bq kg -1 dry weight (dw), respectively, whereas after separation of minerals, the concentrations in the ilmenite fraction were 2240±64 and 6125±485 Bq kg -1 (dw), respectively. Tantalite displayed the highest concentrations with 44 738±2474 Bq kg -1 of 238 U. Radiation exposure of workers in mining facilities is likely to occur at levels above the dose limit for members of the public (1 mSv y -1 ) and therefore radiation doses should be assessed as occupational exposures. Local populations living in these regions in general are not exposed to segregated minerals with high radionuclide concentrations. However, there is intensive traditional mining and a large number of artisan miners and their families may be exposed to radiation doses exceeding the dose limit. A radiation protection programme is therefore needed to ensure radiation protection of the public and workers of developing mining projects. (authors)

Radionuclides and radiation doses in heavy mineral sands and other mining operations in Mozambique.

Science.gov (United States)

Carvalho, Fernando P; Matine, Obete F; Taímo, Suzete; Oliveira, João M; Silva, Lídia; Malta, Margarida

2014-01-01

Sites at the littoral of Mozambique with heavy mineral sands exploited for ilmenite, rutile and zircon and inland mineral deposits exploited for tantalite, uranium and bauxite were surveyed for ambient radiation doses, and samples were collected for the determination of radionuclide concentrations. In heavy mineral sands, (238)U and (232)Th concentrations were 70±2 and 308±9 Bq kg(-1) dry weight (dw), respectively, whereas after separation of minerals, the concentrations in the ilmenite fraction were 2240±64 and 6125±485 Bq kg(-1) (dw), respectively. Tantalite displayed the highest concentrations with 44 738±2474 Bq kg(-1) of (238)U. Radiation exposure of workers in mining facilities is likely to occur at levels above the dose limit for members of the public (1 mSv y(-1)) and therefore radiation doses should be assessed as occupational exposures. Local populations living in these regions in general are not exposed to segregated minerals with high radionuclide concentrations. However, there is intensive artisanal mining and a large number of artisanal miners and their families may be exposed to radiation doses exceeding the dose limit. A radiation protection programme is therefore needed to ensure radiation protection of the public and workers of developing mining projects.

Diversifying the academic public health workforce: strategies to extend the discourse about limited racial and ethnic diversity in the public health academy.

Science.gov (United States)

Annang, Lucy; Richter, Donna L; Fletcher, Faith E; Weis, Megan A; Fernandes, Pearl R; Clary, Louis A

2010-01-01

While public health has gained increased attention and placement on the national health agenda, little progress has been made in achieving a critical mass of underrepresented minority (URM) academicians in the public health workforce. In 2008, a telephone-based qualitative assessment was conducted with URM faculty of schools of public health to discuss this issue. As a result, we present successful strategies that institutional leaders can employ to extend the discourse about addressing limited diversity in the public health academy.

Derived limits for surface contamination

CERN Document Server

Wrixon, A D; Linsley, G S; White, D F

1979-01-01

Derived limits (DLs) for surface contamination were first established for use in the nuclear energy industry where a wide variety of radionuclides is encountered. They were later used in factories, hospitals, and universities, where the radionuclides used are normally fewer in number, either known or readily identifiable, and often of low toxicity. In these situations the current limits are frequently over-restrictive. This report describes a reassessment of the values in the light of more recent information on the possible pathways of exposure and the dose equivalent limits given in ICRP Publication 26. The reassessment is prompted also by the introduction of SI units. The results of the reassessment are used to produce a classification of DLs for all radionuclides for active and inactive area surfaces and for skin.

Principles for limiting exposure of the public to natural sources of radiation

International Nuclear Information System (INIS)

1984-01-01

In a preliminary note a discussion is presented of the factors by which the values of Annual Limits on Intakes (ALI) and Derived Air Concentrations (DAC) recommended in ICRP Publication 30 for workers would differ from those that would be appropriate for members of the public. In Publication 39, the principles adopted distinguish between procedures for existing exposure situations, which can only be influenced by remedial action, and examples of future exposure situations which can be subject to administrative control (e.g. new house construction, reduction of ventilation in existing houses, production of building materials from new production facilities, water supplies from new facilities, burning natural gas from new wells, using fertiliser from new mills and factories). (U.K.)

Some limitations of public sequence data for phylogenetic inference (in plants).

Science.gov (United States)

Hinchliff, Cody E; Smith, Stephen Andrew

2014-01-01

The GenBank database contains essentially all of the nucleotide sequence data generated for published molecular systematic studies, but for the majority of taxa these data remain sparse. GenBank has value for phylogenetic methods that leverage data-mining and rapidly improving computational methods, but the limits imposed by the sparse structure of the data are not well understood. Here we present a tree representing 13,093 land plant genera--an estimated 80% of extant plant diversity--to illustrate the potential of public sequence data for broad phylogenetic inference in plants, and we explore the limits to inference imposed by the structure of these data using theoretical foundations from phylogenetic data decisiveness. We find that despite very high levels of missing data (over 96%), the present data retain the potential to inform over 86.3% of all possible phylogenetic relationships. Most of these relationships, however, are informed by small amounts of data--approximately half are informed by fewer than four loci, and more than 99% are informed by fewer than fifteen. We also apply an information theoretic measure of branch support to assess the strength of phylogenetic signal in the data, revealing many poorly supported branches concentrated near the tips of the tree, where data are sparse and the limiting effects of this sparseness are stronger. We argue that limits to phylogenetic inference and signal imposed by low data coverage may pose significant challenges for comprehensive phylogenetic inference at the species level. Computational requirements provide additional limits for large reconstructions, but these may be overcome by methodological advances, whereas insufficient data coverage can only be remedied by additional sampling effort. We conclude that public databases have exceptional value for modern systematics and evolutionary biology, and that a continued emphasis on expanding taxonomic and genomic coverage will play a critical role in developing

Factors affecting radiation doses from dedicated rail transport of spent reactor fuel

International Nuclear Information System (INIS)

Martin, J.E.

1988-01-01

This paper reports there are two exposure control concerns associated with the shipment of spent reactor fuel in dedicated trains -- compliance with transportation regulations for maximum allowable radiation levels, and minimizing the dose received by the general public. This article examines the methods used to calculate the dose equivalent rates alongside stationary (transport regulations) and moving trains (public exposure) of various lengths. The factors examined include the source term, the effect of overlapping radiation fields, the speed of the train, and the location of the population relative to the train. Trains made up of series of cars that individually meet transport regulations can, as a whole, exceed transport vehicle dose equivalent rate limits by up to 23% due to overlapping radiation fields. For moving trains and the worst case analyzed -- a person located 20 feet from the tracks and a train speed of 5 mph --- 141 rail cars would have to pass by to deliver a dose equivalent of 1 mrem

Health conditions and role limitation in three European Regions: a public-health perspective.

Science.gov (United States)

Barbaglia, Gabriela; Adroher, Núria D; Vilagut, Gemma; Bruffaerts, Ronny; Bunting, Brentan; Caldas de Almeida, José Miguel; Florescu, Silvia; de Girolamo, Giovanni; de Graaf, Ron; Haro, Josep Maria; Hinkov, Hristo; Kovess-Masfety, Vivianne; Matschinger, Herbert; Alonso, Jordi

To describe the distribution of role limitation in the European population aged 18-64 years and to examine the contribution of health conditions to role limitation using a public-health approach. Representative samples of the adult general population (n=13,666) aged 18-64 years from 10 European countries of the World Mental Health (WMH) Surveys Initiative, grouped into three regions: Central-Western, Southern and Central-Eastern. The Composite International Diagnostic Interview (CIDI 3.0) was used to assess six mental disorders and standard checklists for seven physical conditions. Days with full and with partial role limitation in the month previous to the interview were reported (WMH-WHODAS). Population Attributable Fraction (PAFs) of full and partial role limitation were estimated. Health conditions explained a large proportion of full role limitation (PAF=62.6%) and somewhat less of partial role limitation (46.6%). Chronic pain was the single condition that consistently contributed to explain both disability measures in all European Regions. Mental disorders were the most important contributors to full and partial role limitation in Central-Western and Southern Europe. In Central-Eastern Europe, where mental disorders were less prevalent, physical conditions, especially cardiovascular diseases, were the highest contributors to disability. The contribution of health conditions to role limitation in the three European regions studied is high. Mental disorders are associated with the largest impact in most of the regions. There is a need for mainstreaming disability in the public health agenda to reduce the role limitation associated with health conditions. The cross-regional differences found require further investigation. Copyright © 2016 SESPAS. Publicado por Elsevier España, S.L.U. All rights reserved.

Bases for establishing radiation exposure limits

International Nuclear Information System (INIS)

Pochin, E.E.

1977-01-01

It is an essential requirement of good radiation protection that all unnecessary exposure of people should be avoided and that any necessary exposure, whether of workers or of members of the general public, should be minimized. It is, however, an additional requirement that such necessary exposures should not exceed certain stated limits. These principles are based on the possibility that even the smallest exposures may involve some risk of harm, that any risk of harm should be justifiable by the circumstances necessitating it, and that risk should always be limited to an appropriately low level. The bases for establishing exposure limits must therefore involve an assessment of the risk involved in any form of radiation exposure, and an opinion as to the degree of safety that should be ensured in circumstances which necessitate any occupational or public exposure to radiation. There is increasing quantitative evidence on the frequency on which harm, and particularly the induction of malignancies, may be caused in people exposed to radiation at high doses; and somewhat clearer bases than previously for inferring the possible frequencies at low doses. It is therefore easier to assess the degree of safety ensured by restricting radiation exposure to particular levels. It is clear also that a comparable degree of safety should be ensured whether the radiation exposure involves the whole body more of less uniformly, or individual tissues or organs selectively. The ''weighting'' factors appropriate to irradiation of particular tissues from internal emitters can thus be defined in terms of their likely individual contributions to the harm of whole-body irradiation. In this way the limits for different modes of exposure by external or internal radiation can be related so as to ensure that protection should be equally effective for different distributions of absorbed dose in the body. In particular, the over-simplified concept of a single critical organ determining the

Estimating the Effects of Astronaut Career Ionizing Radiation Dose Limits on Manned Interplanetary Flight Programs

Science.gov (United States)

Koontz, Steven L.; Rojdev, Kristina; Valle, Gerard D.; Zipay, John J.; Atwell, William S.

2013-01-01

The Hybrid Inflatable DSH combined with electric propulsion and high power solar-electric power systems offer a near TRL-now solution to the space radiation crew dose problem that is an inevitable aspect of long term manned interplanetary flight. Spreading program development and launch costs over several years can lead to a spending plan that fits with NASA's current and future budgetary limitations, enabling early manned interplanetary operations with space radiation dose control, in the near future while biomedical research, nuclear electric propulsion and active shielding research and development proceed in parallel. Furthermore, future work should encompass laboratory validation of HZETRN calculations, as previous laboratory investigations have not considered large shielding thicknesses and the calculations presented at these thicknesses are currently performed via extrapolation.

Reflections on public acceptance of nuclear energy and the low dose issue

International Nuclear Information System (INIS)

Becker, K.

2001-01-01

The present rules of radiation protection are based on the concepts adopted fifteen years ago and now outdated, and on the ICRP 60 publication. They have become a matter of dispute among experts groups, research, and the regulatory authorities. A major role in this debate is played by new basic scientific and epidemiological findings, economic and political interests, the influence of the media, and the psychology of risk perception. For instance, also the different evaluations of natural and manmade radiation exposures contribute to the general sense of uncertainty. The article summarizes the discussion, and the development, in the past two or three years. Special attention is given to the trends which are to result in sound, feasible practices from the currently dominating assumption of the LNT/collective dose hypotheses with an interpolation to low or even very low doses. The renewed discussion sparked off by current research findings should result in a reasonable way of handling radiation so as to be able to classify a potential radiation risk in an appropriate balance between natural and manmade risks. (orig.) [de

Dose coefficients for radionuclides produced in high energy proton accelerator facilities. Coefficients for radionuclides not listed in ICRP publications

CERN Document Server

Kawai, K; Noguchi, H

2002-01-01

Effective dose coefficients, the committed effective dose per unit intake, by inhalation and ingestion have been calculated for 304 nuclides, including (1) 230 nuclides with half-lives >= 10 min and their daughters that are not listed in ICRP Publications and (2) 74 nuclides with half-lives < 10 min that are produced in a spallation target. Effective dose coefficients for inhalation of soluble or reactive gases have been calculated for 21 nuclides, and effective dose rates for inert gases have been calculated for 9 nuclides. Dose calculation was carried out using a general-purpose nuclear decay database DECDC developed at JAERI and a decay data library newly compiled from the ENSDF for the nuclides abundantly produced in a spallation target. The dose coefficients were calculated with the computer code DOCAP based on the respiratory tract model and biokinetic model of ICRP. The effective dose rates were calculated by considering both external irradiation from the surrounding cloud and irradiation of the lun...

Quantification of individual of individual annual doses to the public due to Embalse NPP operation

International Nuclear Information System (INIS)

Salas, Carlos

2008-01-01

This paper compares the individual annual doses to the public produced during Embalse NPP operation and the natural radiation doses absorbed in everyday life by the same individuals. The basic idea is to show several examples that allow the comparison. Therefore, everybody will get a clear picture of the radiological contamination that surrounds us and the actual influence that Embalse NPP's operation has in the environment. The first concept to be considered is that the human body cells cannot distinguish whether radiation comes from a natural or an artificial source (a source created by man). This is of great importance in the case of the popular myth that says that radiation coming from artificial sources is the only damaging radiation, and that other types of radiation are innocuous, and represent no hazard to human health. We can preliminarily state that when considering the same dose, the effects of both kinds of radiation in human body are equal. (author)

Dose conversion coefficients for high-energy photons, electrons, neutrons and protons

International Nuclear Information System (INIS)

Sakamoto, Yukio

2005-01-01

Dose conversion coefficients for photons, electrons and neutrons based on new ICRP recommendations were cited in the ICRP Publication 74, but the energy ranges of these data were limited and there are no data for high energy radiations produced in accelerator facilities. For the purpose of designing the high intensity proton accelerator facilities at JAERI, the dose evaluation code system of high energy radiations based on the HERMES code was developed and the dose conversion coefficients of effective dose were evaluated for photons, neutrons and protons up to 10 GeV, and electrons up to 100 GeV. The dose conversion coefficients of effective dose equivalent were also evaluated using quality factors to consider the consistency between radiation weighting factors and Q-L relationship. The effective dose conversion coefficients obtained in this work were in good agreement with those recently evaluated by using FLUKA code for photons and electrons with all energies, and neutrons and protons below 500 MeV. There were some discrepancy between two data owing to the difference of cross sections in the nuclear reaction models. The dose conversion coefficients of effective dose equivalents for high energy radiations based on Q-L relation in ICRP Publication 60 were evaluated only in this work. The previous comparison between effective dose and effective dose equivalent made it clear that the radiation weighting factors for high energy neutrons and protons were overestimated and the modification was required. (author)

Investigation of the sources and fate of radioactive discharges to public sewers

International Nuclear Information System (INIS)

Titley, J.; Carey, A.; Crockett, G.

2000-01-01

. Doses were predicted for discharges at the authorised limits and for typical disposals made in 1997. All the predicted and measured doses were below the dose limit and maximum dose constraint for members of the public. Actual discharge levels are less than authorised limits and consequently the actual doses to members of the public will be less than the values quoted below. Estimated doses from disposals at maximum authorised limits in Leeds were 80 μSv y -1 to typical workers around the sewage works and incinerator, and up to 238 μSv y -1 in the sludge pressroom. The most important radionuclide was I-131. Estimated doses from disposals at authorised limits in Beckton were 210 μSv/y to typical workers and 207 μSv y -1 to sludge press workers. These doses were dominated by disposals of I-131 and Rb-84. Maximum estimated doses to the public from disposal of effluent and incineration of sewage sludge at Beck-ton were 30 μSv y -1 and 2 μSv y -1 respectively and in Leeds were 180 μSv y -1 and 2 μSv y -1 respectively. The most important radionuclides were C-14, I-125 and I-131 at both sites. Estimated doses based on typical disposals in both catchments were up to a factor of three lower at the sewage treatment works and up to an order of magnitude lower for the public. Dose rates were measured at various points in each sewage works, and were found to be below the uncertainty on the results. The applicability of the results for Beckton and Knostrop to other sewage treatment works was addressed and simple formulae given for the important pathways. The study also looked at the need for further data on radionuclide behaviour in incinerators and the need for discharge reduction measures. Neither can be justified on the basis of this study. (author)

The embryogenesis of dose assessment at Hanford

International Nuclear Information System (INIS)

Foster, R.F.

1990-01-01

Several significant events occurred between 1955 and 1960 that resulted in major changes in environmental monitoring at Hanford and in the initiation of comprehensive dose assessments. These included: (1) specification of dose limits for nonoccupational exposure (including internal emitters); (2) a national and international awakening to the need for managing the disposal of radioactive wastes; (3) identification of the most important radionuclides and their sources of exposure; (4) data that quantified the transfer coefficients of nuclides along environmental pathways; and (5) development of greatly improved radiation detection instrumentation. In response to a growing need, the Hanford Laboratories formed the Environmental Studies and Evaluation component. This group revamped the monitoring and sampling programs so that analytical results contributed directly to dose estimation. Special studies were conducted to ascertain local dietary and recreational habits that affected dose calculations and to calibrate the models. These studies involved extensive contact with the public and governmental agencies, which elicited a positive reaction

Assessment and recording of radiation doses to workers

International Nuclear Information System (INIS)

1986-01-01

The assessment and recording of the radiation exposure of workers in activities involving radiation risks are required for demonstrating compliance with institutional dose limitations and for a number of other complementary purposes. A significant proportion of the labor force involved in radiation work is currently represented by those specialised workers who operate as itinerant contractors for different nuclear installations and in different countries. In order to ensure that the exposure of these workers is adequately and consistently controlled and kept within acceptable limits, there is a need for the criteria and methods for dose assessment and recording to be harmonised throughout the different countries. An attempt in that direction has been made in this report, which has been prepared by a group of experts convened by the Committee on Radiation Protection and Public Health of the OECD Nuclear Energy Agency. Its primary purpose is to describe recommended technical procedures for an unified approach to the assessment and recording of worker doses. The report is published under the responsibility of the Secretary-General of the OECD, and does not commit Member governments

17 CFR 250.41 - Exemption of public utility subsidiaries with respect to limited acquisition of utility assets.

Science.gov (United States)

2010-04-01

... Exemption of public utility subsidiaries with respect to limited acquisition of utility assets. Any public... derived from its operations as a public-utility company during the preceding calendar year. (d... 17 Commodity and Securities Exchanges 3 2010-04-01 2010-04-01 false Exemption of public utility...

Interdisciplinary perspectives on dose limits in radioactive waste management : A research paper developed within the ENTRIA project

NARCIS (Netherlands)

Kalmbach, K.; Röhlig, K.-J.

2016-01-01

Within the ENTRIA project, an interdisciplinary group of scientists developed a research paper aiming at a synthesis of the technical, sociology of knowledge, legal, societal, and political aspects of dose limits within the field of radioactive waste management. In this paper, the ENTRIA project is

Generalised derived limits for radioisotopes of iodine

International Nuclear Information System (INIS)

Hughes, J.S.; Haywood, S.M.; Simmonds, J.R.

1984-04-01

Generalised Derived Limits (GDLs) are evaluated for iodine-125,129,131,132,133,134,135 in selected materials from the terrestrial and aquatic environments and for discharge to atmosphere. They are intended for use as convenient reference levels against which the results of environmental monitoring can be compared and atmospheric discharges assessed. GDLs are intended for use when the environmental contamination or discharge to atmosphere is less than about 5% of the GDL. If the level of environmental contamination or discharge to the atmosphere exceeds this percentage of the GDL it does not necessarily mean that the dose equivalents to members of the public are approaching the dose equivalent limit. It is rather an indication that it may be appropriate to obtain a more specific derived limit for the particular situation by reviewing the values of the parameters involved in the calculation. GDL values are specified for iodine radionuclides in water, soil, grass, sediments and various foodstuffs derived from the terrestrial and aquatic environments. GDLs are also given for iodine radionuclides on terrestrial surfaces and for their discharge to atmosphere. (author)

Revised age-dependent doses to members of the public from intake of radionuclides using the new tissue weighting factors

International Nuclear Information System (INIS)

Jain, S.C.; Gupta, M.M.; Nagaratnam, A.; Reddy, A.R.; Mehta, S.C.

1992-01-01

ICRP 56 gave age-dependent dose coefficients to members of the public from intake of most radiologically significant radionuclides that might be released to the environment due to various human activities. It has computed effective dose equivalent (now called effective dose) from these dose coefficients utilising the tissue weighting factors as given by ICRP 26. The recent ICRP 1990 recommendations have revised the tissue weighting factors based on new information on risk estimates of fatal cancer and hereditary disorders. This change in the tissue weighting factors will subsequently affect the computation of effective dose due to intake of various radio-nuclides considered by ICRP 56. The revised effective doses for ingested as well as inhaled radionuclides have been worked out and compared from corresponding earlier values. No change was found in the case of tritiated water, organically bound tritium and 14 C. For the majority of the radionuclides, the revised effective dose was within ± 20% of the earlier values. Larger variations in effective dose were noted for radionuclides which deposit preferentially in one or two organs. (author)

Reconstructive dosimetry and radiation doses evaluation of members of the public due to radiological accident in industrial radiography

International Nuclear Information System (INIS)

Lima, Camila Moreira Araujo de

2016-01-01

Radiological accidents have occurred mainly in the practices recognized as high risk radiological and classified by the IAEA as Categories 1 and 2, and highlighted the radiotherapy, industrial irradiators and industrial radiography. In Brazil, since there were five major cases in industrial radiography, which involved 7 radiation workers and 19 members of the public, causing localized radiation lesions on the hands and fingers. One of these accidents will be the focus of this work. In this accident, a "1"9"2Ir radioactive source was exposed for more than 8 hours in the workplace inside a company, exposing radiation workers, individuals of the public and people from the surrounding facilities, including children of a school. The radioactive source was also handled by a security worker causing severe radiation injuries in the hand and fingers. In this paper, the most relevant and used techniques of reconstructive dosimetry internationally are presented. To estimate the radiation doses received by exposed individuals in various scenarios of radiological accident in focus, the following computer codes were used: Visual Monte Carlo Dose Calculation (VMC), Virtual Environment for Radiological and Nuclear Accidents Simulation (AVSAR) and RADPRO Calculator. Through these codes some radiation doses were estimated, such as, 33.90 Gy in security worker's finger, 4.47 mSv in children in the school and 55 to 160 mSv for workers in the company during the whole day work. It is intended that this work will contribute to the improvement of dose reconstruction methodology for radiological accidents, having then more realist radiation doses. (author)

Dose evaluation due to the effluent liberation by medical installations at city of Rio de Janeiro, Brazil

International Nuclear Information System (INIS)

Shu, Jane; Rochedo, Elaine R.R.; Heilbron, Paulo F.L.; Crispim, Verginia R.

2011-01-01

This paper, the city of Rio de Janeiro was taken as a case study. It was processed deterministic and probabilistic simulations vor evaluation of the dose in two exposure sceneries, one of them referring to public members exposure and the other relative to exposure of sewage sanitary treatment plant workers. The results showed that at present the doses for inhabitants of the city and operators of treatment station are lower to dose limit established for the public, the approach presently in use in Brazil is not sufficient to accomplish whit international requirements and the regulation should be revised to be adopted specific values for each radionuclide

Some human activities to decrease public radiation dose

International Nuclear Information System (INIS)

Pan Ziqiang; Guo Minqiang

1994-01-01

The necessity of studying the variations in radiation levels from the balance viewpoint is discussed. Some human activities may increase, while others may decrease, radiation dose to population. In 1988, China's investigation showed that travel by air caused a raise of population collective dose by 3.6 x 10 1 man·Sv, while travel by ship, train and vehicle lead to a drop of 5.36 x 10 2 man·Sv, and that dwellings of coal cinder brick decreased collective dose by 3.5 x 10 3 man·Sv, while buildings of reinforced concrete structure increased collective dose by 3.7 x 10 3 man·Sv. It is inadequate to only study those activities which may increase radiation levels

Health and dosimetry considerations in the ICRP 1990 formulation of effective dose

International Nuclear Information System (INIS)

Eckerman, K.F.

1991-01-01

The new recommendations of the International Commission on Radiological Protection contained in Publication 60 supersede those of Publication 26 issued in 1977. The recommendations are intended to assist national authorities in formulation of radiation protection guidance. Sufficient explanatory information is included to clearly note that radiation protection issues cannot be resolved on the basis of scientific considerations alone, but also require value judgements regarding the relative on the basis of scientific considerations alone, but also require value judgements regarding the relative importance of different kinds of risks and the balance between risk and benefit. Ionizing radiation causes both deterministic and stochastic effects in irradiated tissue. It is the aim of radiation protection to avoid deterministic effects by setting dose limits below their thresholds and to control exposures to limit the frequency of stochastic effects, believed to occur (albeit with low frequency) even at the lowest doses. Cancer induction and hereditary effects are the stochastic effects of concern

[Global public health: international health is tested to its limits by the human influenza A epidemic].

Science.gov (United States)

Franco-Giraldo, Alvaro; Alvarez-Dardet, Carlos

2009-06-01

This article comes from the intense international pressure that follows a near-catastrophy, such as the human influenza A H1N1 epidemic, and the limited resources for confronting such events. The analysis covers prevailing 20th century trends in the international public health arena and the change-induced challenges brought on by globalization, the transition set in motion by what has been deemed the "new" international public health and an ever-increasing focus on global health, in the context of an international scenario of shifting risks and opportunities and a growing number of multinational players. Global public health is defined as a public right, based on a new appreciation of the public, a new paradigm centered on human rights, and altruistic philosophy, politics, and ethics that undergird the changes in international public health on at least three fronts: redefining its theoretical foundation, improving world health, and renewing the international public health system, all of which is the byproduct of a new form of governance. A new world health system, directed by new global public institutions, would aim to make public health a global public right and face a variety of staggering challenges, such as working on public policy management on a global scale, renewing and democratizing the current global governing structure, and conquering the limits and weaknesses witnessed by international health.

Reliability of the ICRP's dose coefficients for members of the public: IV. Basis of the human alimentary tract model and uncertainties in model predictions

International Nuclear Information System (INIS)

Leggett, R.; Harrison, J.; Phipps, A.

2007-01-01

The biokinetic and dosimetric model of the gastrointestinal (GI) tract applied in current documents of the International Commission on Radiological Protection (ICRP) was developed in the mid-1960's. The model was based on features of a reference adult male and was first used by the ICRP in Publication 30, Limits for Intakes of Radionuclides by Workers (Part 1, 1979). In the late 1990's an ICRP task group was appointed to develop a biokinetic and dosimetric model of the alimentary tract that reflects updated information and addresses current needs in radiation protection. The new age-specific and gender-specific model, called the Human Alimentary Tract Model (HATM), has been completed and will replace the GI model of Publication 30 in upcoming ICRP documents. This paper discusses the basis for the structure and parameter values of the HATM, summarises the uncertainties associated with selected features and types of predictions of the HATM and examines the sensitivity of dose estimates to these uncertainties for selected radionuclides. Emphasis is on generic biokinetic features of the HATM, particularly transit times through the lumen of the alimentary tract, but key dosimetric features of the model are outlined, and the sensitivity of tissue dose estimates to uncertainties in dosimetric as well as biokinetic features of the HATM are examined for selected radionuclides. (authors)

Evaluation of the effective dose equivalent to tbe public of Pavia after the Chernobyl nuclear accident

International Nuclear Information System (INIS)

Altieri, S.; Berzero, A.; Meloni, S.; Rosti, G.; Genova, N.

1988-01-01

The Chernobyl radionuclide monitoring campaign in air particulate and foodstuffs was carried out and continued up to June 1987. On the basis of collected data estimates of the collective effective dose equivalent commitment to the public of province of Pavia, by external irradiation or by inhalation, were carried out and are reported in the present paper

Committed effective dose determination in southern Brazilian cereal flours.

Science.gov (United States)

Scheibel, V; Appoloni, C R

2013-01-01

The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in eight commercial samples of South-Brazilian cereal flours (soy, wheat, cornmeal, cassava, rye, oat, barley and rice flours). The radioactivity traces of (228)Th, (228)Ra, (226)Ra, (40)K, (7)Be and (137)Cs were measured by gamma-ray spectrometry employing an HPGe detector of 66 % relative efficiency. The efficiency curve has taken into account the differences in densities and chemical composition between the matrix and the certified sample. The highest concentration levels of (228)Th and (40)K were 3.5±0.4 and 1469±17 Bq kg(-1) for soy flour, respectively, within the 95 % confidence level. The lower limit of detection for (137)Cs ranged from 0.04 to 0.4 Bq kg(-1). The highest committed effective dose was 0.36 μSv.y(-1) for (228)Ra in cassava flour (adults). All committed effective doses determined at the present work were lower than the International Atomic Energy Agency dose limit of 1 mSv.y(-1), to the public exposure.

Committed effective dose determination in southern Brazilian cereal flours

International Nuclear Information System (INIS)

Scheibel, V.; Appoloni, C. R.

2013-01-01

The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in eight commercial samples of South-Brazilian cereal flours (soy, wheat, cornmeal, cassava, rye, oat, barley and rice flours). The radioactivity traces of 228 Th, 228 Ra, 226 Ra, 40 K, 7 Be and 137 Cs were measured by gamma-ray spectrometry employing an HPGe detector of 66 % relative efficiency. The efficiency curve has taken into account the differences in densities and chemical composition between the matrix and the certified sample. The highest concentration levels of 228 Th and 40 K were 3.5±0.4 and 1469±17 Bq kg -1 for soy flour, respectively, within the 95 % confidence level. The lower limit of detection for 137 Cs ranged from 0.04 to 0.4 Bq kg -1 . The highest committed effective dose was 0.36 μSv.y -1 for 228 Ra in cassava flour (adults). All committed effective doses determined at the present work were lower than the International Atomic Energy Agency dose limit of 1 mSv.y -1 , to the public exposure. (authors)

Annual dose at the exclusion area boundary of a multi-unit CANDU site

International Nuclear Information System (INIS)

Gagnon, N.; Bobb, C.R.; Tsang, K.T.

1997-01-01

The annual dose to members of the public from CANDU nuclear power stations is dominated by the contribution from airborne effluents. The principal radionuclides contributing to the annual dose are tritium, carbon-14 and noble gases. The tritium is released as tritiated heavy-water vapour; the carbon-14 is released principally as carbon dioxide. To demonstrate compliance with the public dose limit, AECL has calculated the annual dose from airborne emissions from 10 CANDU units at an extended Wolsong site. The analysis has used the treatment of atmospheric dispersion described in the US Regulatory Guide 1.111 and programmed in the code XOQDOQ. The analysis has then modelled the transport of these airborne emissions through the environment as they expose the critical group using the US Regulatory Guide 1.109. the study takes account of the different annual emissions from each unit to reflect the different design features of the units. This study also includes a treatment of topography and makes allowances for building wake effects

Comparative study of radiological impact of nuclear power plant and coal-fired power plant: estimation of radiation dose to public from nuclear power plant and coal-fired power plant generation

International Nuclear Information System (INIS)

Umbara, Heru; Yatim, Sofyan

1998-01-01

Radiation impact assessment of Nuclear Power Plant and Coal-Fired Power Plant in Muria Penninsula was carried out. The computation of radionuclide releases to the atmosphere subjects to gaussian plume model, on the other hand, the radionuclide transfer model between environmental compartment (pathway) follow concentration factor methods. Both models are compiled in GENII-The Hanford Environmental Radiation Dosimetry Software System, which is used in the assessment. Most of all input data for GENII package are site specific, such as meteorological data, stack flow, stack height, population, local consumption except the transfer factor data are taken from the GENII package. The results show that during operation of NPP the maximal exposed individual received annual effective dose 150 nSv at 300 -700 m from the site toward east otherwise in operation of CPP the maximal exposed individual received annual effective dose 410 nSv in the same distance and direction. Both results of the maximal exposed individual received annual effective dose about 0,003 % and 0,008 % of whole body annual dose limit for members of public for NPP and CPP. (author)

Dose conversion coefficients for high-energy photons, electrons, neutrons and protons

CERN Document Server

Sakamoto, Y; Sato, O; Tanaka, S I; Tsuda, S; Yamaguchi, Y; Yoshizawa, N

2003-01-01

In the International Commission on Radiological Protection (ICRP) 1990 Recommendations, radiation weighting factors were introduced in the place of quality factors, the tissue weighting factors were revised, and effective doses and equivalent doses of each tissues and organs were defined as the protection quantities. Dose conversion coefficients for photons, electrons and neutrons based on new ICRP recommendations were cited in the ICRP Publication 74, but the energy ranges of theses data were limited and there are no data for high energy radiations produced in accelerator facilities. For the purpose of designing the high intensity proton accelerator facilities at JAERI, the dose evaluation code system of high energy radiations based on the HERMES code was developed and the dose conversion coefficients of effective dose were evaluated for photons, neutrons and protons up to 10 GeV, and electrons up to 100 GeV. The dose conversion coefficients of effective dose equivalent were also evaluated using quality fact...

Vertical Distribution and Estimated Doses from Artificial Radionuclides in Soil Samples around the Chernobyl Nuclear Power Plant and the Semipalatinsk Nuclear Testing Site

Science.gov (United States)

Taira, Yasuyuki; Hayashida, Naomi; Tsuchiya, Rimi; Yamaguchi, Hitoshi; Takahashi, Jumpei; Kazlovsky, Alexander; Urazalin, Marat; Rakhypbekov, Tolebay; Yamashita, Shunichi; Takamura, Noboru

2013-01-01

For the current on-site evaluation of the environmental contamination and contributory external exposure after the accident at the Chernobyl Nuclear Power Plant (CNPP) and the nuclear tests at the Semipalatinsk Nuclear Testing Site (SNTS), the concentrations of artificial radionuclides in soil samples from each area were analyzed by gamma spectrometry. Four artificial radionuclides (241Am, 134Cs, 137Cs, and 60Co) were detected in surface soil around CNPP, whereas seven artificial radionuclides (241Am, 57Co, 137Cs, 95Zr, 95Nb, 58Co, and 60Co) were detected in surface soil around SNTS. Effective doses around CNPP were over the public dose limit of 1 mSv/y (International Commission on Radiological Protection, 1991). These levels in a contaminated area 12 km from Unit 4 were high, whereas levels in a decontaminated area 12 km from Unit 4 and another contaminated area 15 km from Unit 4 were comparatively low. On the other hand, the effective doses around SNTS were below the public dose limit. These findings suggest that the environmental contamination and effective doses on the ground definitely decrease with decontamination such as removing surface soil, although the effective doses of the sampling points around CNPP in the present study were all over the public dose limit. Thus, the remediation of soil as a countermeasure could be an extremely effective method not only for areas around CNPP and SNTS but also for areas around the Fukushima Dai-ichi Nuclear Power Plant (FNPP), and external exposure levels will be certainly reduced. Long-term follow-up of environmental monitoring around CNPP, SNTS, and FNPP, as well as evaluation of the health effects in the population residing around these areas, could contribute to radiation safety and reduce unnecessary exposure to the public. PMID:23469013

Vertical distribution and estimated doses from artificial radionuclides in soil samples around the Chernobyl nuclear power plant and the Semipalatinsk nuclear testing site.

Directory of Open Access Journals (Sweden)

Yasuyuki Taira

Full Text Available For the current on-site evaluation of the environmental contamination and contributory external exposure after the accident at the Chernobyl Nuclear Power Plant (CNPP and the nuclear tests at the Semipalatinsk Nuclear Testing Site (SNTS, the concentrations of artificial radionuclides in soil samples from each area were analyzed by gamma spectrometry. Four artificial radionuclides ((241Am, (134Cs, (137Cs, and (60Co were detected in surface soil around CNPP, whereas seven artificial radionuclides ((241Am, (57Co, (137Cs, (95Zr, (95Nb, (58Co, and (60Co were detected in surface soil around SNTS. Effective doses around CNPP were over the public dose limit of 1 mSv/y (International Commission on Radiological Protection, 1991. These levels in a contaminated area 12 km from Unit 4 were high, whereas levels in a decontaminated area 12 km from Unit 4 and another contaminated area 15 km from Unit 4 were comparatively low. On the other hand, the effective doses around SNTS were below the public dose limit. These findings suggest that the environmental contamination and effective doses on the ground definitely decrease with decontamination such as removing surface soil, although the effective doses of the sampling points around CNPP in the present study were all over the public dose limit. Thus, the remediation of soil as a countermeasure could be an extremely effective method not only for areas around CNPP and SNTS but also for areas around the Fukushima Dai-ichi Nuclear Power Plant (FNPP, and external exposure levels will be certainly reduced. Long-term follow-up of environmental monitoring around CNPP, SNTS, and FNPP, as well as evaluation of the health effects in the population residing around these areas, could contribute to radiation safety and reduce unnecessary exposure to the public.

Vertical distribution and estimated doses from artificial radionuclides in soil samples around the Chernobyl nuclear power plant and the Semipalatinsk nuclear testing site.

Science.gov (United States)

Taira, Yasuyuki; Hayashida, Naomi; Tsuchiya, Rimi; Yamaguchi, Hitoshi; Takahashi, Jumpei; Kazlovsky, Alexander; Urazalin, Marat; Rakhypbekov, Tolebay; Yamashita, Shunichi; Takamura, Noboru

2013-01-01

For the current on-site evaluation of the environmental contamination and contributory external exposure after the accident at the Chernobyl Nuclear Power Plant (CNPP) and the nuclear tests at the Semipalatinsk Nuclear Testing Site (SNTS), the concentrations of artificial radionuclides in soil samples from each area were analyzed by gamma spectrometry. Four artificial radionuclides ((241)Am, (134)Cs, (137)Cs, and (60)Co) were detected in surface soil around CNPP, whereas seven artificial radionuclides ((241)Am, (57)Co, (137)Cs, (95)Zr, (95)Nb, (58)Co, and (60)Co) were detected in surface soil around SNTS. Effective doses around CNPP were over the public dose limit of 1 mSv/y (International Commission on Radiological Protection, 1991). These levels in a contaminated area 12 km from Unit 4 were high, whereas levels in a decontaminated area 12 km from Unit 4 and another contaminated area 15 km from Unit 4 were comparatively low. On the other hand, the effective doses around SNTS were below the public dose limit. These findings suggest that the environmental contamination and effective doses on the ground definitely decrease with decontamination such as removing surface soil, although the effective doses of the sampling points around CNPP in the present study were all over the public dose limit. Thus, the remediation of soil as a countermeasure could be an extremely effective method not only for areas around CNPP and SNTS but also for areas around the Fukushima Dai-ichi Nuclear Power Plant (FNPP), and external exposure levels will be certainly reduced. Long-term follow-up of environmental monitoring around CNPP, SNTS, and FNPP, as well as evaluation of the health effects in the population residing around these areas, could contribute to radiation safety and reduce unnecessary exposure to the public.

Survey of food radioactivity and estimation of internal dose from ingestion in China

International Nuclear Information System (INIS)

Zhang Jingyuan; Zhu Hongda; Han Peizhen

1988-01-01

In order to provide necessary bases for establishing 'Radionuclide Concentration Limits in Food stuffs', survey on radionuclide contents in Chinese food and estimation of internal dose from ingestion were carried out with the cooperation of 30 radiation protection establishments during the period 1982-1986. Activity concentrations in 14 categories (27 kinds) of Chinese food for 22 radionuclides were determined. In the light of three principal types of Chinese diet, food samples were collected from normal radiation background areas in 14 provinces or autonomous regions and three similarly elevated natural background areas. Annual intake by ingestion and resultant committed dose equivalents to general public for 15 radionuclides in these areas were estimated. In normal background areas the total annual intake of the 15 radionuclides by the public (adlut males) is about 4.2 x 10 4 Bq, and the resultant total committed dose equivalent is about 3.43 x 10 -4 Sv, but in two elevated natural background area the public annual intake and resulting committed dose equivalents for some natural radionulides are much higher than those in normal areas, while no obvious radiocontamination was discoveried relative contribution of each food category or each radionuclide to the total are discussed

Estimation of effective dose from limited cone beam X-ray CT examination

Energy Technology Data Exchange (ETDEWEB)

Iwai, Kazuo; Arai, Yoshinori; Hashimoto, Koji [Nihon Univ., Tokyo (Japan). School of Dentistry; Nishizawa, Kanae

2000-12-01

The limited cone beam X-ray CT (Ortho-CT) was developed on the basis of multi-functional panoramic apparatus, SCANORA (Soredex Co. Helsinki Finland). The imaging intensifier (I.I.) was built in this apparatus as a X-ray detection device instead of X-ray film. The signal provided from I.I. was converted from analog into digital by an analog-digital converter and image reconstitution was done as a three-directional image of the dimensions 3.8 cm of width, 3.0 cm height and 3.8 cm depth with the personal computer. The 3DX Multi image micro CT'' (3DX) was developed along similar lines by MORITA Co., Ltd. (Kyoto, JAPAN). In this study, the stochastic effect on organ and tissue caused by examinations using Ortho-CT and 3DX was measured. The effective dose was estimated according to the recommendation of ICRP60 and was compared with those of panoramic radiography and computed tomography. The irradiation conditions were as follows: 85 kV, 10 mA with the filtration of 3 mmAl and added 1 mmCu for Ortho-CT, and 80 kV, 2 mA and the filtration of 3.1 mmAL for 3DX. The measurement of organ and tissue dose was performed using an anthropomorphic Rando woman phantom (Alderson Research Laboratories Co., Stanfora, CN), as well as by using two different type of thermoluminescent dosimeter (TLD); Panasonic UD-170A (BeO) and UD-110S (CaSO{sub 4}: Tm). The UD-170A was for dose measurement of the inner useful X-ray beams, while the UD-110S was for outer beams. The measured organ and tissue were those recommended with ICRP60 (gonad, breast, bone marrow, lung, thyroid gland, esophagus, stomach, colon, liver, bladder, skin, brain, thymus, adrenal, kidney, spleen, pancrease, upper large intestine, uterus, eyes and major salivary gland). The imaging by Orhto-CT was made in the left maxillary 1st molar, left mandibular 1st molar and temporomandibular joint. 3DX measurement was made in the maxillary incisor region and middle ear regions other than the regions mentioned above. The skin

Dose control in road transport of radioactive material

International Nuclear Information System (INIS)

Gerulis, Eduardo

2013-01-01

The radiation doses to workers in the transport of radioactive material should be as low as reasonably achievable. The average doses of drivers and loaders, sampled in this thesis should be decreased. The demonstration of doses control in a road vehicle with radioactive material required by the current Brazilian regulation, CNEN NE 5.01 should be written in its own printed form with exposure values obtained in normally occupied positions from workers and members of the public, even when the consignment does not need 'exclusive use' (⅀IT ≤50). Through bibliographic research, modeling and field research, this research work shows that this demonstration of the control should be done by writing the registration accumulation of load, limited (⅀IT ≤50), also in the own printed form. It is for a better control method, in order to avoid the use of measuring equipment, to build standardization with foreign regulations, to the current occupational doses of radioprotection technicians, the costs and time, (important for consignment with radiopharmaceuticals short half-life) would be all smaller. Exposure values of the parameters used with this method are smaller than regulatory limits. The segregation distances between loads and the cabins of vehicles shall be showed by Brazilian regulation updated to contribute to these aims. (author)

Determination of dose equivalent and risk in thorium cycle

International Nuclear Information System (INIS)

Ney, C.L.V.N.

1988-01-01

In these report are presented the calculations of dose equivalent and risk, utilizing the dosimetric model described in publication 30 of the International Comission on Radiological Protection. This information was obtained by the workers of the thorium cycle, employed at the Praia and Santo Amaro Facilities, by assessing the quantity and concentration of thorium in the air. The samples and the number of measurements were established through design of experiments techniques, and the results were evaluated with the aid of variance analysis. The estimater of dose equivalent for internal and external radiation exposure and risk associated were compared with the maximum recommended limits. The results indicate the existence of operation areas whose values were above those limits, requiring so an improvement in the procedures and services in order to meet the requirements of the radiological protetion. (author) [pt

The Alpha value decrease when the annual individual effective dose decreases?

International Nuclear Information System (INIS)

Sordi, Gian M.; Marchiusi, Thiago; Sousa, Jefferson de J.

2008-01-01

A recent IAEA publication tells that a few entities took different alpha values for maxima individual doses. Beyond to disregard the international agencies, that recommend only one alpha value for each country, the alpha values decreases when the individual doses decreases and the practice happens exactly the conversely as we will show in this paper. We will prove that the alpha value increase when the maximum individual doses decreases in a four different manner. The first one we call the theoretical conception and it is linked to the emergent of the ALARA policy and to the purpose that led to the 3/10 of the annual limits, for to decrease the individual doses as a first resort and a 1/10 as a last resort. The second prove will be based in a small mine example used in the ICRP publication number 55 concerning to the optimization and the quantitative decision-aiding techniques in radiological protection where we will determine the alpha value ranges in which each radiological protection options becomes the analytical solution. The third prove will be based in the determination of the optimized thickness example of a plane shielding for a radiation source exposed in the ICRP publication number 37. We will use, also, the numerical example provided there. Eventually, as four prove we will show that the alpha value dos not only increases with the maximum individual dose decrease, but also, with the shielding geometry. (author)

The public committed effective dose caused by consumption of foods and foodstuffs in Ninh Thuan

International Nuclear Information System (INIS)

Nguyen Trong Ngo; Nguyen Thanh Binh; Le Nhu Sieu; Truong Y; Nguyen Van Phuc; Nguyen Thi Linh; Nguyen Dinh Tung

2014-01-01

Based on the data set about radionuclides concentration in foods and foodstuffs obtained from the implementation of the National Projects on “Investigation on radionuclides and toxic elements concentration in the main kinds of foods and foodstuffs of Vietnam” and “Assessment of Marine Environmental Radioactivity Status for two selected sites of Nuclear Power Plant in the near future at Ninh Thuan Province”, a calculation software of the International Commission for Radiological Protection (ICRP), the public committed effective doses (for adult only) caused by consumption of main foods & foodstuffs in the studied experimental region were estimated. In general, the committed effective doses for adult public caused by the daily intake of radionuclides of U, 232 Th, 210 Pb, 210 Po, 226 Ra, 40 K, 90 Sr, 137 Cs and 239,240 Pu are: 7.9x10 -5 , 4.1x10 -6 , 1.1x10 -2 , 1.7x10 -1 , 1.4x10 -3 , 1.2x10 -1 , 2.32x10 -4 , 1.9x10 -4 , 2.7x10 -9 (mSv/year), respectively, and the contribution of U, Th series, 40 K and artificial radionuclides are 61.3%, 38.6% and 0.1%, respectively. (author)

Exposure dose estimation of nursing personnel and visitors following "1"2"5I brachytherapy

International Nuclear Information System (INIS)

Nakazato, Kazuhisa; Kikuchi, Hirosumi; Hotta, Harumi; Nishizawa, Kunihide

2007-01-01

An automated access management system to the controlled sickrooms for "1"2"5I brachytherapy was developed. The system consists of access control and video surveillance units. The patients implanted "1"2"5I seeds were isolated for about 20 h after surgery in the controlled sickrooms. The maximum doses and dose rates of the nurses and visitors were estimated by using the legal upper limit activity of 1,300 MBq, the measured longest staying time, and the shortest distance between the patients and individuals. Video analysis revealed activities of the nurses, patients, and visitors in the controlled sickroom, and relationships between the access frequency and staying time. The nurses' measured doses ranged from 1 to 3 μSv, and averaged 1.6 μSv. The nurses' maximum dose and dose rate were 16 μSv and 5.6 nSv·h"-"1·MBq"-"1. The visitors' maximum dose and dose rate were 6 μSv and 2.6 nSv·h"-"1·MBq"-"1. The nurses and visitors' exposure doses per patient were estimated to be negligible compared with the annual limit of the public. (author)

Canadian and United States regulatory models compared: doses from atmospheric pathways

International Nuclear Information System (INIS)

Peterson, S-R.

1997-01-01

CANDU reactors sold offshore are licensed primarily to satisfy Canadian Regulations. For radioactive emissions during normal operation, the Canadian Standards Association's CAN/CSA-N288.1-M87 is used. This standard provides guidelines and methodologies for calculating a rate of radionuclide release that exposes a member of the public to the annual dose limit. To calculate doses from air concentrations, either CSA-N288.1 or the Regulatory Guide 1.109 of the United States Nuclear Regulatory Commission, which has already been used to license light-water reactors in these countries, may be used. When dose predictions from CSA-N288.1 are compared with those from the U.S. Regulatory Guides, the differences in projected doses raise questions about the predictions. This report explains differences between the two models for ingestion, inhalation, external and immersion doses

Derived intervention levels for application in controlling radiation doses to the public in the event of a nuclear accident or radiological emergency

International Nuclear Information System (INIS)

1986-01-01

This document sets out the principles and procedures for estimating derived intervention levels (DILs) and illustrates the application of these procedures to the estimation of DILs for a range of nuclides and exposure pathways, as aids to decisions on the application of protective measures for the public in the early and intermediate phases of a nuclear accident. The levels are derived subject to a number of assumptions about the intervention level of dose, the characteristics of the released material, the habits of the exposed individuals and local environmental conditions. Some guidance is given on the sensitivity of the estimated DILs to plausible variations in the above assumptions. The detailed procedures described in the document for estimating DILs and illustrations of their application are limited to accidental releases to the atmosphere

Effective dose calculation in CT using high sensitivity TLDs

International Nuclear Information System (INIS)

Brady, Z.; Johnston, P.N.

2010-01-01

Full text: To determine the effective dose for common paediatric CT examinations using thermoluminescence dosimetry (TLD) mea surements. High sensitivity TLD chips (LiF:Mg,Cu,P, TLD-IOOH, Thermo Fisher Scientific, Waltham, MA) were calibrated on a linac at an energy of 6 MY. A calibration was also performed on a superricial X-ray unit at a kilovoltage energy to validate the megavoltage cali bration for the purpose of measuring doses in the diagnostic energy range. The dose variation across large organs was assessed and a methodology for TLD placement in a 10 year old anthropomorphic phantom developed. Effective dose was calculated from the TLD measured absorbed doses for typical CT examinations after correcting for the TLD energy response and taking into account differences in the mass energy absorption coefficients for different tissues and organs. Results Using new tissue weighting factors recommended in ICRP Publication 103, the effective dose for a CT brain examination on a 10 year old was 1.6 millisieverts (mSv), 4.9 mSv for a CT chest exa ination and 4.7 mSv for a CT abdomen/pelvis examination. These values are lower for the CT brain examination, higher for the CT chest examination and approximately the same for the CT abdomen/ pelvis examination when compared with effective doses calculated using ICRP Publication 60 tissue weighting factors. Conclusions High sensitivity TLDs calibrated with a radiotherapy linac are useful for measuring dose in the diagnostic energy range and overcome limitations of output reproducibility and uniformity asso ciated with traditional TLD calibration on CT scanners or beam quality matched diagnostic X-ray units.

Cosmogenic radioberyllium and background radiation dose to the general public

International Nuclear Information System (INIS)

Poeschl, M.; Ohera, M.

2008-01-01

To discover the causes of the presence of abnormal Be concentrations (anthropogenic or natural or cosmogenic source) in the area of the Kralicky Sneznik mountain massive (in the northeast of the Czech Republic, altitude of about 800 m), concentrations of 7 Be and 10 Be were also assayed in selected environmental components in the years of 2005 - 2007. The 10 Be concentrations in soils (80.39x10 6 - 210.45x10 6 atom g -1 ) and activity concentrations of 7 Be in soils and wet deposition were very low (1.3 - 5.3 Bq kg -1 and 0.6 - 4.5 Bq l -1 , resp.). However, activities of 7 Be in birch leaves and grass (dry matter) reached relatively high values (up to 1000 Bq kg -1 ) and, in addition, showed out their significant seasonal growth. In the work the probable contribution of the cosmogenic 7 Be activities to background radiation dose to the general public is discussed. (authors)

A review of data on the effects of low and low dose-rate radiation with special reference to the dose limit problem

International Nuclear Information System (INIS)

Matsudaira, Hiromichi

1977-01-01

This is a review of data pertaining to detection and quantification of the effects after exposure to low LET radiations delivered at low and low dose-rate, i.e., at a level of maximum permissible dose for the radiation workers, on experimental materials ranging from plant to rodents and on some human populations. Irradiation at a dose of a few rad is reported to induce mutation or malignant transformation in some selected model systems, with a linear dose-effect relationship. Moreover, the incidence of the chromosome aberrations in spermatocytes is reported to be elevated in the scorpiones (Tityus bahiensis) collected in a region of high natural background radiations (several rem/year). An increase in the incidence of childhood malignancies is reported among children exposed in utero to diagnostic X-rays. Appreciable increase in the incidence of genetic diseases due possibly to chromosome aberrations is also reported among population living in a region of high natural background radiations. Points are raised and discussed as to the interpretation and particularly application of these data to the estimation of somatic and genetic risks of human population from man-made radiations. Recent attempts of risk-benefit analysis with populations subjected to mass X-ray examination of the chest and stomac are referred to. Since we are unaware of the actual injuries due to the exposure even at the level of radiation workers (5 rem/year), it is out of the capacity of a biologist to afford the basis for the decision of limiting the exposure of general population due to the light water reactor operation to 5 mrem/year. (auth.)

Problems is applying new internal dose coefficients to radiation control

Energy Technology Data Exchange (ETDEWEB)

Sato, Yuichi [Oarai Laboratory, Chiyoda Technol Corporation, Ibaraki (Japan)

1998-06-01

The author discussed problems concerning the conceivable influence in the radiation control and those newly developing when the new internal dose coefficients are applied in the law in the future. For the conceivable influence, the occupational and public exposure was discussed: In the former, the effective dose equivalent limit (at present, 50 mSv/y) was thought to be reduced and in the latter, the limit to be obscure although it might be more greatly influenced by the new coefficients. For newly developing problems, since the new biological model which is more realistic was introduced for calculation of the internal dose and made the calculation more complicated, use of computer is requisite. The effective dose of the internal exposure in the individual monitoring should be conveniently calculated as done at present even after application of the new coefficients. For calculation of the effective dose of the internal exposure, there are such problems as correction of the inhaled particle size and of the individual personal parameter. A model calculation of residual rate in the chest where the respiratory tract alone participated was presented as an example but for the whole body, more complicated functions were pointed out necessary. The concept was concluded to be incorporated in the law in a convenient and easy manner and a software for calculation of internal dose using the new coefficients was wanted. (K.H.)

Over 600 mobile base station measurements in Buenos Aires City, how far are general public limits?

International Nuclear Information System (INIS)

Aguirre, Anibal; Dalmas Di Giovanni, Norberto; Garcia Diaz, Javier; Douthat, Analia; Munoz, Claudio; Saint Nom, Roxana

2008-01-01

Full text: The general public worries about non ionizing radiation (NIR), produced by mobile base station aren't new, mainly in big cities like Buenos Aires where the amount of antennas of wide communication services (mobile, data links, FM Broadcasting, TV and others), are so considerable. Buenos Aires City has 3 million inhabitants in a surface of 203 km 2 and has about 700 mobile base stations between macro and micro cells. When public demand arrived to local government authorities, the first logical step was to promote a big measurement campaign to do a radiation map of the city. This measurement campaign has been done for two measurement teams, one with CITEFA NIR specialists and the other with ITBA NIR specialists, during 6 months. Local NRI measurement guidelines established that has to be taken between 12 and 16 points around NRI source in a 50 m or 100 m radius, depending on the neighbourhood buildings features (buildings located in the centre of the city aren't the same as a quiet house district). The obtained measured values had to be compared with Argentinean exposure limits, which are the same that ICNIRP limits. With over 7500 measured points in the entire city with wide band instruments (200 kHz-40 GHz), we have started our analysis. This information has been used by local authorities to upgrade a radiation map that can be consulted on the local government internet site. We have compared the obtained values with some international general public exposure limits. From this comparison we found that over 90% of measured points were under general public ICNIRP cell phone frequency limits, but the surprise was that, about 80% of them were below Russian limits (6 V/m) that are the strictest of the world. According to the obtained results and to provide a conclusion we could say that, if in a big city with a very high NIR sources density, we find a majority of lower limits values, this situation will be better in a little town with few NIR sources. However

Dose limits, constraints, reference levels. What does it mean for radiation protection?; Grenzwerte, Richtwerte, Referenzwerte. Was bedeutet das fuer den Strahlenschutz

Energy Technology Data Exchange (ETDEWEB)

Breckow, J. [Technische Hochschule Mittelhessen (THM), Giessen (Germany). Inst. fuer Medizinische Physik und Strahlenschutz (IMPS)

2016-07-01

The established concept of radiation protection with its basic principles justification, optimization, and limitation has proved its value and is going to be continued. In its deeper meaning, however, the concept is rather subtle and complex. Furthermore, in some aspects there remain some breaches or inconsistencies. This is just true for the terms dose limit, reference lever, and constraint that are tightly associated with the radiation protection principles. In order to guarantee the ability of radiation protection in whole extent, the subtle differences of meaning have to be communicated. There is a permanent need to defend the conceptual function of these terms against deliberate or undeliberate misinterpretations. Reference levels are definitely not the same as dose limits and they may not be misused as such. Any attempt to misinterpret fundamental radiation protection principles for selfish purposes should discouraged vigorously.

Application in the Nordic countries of ICRP publication 26

International Nuclear Information System (INIS)

2006-01-01

The radiation protection institutes of the five Nordic countries, Denmark, Finland, Iceland, Norway and Sweden, published in 1976 a joint report on the applicability of international radiation protection recommendations in the Nordic countries. The report was mainly based on the set of recommendations issued by the International Commission on Radiological Protection (ICRP). In the report it was stated that 'if the basic recommendations of ICRP are subsequently revised, it is the intention of the radiation protection institutes to consider equivalent changes in the recommended basis for regulatory texts and, if there is full agreement, jointly to announce changes which may be made in respect to the principles which have been recommended here'. In 1977 ICRP published its revised basic recommendations (ICRP Publication 26) which resulted from the examination of new information during the last decade and since the Commission's previous basic recommendations (ICRP Publication 9 adopted in 1965. In 1978 the representatives of the radiation protection institutes of the Nordic countries agreed at their meeting in Helsinki to prepare a joint policy document on the application of the revised ICRP recommendations in the Nordic countries. In common with the previous joint report of the Nordic radiation protection institutes of 1976 the present recommendations deal only with ionizing radiation. In the new recommendations ICRP has more clearly than in the previous recommendations systematized the basic principles in radiation protection by crystallizing its system of dose limitation in three main points: a) no practice shall be adopted unless its introduction produces a positive net benefit; b) all exposures shall be kept as low as reasonably achievable, economic and social factors being taken into account; and C) the dose equivalent to individuals shall not exceed the limits recommended for the appropriate circumstances by the Commission. The levels for basic dose

The Opportunities and Limitations of Using Mechanical Turk (MTurk) in Public Administration and Management Scholarship

DEFF Research Database (Denmark)

Stritch, Justin Michael; Pedersen, Mogens Jin; Taggert, Gabel

2017-01-01

Other social science fields are increasingly conducting research using Amazon’s Mechanical Turk (MTurk)—an online crowdsourcing platform—but how might MTurk be useful to public administration and management research? This article provides an introduction of the platform and considers both...... the opportunities and limitations for using MTurk in public administration and management scholarship. We find that MTurk might be relevant for examining particular types of research questions. We identify five areas where MTurk data may complement and enhance public administration and management research: (1...

Public exposure due to radioactive liquid effluent discharges from Instituto de Pesquisas Energeticas Nucleares/IPEN

International Nuclear Information System (INIS)

Rocca, Fatima F.D.

1995-01-01

The physical and social-economic characterization of aquatic environment influenced by IPEN was performed and possible exposure pathways were identified. The effective dose equivalent to the critical groups were estimated by using a mathematic model that simulate radionuclide transport through environment components, and dosimetric models that relate activity at environment components to public exposure. This study has concluded that there is not a single critical group that receives the highest dose equivalents from the source, but all the populational groups potentially exposed receive doses at the same level, and then all of them must be considered in a radiological assessment process. The results showed that the public exposure due to liquid discharges from IPEN remains bellow established dose limits. (author). 58 refs., 28 figs., 24 tabs

External dose measurements for patients receiving therapeutic I-131 for thyroid cancer

International Nuclear Information System (INIS)

Molfetas, M.; Kottou, S.

2002-01-01

Iodine-131 is a well established and effective treatment, supplementing surgery, in differentiated thyroid carcinoma. Iodine-131 except from its β-emission, that generates a cell-killing effect in a small area, has also a γ-emission irradiating distant tissues and even people who are close enough with the treated patient. The International Commission on Radiation Protection, ICRP has estimated the probability of a radiation-induced fatal cancer for the whole population at 5.0 % per sievert for low doses and at low dose rates and at 1.3 % for serious genetic diseases. For elderly people the probability seems to be 3 to 10 times lower, whereas for children up to the age of 10 years, 2-3 times higher. These findings led the ICRP to recommend new dose limits, lower than the previous ones. The European Union has endorsed the ICRP recommendations and the Council issued two directives, with which the Greek legislation complied recently. The current annual public dose limit is 1 mSv, while in the new Greek legislation the concept of dose constrains (0.5 m Sv in Greece) has also been proposed as a goal to reach whenever possible

Principles for the establishment of upper bounds to doses to individuals from global and regional sources

International Nuclear Information System (INIS)

1989-01-01

The IAEA Safety Guide, Safety Series No. 77 (1986), Principles for Limiting Releases of Radioactive Effluents into the Environment, identifies the concept of upper bounds to individual dose. They are the fractions of the dose limit for members of the public allocated to the various different sources and practices which can give rise to individual exposure. This Guide is concerned with the contributions to individual dose which may arise from other sources in the same region and also from sources which are far away but which, because of the nature of the radionuclides involved, give rise to a global component of dose. Consideration is given to the need for control of such exposures and the means by which it could be achieved. The text may be seen as providing expansion of the guidance given in Safety Series No. 77. 24 refs

Georgia fishery study: implications for dose calculations

International Nuclear Information System (INIS)

Turcotte, M.D.S.

1983-01-01

Fish consumption will contribute a major portion of the estimated individual and population doses from L-Reactor liquid releases and Cs-137 remobilization in Steel Creek. It is therefore important that the values for fish consumption used in dose calculations be as realistic as possible. Since publication of the L-Reactor Environmental Information Document (EID), data have become available on sport fishing in the Savannah River. These data provide SRP with site-specific sport fish harvest and consumption values for use in dose calculations. The Georgia fishery data support the total population fish consumption and calculated dose reported in the EID. The data indicate, however, that both the EID average and maximum individual fish consumption have been underestimated, although each to a different degree. The average fish consumption value used in the EID is approximately 3% below the lower limit of the fish consumption range calculated using the Georgia data. A fish consumption value of 11.3 kg/yr should be used to recalculate dose to the average individual from L-Reactor restart. Maximum fish consumption in the EID has been underestimated by approximately 60%, and doses to the maximum individual should also be recalculated. Future dose calculations should utilize an average fish consumption value of 11.3 kg/yr, and a maximum fish consumption value of 34 kg/yr

Bases for establishing radiation exposure limits

International Nuclear Information System (INIS)

Pochin, E.E.

1977-01-01

It is an essential requirement of good radiation protection that all unnecessary exposure of people should be avoided and that any necessary exposure, whether of workers or of members of the general public, should be minimised. It is, however, an additional requirement that such necessary exposures should not exceed certain stated limits. These principles are based on the possibility that even the smallest exposures may involve some risk of harm, that any risk of harm should be justifiable by the circumstances necessitating it, and that risk should always be limited to an appropriately low level. The bases for establishing exposure limits must therefore involve an assessment of the risk involved in any form of radiation exposure, and an opinion as to the degree of safety that should be ensured in circumstances which necessitate any occupational or public exposure to radiation. There is increasing quantitative evidence on the frequency on which harm, and particularly the induction of malignancies, may be caused in people exposed to radiation at high doses; and somewhat clearer bases than previously for inferring the possible frequencies at low doses. It is therefore easier to assess the degree of safety ensured by restricting radiation exposure to particular levels. The degree of safety which should be regarded as appropriate in different circumstances remains a matter for review, but suggestions are made as to levels which would be advocated by informed opinion, and the exposure limits which would correspond to these. It is clear also that a comparable degree of safety should be ensured whether the radiation exposure involves the whole body more of less uniformly, or individual tissues or organs selectively. Increasing epidemiological evidence is available on the relative sensitivity to radiation induction of malignancies in a number of organs, and to the apparently much lower sensitivity of other organs; and experimental evidence in animals allows a comparable

Risk ratios for use in establishing dose limits for occupational exposure to radiation

International Nuclear Information System (INIS)

Metcalf, P.E.; Winkler, B.C.

1980-01-01

Dose limits for occupational exposure to radiation may be established by comparing the associated mortality risk with apparently accepted levels of industrial mortality risk due to conventional hazards. Average levels of industrial mortality risk rates are frequently quoted and used in such comparisons. However, within particular occupations or industries certain groups of workers will be exposed to higher levels of risk than the average, again an apparently accepted situation. A study has been made of the ratios of maximum to average industrial mortality risk currently experienced in some South African industries. Such a ratio may be used to assess the acceptability of maximum individual-to-average exposures in particular groups of exposed individuals. (author)

Evolution of radiation doses received by workers and the public during the transportation of radioactive materials in France

International Nuclear Information System (INIS)

Hamard, J.; Fignon, M.; Mauny, G.; Bernard, H.; Morin, J.

1989-01-01

This study makes an inventory of external irradiation dose equivalents and collective dose equivalents received by workers and the public during the transportation of radioactive materials in France between 1982 and 1988 (in the following, the authors use only the term dose). It deals with the transport of radiopharmaceuticals, irradiated fuels, wastes and other various radioactive materials. The evolution of the doses is referred to the variation of the number of packages, the mass on the volume transported for these main categories of materials. The transportation of radioactive materials uses various transport means: road, rail, air, and implies the intervention of various societies. Most of them have taken part in this study. Most societies involved in the transport carry out an individual dosimetry of the workers. But the decisions to carry such a dosimetry depends on the appreciation of the employer in relation with the more or less evident level of risk resulting from the transport and handling of the radioactive materials. The relatively low level of risk in current situations could incite some carriers not to carry out individual dosimetry. Thus the knowledge of individual doses essentially variables with the workers would therefore be difficult

Internal Dosimetry Monitoring- Detection Limits for a Selected Set of Radionuclides and Their Translation Into Committed Effective Dose

International Nuclear Information System (INIS)

Brandl, A.; Hrnecek, E.; Steger, F.

2004-01-01

To harmonize the practice of internal dosimetry monitoring across the country, the Austrian Standards Institute is currently drafting a new set of standards which are concerned with occupational incorporation monitoring of individuals handling non-sealed radioactive material. This set of standards is expected to consist of three parts discussing the general necessity and frequency, the requirements for monitoring institutions, and the determination and rigorous calculation of committed effective dose after incorporation of radioactive material, respectively. Considerations of the requirements for routine monitoring laboratories have led to an evaluation of the detection limits for routine monitoring equipment. For a selected set of radionuclides, these detection limits are investigated in detail. The main emphasis is placed on the decay chains of naturally occurring radionuclides showing some significant potential for being out of equilibrium due to chemical processes in certain mining industries. The radionuclides considered in this paper are 226Ra, 228Ra, 228Th, 232Th, 234U, 235U, and 238U. Given the routine monitoring intervals of the Austrian Standard, these detection limits are translated into information on committed effective dose. This paper investigates whether routine monitoring equipment is sufficient to ensure compliance with EC directive 96/29/Euratom for this selected set of radionuclides. (Author) 9 refs

Expansive or limitative strategy? A case study of organisational responses to new public health.

Science.gov (United States)

Nielsen, Annegrete Juul; Knudsen, Morten; Finke, Katrine

2008-01-01

Since the emergence of new public health in the 1970s, health has not merely been considered the absence of disease, but physical, mental and social wellbeing. This article seeks to analyzes the implications of this broad concept of health at an organizational level. The paper presents a qualitative case study of boundary drawing in a Danish municipal agency in charge of planning and conducting health promoting and disease preventing activities from 1989 to 2005. The theoretical framework draws on Niklas Luhmann's organization theory. Two different organizational answers were found to the challenges inherent in the broad concept of new public health. First, the organization tried to increase its size and incorporate as many aspects of the environment as possible. This expansive strategy jeopardised the identity of the organization. Second, the organization tried to keep clear and tight boundaries and from this position irritate entities in the environment. This limitative strategy made the organization spend relatively more energy on organizing and controlling itself than on public health work. The case study shows how a broad concept of health makes boundary management topical in organizations dealing with health promotion and disease prevention. Organizations in charge of public health activities need to reflect on how they can create intelligent compensations for the disadvantages involved in an expansive or a limitative strategy. The broad concept of health inherent in new public health has been widely accepted and yet its challenges to organizational boundary drawing have attracted little attention. This paper provides an analysis of these challenges.

TU-C-18A-01: Models of Risk From Low-Dose Radiation Exposures: What Does the Evidence Say?

International Nuclear Information System (INIS)

Bushberg, J; Boreham, D; Ulsh, B

2014-01-01

At dose levels of (approximately) 500 mSv or more, increased cancer incidence and mortality have been clearly demonstrated. However, at the low doses of radiation used in medical imaging, the relationship between dose and cancer risk is not well established. As such, assumptions about the shape of the dose-response curve are made. These assumptions, or risk models, are used to estimate potential long term effects. Common models include 1) the linear non-threshold (LNT) model, 2) threshold models with either a linear or curvilinear dose response above the threshold, and 3) a hormetic model, where the risk is initially decreased below background levels before increasing. The choice of model used when making radiation risk or protection calculations and decisions can have significant implications on public policy and health care decisions. However, the ongoing debate about which risk model best describes the dose-response relationship at low doses of radiation makes informed decision making difficult. This symposium will review the two fundamental approaches to determining the risk associated with low doses of ionizing radiation, namely radiation epidemiology and radiation biology. The strengths and limitations of each approach will be reviewed, the results of recent studies presented, and the appropriateness of different risk models for various real world scenarios discussed. Examples of well-designed and poorly-designed studies will be provided to assist medical physicists in 1) critically evaluating publications in the field and 2) communicating accurate information to medical professionals, patients, and members of the general public. Equipped with the best information that radiation epidemiology and radiation biology can currently provide, and an understanding of the limitations of such information, individuals and organizations will be able to make more informed decisions regarding questions such as 1) how much shielding to install at medical facilities, 2) at

TU-C-18A-01: Models of Risk From Low-Dose Radiation Exposures: What Does the Evidence Say?

Energy Technology Data Exchange (ETDEWEB)

Bushberg, J [UC Davis Medical Center, Sacramento, CA (United States); Boreham, D [McMaster University, Ontario, CA (Canada); Ulsh, B

2014-06-15

At dose levels of (approximately) 500 mSv or more, increased cancer incidence and mortality have been clearly demonstrated. However, at the low doses of radiation used in medical imaging, the relationship between dose and cancer risk is not well established. As such, assumptions about the shape of the dose-response curve are made. These assumptions, or risk models, are used to estimate potential long term effects. Common models include 1) the linear non-threshold (LNT) model, 2) threshold models with either a linear or curvilinear dose response above the threshold, and 3) a hormetic model, where the risk is initially decreased below background levels before increasing. The choice of model used when making radiation risk or protection calculations and decisions can have significant implications on public policy and health care decisions. However, the ongoing debate about which risk model best describes the dose-response relationship at low doses of radiation makes informed decision making difficult. This symposium will review the two fundamental approaches to determining the risk associated with low doses of ionizing radiation, namely radiation epidemiology and radiation biology. The strengths and limitations of each approach will be reviewed, the results of recent studies presented, and the appropriateness of different risk models for various real world scenarios discussed. Examples of well-designed and poorly-designed studies will be provided to assist medical physicists in 1) critically evaluating publications in the field and 2) communicating accurate information to medical professionals, patients, and members of the general public. Equipped with the best information that radiation epidemiology and radiation biology can currently provide, and an understanding of the limitations of such information, individuals and organizations will be able to make more informed decisions regarding questions such as 1) how much shielding to install at medical facilities, 2) at

Evaluation of averted doses to members of the Public by tap water restrictions after the Fukushima Daiichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Kinase, Sakae; Kimura, Masanori; Hato, Shinji

2014-01-01

The effectiveness of urgent protective measures such as tap water restrictions and bottled water supplies in the early stage of an emergency exposure situation was studied after the Fukushima Daiichi nuclear power plant accident. Temporal changes in the concentration of an important radionuclide –iodine 131– in tap water were analyzed using published data in Fukushima, Ibaraki and Tokyo. Averted doses to members of the public due to chronic intakes of iodine 131 through tap water restrictions were also evaluated using an internal dose calculation code, DSYS-chronic code. In addition, the costs of bottled water supplies were calculated approximately. Consequently, it was found that the apparent half-life of iodine 131 in tap water was 2.8±1.2 days. The averted equivalent doses to the thyroid of members of the public –1-year-old children– were found to have a maximum value of 8.2 mSv in a local area of Fukushima. In comparison with Fukushima, the bottled water supplies might be a large sum of money regardless of the low doses in Tokyo. In conclusion, apart from the bottled water supplies, the tap water restrictions implemented by the authorities would be effective after the Fukushima Daiichi nuclear power plant accident. (author)

Evaluation of the population dose due to the gaseous emission of a radioisotopes production unit

International Nuclear Information System (INIS)

Gordon, A.M.P.L.; Jacomino, V.M.F.; Sordi, G.-M.A.A.

1990-05-01

In order to control the emission of gaseous radioactive iodine from the unit responsible for the production of radioisotopes of IPEN-CNEN/SP, a discharge monitoring is carried out. In 1988 an activity of 65 GBq of I-131 was discharged to the environment. Based upon this value and the site analysis, the effective equivalent dose in the general public was evaluated for normal operation and for an incidental discharge. The evaluation was carried out by using a diffusion atmospheric model, 500 to 7000 m away from the discharge point and using 8 different wind direction sectors. The critical group was identified as being the people who lives 3000 m far from the discharge point, in the diffusion sector NW. The dose evaluated at this point is 10 9 times lower than the annual dose limit for individual of the public, according to Radiological Protection Standards. The derived limit for discharge of iodine was also evaluated and it was concluded that the IPEN-CNEN/SP can increase their production up to a level which results in an annual discharge of 1,5 x 10 12 of I-131. (author) [pt

Effluent release limits, sources and control

International Nuclear Information System (INIS)

Swindell, G.E.

1977-01-01

Objectives of radiation protection in relation to releases. Environmental transfer models for radionuclides. Relationship between releases, environmental levels and doses to persons. Establishment of release limits: Limits based on critical population group concept critical pathway analysis and identification of critical group. Limits based on optimization of radiation protection individual dose limits, collective doses and dose commitments 1) differential cost benefit analysis 2) authorized and operational limits taking account of future exposures. Monitoring of releases to the environment: Objectives of effluent monitoring. Typical sources and composition of effluents; design and operation of monitoring programmes; recording and reporting of monitoring results; complementary environmental monitoring. (orig.) [de

Publication of ICRP 60 and 61

Energy Technology Data Exchange (ETDEWEB)

Goldfinch, E P

1990-01-01

After considerable deliberation and consultation, the International Commission on Radiological Protection (ICRP) has published its 1990 recommendations and resultant annual limits on intakes for workers. The effects of these new recommendations will be considered by the International Atomic Energy Agency (IAEA) in relation to its transport regulations and supporting documents during the current revision process. This revision process should lead to the publication of revised regulations in 1996. Initially, the immediate reaction in some areas is that the revised dose limits and annual limits should automatically result in straightforward reductions in the A{sub 1} and A{sub 2} values in the regulations, and in reduction in the permitted radiation levels on and around packages, conveyances etc. However, this reaction is questioned for the reason that it is necessary to separately examine the radiological consequences in routine transport and in accidents (''normal conditions of transport'' and ''accident conditions'' in the terminology of the regulations). Because accidents to radioactive material packaging are rare, the potential harm to individuals is not likely to be repeated. Thus a lowering of the dose limit may not be necessary. (author).

Low doses of prophylactic cranial irradiation effective in limited stage small cell carcinoma of the lung

International Nuclear Information System (INIS)

Rubenstein, James H.; Dosoretz, Daniel E.; Katin, Michael J.; Blitzer, Peter H.; Salenius, Sharon A.; Floody, Patrick A.; Harwin, William N.; Teufel, Thomas E.; Raymond, Michael G.; Reeves, James A.; Hart, Lowell L.; McCleod, Michael J.; Pizarro, Alejandro; Gabarda, Antonio L.; Rana, Van G.

1995-01-01

Purpose: Prophylactic cranial irradiation (PCI) for the prevention of brain metastasis in small cell lung cancer remains controversial, both in terms of efficacy and the optimal dose-fractionation scheme. We performed this study to evaluate the efficacy of PCI at low doses. Methods and Materials: One hundred and ninety-seven patients were referred to our institution for treatment of limited stage small cell carcinoma of the lung between June 1986 and December 1992. Follow-up ranged from 1.1 to 89.8 months, with a mean of 19 months. Eighty-five patients received PCI. Results: Patients receiving PCI exhibited brain failure in 15%, while 38% of untreated patients developed metastases. This degree of prophylaxis was achieved with a median total dose of 25.20 Gy and a median fraction size of 1.80 Gy. At these doses, acute and late complications were minimal. Patients receiving PCI had significantly better 1-year and 2-year overall survivals (68% and 46% vs. 33% and 13%). However, patients with a complete response (CR) to chemotherapy and better Karnofsky performance status (KPS) were overrepresented in the PCI group. In an attempt to compare similar patients in both groups (PCI vs. no PCI), only patients with KPS ≥ 80, CR or near-CR to chemotherapy, and treatment with attempt to cure, were compared. In this good prognostic group, survival was still better in the PCI group (p = 0.0018). Conclusion: In this patient population, relatively low doses of PCI have accomplished a significant reduction in the incidence of brain metastasis with little toxicity. Whether such treatment truly improves survival awaits the results of additional prospective randomized trials

Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry

International Nuclear Information System (INIS)

Smith, K.P.; Blunt, D.L.; Williams, G.P.

1996-09-01

A preliminary radiological dose assessment of equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials (NORM) in production waste streams. The assessment estimated maximum individual dose equivalents for workers and the general public. Sensitivity analyses of certain input parameters also were conducted. On the basis of this assessment, it is concluded that (1) regulations requiring workers to wear respiratory protection during equipment cleaning operations are likely to result in lower worker doses, (2) underground injection and downhole encapsulation of NORM wastes present a negligible risk to the general public, and (3) potential doses to workers and the general public related to smelting NORM-contaminated equipment can be controlled by limiting the contamination level of the initial feed. It is recommended that (1) NORM wastes be further characterized to improve studies of potential radiological doses; (2) states be encouraged to permit subsurface disposal of NORM more readily, provided further assessments support this study; results; (3) further assessment of landspreading NORM wastes be conducted; and (4) the political, economic, sociological, and nonradiological issues related to smelting NORM-contaminated equipment be studied to fully examine the feasibility of this disposal option

Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

Directory of Open Access Journals (Sweden)

M. V. Vedernikova

2017-01-01

Full Text Available This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia. The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use

Potential radiation doses from 1994 Hanford Operations

Energy Technology Data Exchange (ETDEWEB)

Soldat, J.K.; Antonio, E.J.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the potential radiation doses to the public from releases originating at the Hanford Site. Members of the public are potentially exposed to low-levels of radiation from these effluents through a variety of pathways. The potential radiation doses to the public were calculated for the hypothetical MEI and for the general public residing within 80 km (50 mi) of the Hanford Site.

Potential radiation doses from 1994 Hanford Operations

International Nuclear Information System (INIS)

Soldat, J.K.; Antonio, E.J.

1995-01-01

This section of the 1994 Hanford Site Environmental Report summarizes the potential radiation doses to the public from releases originating at the Hanford Site. Members of the public are potentially exposed to low-levels of radiation from these effluents through a variety of pathways. The potential radiation doses to the public were calculated for the hypothetical MEI and for the general public residing within 80 km (50 mi) of the Hanford Site

Grand Junction Projects Office Remedial Action Project Building 2 public dose evaluation. Final report

International Nuclear Information System (INIS)

Morris, R.

1996-05-01

Building 2 on the U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) site, which is operated by Rust Geotech, is part of the GJPO Remedial Action Program. This report describes measurements and modeling efforts to evaluate the radiation dose to members of the public who might someday occupy or tear down Building 2. The assessment of future doses to those occupying or demolishing Building 2 is based on assumptions about future uses of the building, measured data when available, and predictive modeling when necessary. Future use of the building is likely to be as an office facility. The DOE sponsored program, RESRAD-BUILD, Version. 1.5 was chosen for the modeling tool. Releasing the building for unrestricted use instead of demolishing it now could save a substantial amount of money compared with the baseline cost estimate because the site telecommunications system, housed in Building 2, would not be disabled and replaced. The information developed in this analysis may be used as part of an as low as reasonably achievable (ALARA) cost/benefit determination regarding disposition of Building 2

Radiation dose to workers due to the inhalation of dust during granite fabrication

International Nuclear Information System (INIS)

Zwack, L M; Stewart, J H; McCarthy, J F; Allen, J G; McCarthy, W B

2014-01-01

There has been very little research conducted to determine internal radiation doses resulting from worker exposure to ionising radiation in granite fabrication shops. To address this issue, we estimated the effective radiation dose of granite workers in US fabrication shops who were exposed to the maximum respirable dust and silica concentrations allowed under current US regulations, and also to concentrations reported in the literature. Radiation doses were calculated using standard methods developed by the International Commission on Radiological Protection. The calculated internal doses were very low, and below both US occupational standards (50 mSv yr −1 ) and limits applicable to the general public (1 mSv yr −1 ). Workers exposed to respirable granite dust concentrations at the US Occupational Safety and Health Administration (OSHA) respirable dust permissible exposure limit (PEL) of 5 mg m −3 over a full year had an estimated radiation dose of 0.062 mSv yr −1 . Workers exposed to respirable granite dust concentrations at the OSHA silica PEL and at the American Conference of Governmental Industrial Hygienists Threshold Limit Value for a full year had expected radiation doses of 0.007 mSv yr −1 and 0.002 mSv yr −1 , respectively. Using data from studies of respirable granite dust and silica concentrations measured in granite fabrication shops, we calculated median expected radiation doses that ranged from <0.001 to 0.101 mSv yr −1 . (paper)

The analysis of annual dose distributions for radiation workers

International Nuclear Information System (INIS)

Mill, A.J.

1984-05-01

The system of dose limitation recommended by the ICRP includes the requirement that no worker shall exceed the current dose limit of 50mSv/a. Continuous exposure at this limit corresponds to an annual death rate comparable with 'high risk' industries if all workers are continuously exposed at the dose limit. In practice, there is a distribution of doses with an arithmetic mean lower than the dose limit. In its 1977 report UNSCEAR defined a reference dose distribution for the purposes of comparison. However, this two parameter distribution does not show the departure from log-normality normally observed for actual distributions at doses which are a significant proportion of the annual limit. In this report an alternative model is suggested, based on a three parameter log-normal distribution. The third parameter is an ''effective dose limit'' and such a model fits very well the departure from log-normality observed in actual dose distributions. (author)

Limitations on the compensation of gamete donors: a public opinion survey.

Science.gov (United States)

Lee, Malinda S; Farland, Leslie V; Missmer, Stacey A; Ginsburg, Elizabeth S

2017-06-01

To determine public opinion on gamete donor compensation. Cross-sectional web-based survey. Not applicable. A nationally representative sample of 1,427 people in the United States. Not applicable. Support for the compensation of gamete donors. Of 1,427 respondents, 51 (4%) disagreed with use of IVF for any indication, and 232 (16%) believed that oocyte and/or sperm donation to be always unacceptable. Of the remaining 1,185 respondents, 953 (80%) supported and 41 (4%) opposed paying sperm donors; 1,063 (90%) supported and 24 (2%) opposed paying oocyte donors. Of respondents, 90% believed that appropriate compensation for one cycle of oocyte donation should be less than $10,000. A total of 559 (47%) supported a limit on sperm donor compensation and 544 (46%) supported a limit on oocyte donor compensation. Individuals who had personal knowledge of someone with infertility or who used assisted reproductive technology (ART), and Republicans compared with Democrats, were more likely to support limits on both oocyte and sperm donor compensation. Divorced compared with married respondents were less likely to support limits on gamete donor compensation. Men were less likely to support limits on sperm donor compensation. Most respondents in a nationally representative cohort support compensating gamete donors. Although most do not support limits on gamete donor compensation, most agree the appropriate payment for one cycle of oocyte donation is in line with former American Society for Reproductive Medicine guidelines. Copyright © 2017 American Society for Reproductive Medicine. Published by Elsevier Inc. All rights reserved.

Measurement of doses to aviator pilots using thermoluminescent dosemeters; Medicion de la dosis a pilotos aviadores usando dosimetros termoluminiscentes

Energy Technology Data Exchange (ETDEWEB)

Azorin N, J.; Cruz C, D. [UAM-I, 09340 Mexico D.F. (Mexico); Rivera M, T. [IPN, ESIME Culhuacan (Mexico)]. e-mail: azorin@xanum.uam.mx

2004-07-01

During the development of their work, the aviator pilots are exposed at high levels of natural radiation of bottom caused mainly by the cosmic radiation of galactic origin and lot. For such reason, the Metropolitan Autonomous University (UAM) and the Union Association of Aviator Pilots (ASPA), subscribed an agreement with the purpose of to measure the doses of ionizing radiation received by the aviator pilots of diverse air companies that man different types of airships and to determine if these doses surpass the one limit of 0.11 mSv/h settled down by the IAEA for the public in general; and if therefore, these workers should be considered as personnel occupationally exposed. In this work the obtained results when measuring the absorbed dose received by Mexican civil aviator pilots during the development of their work, using thermoluminescent dosemeters of LiF:Mg,Cu,P + Ptfe of national production are presented. The obtained results during the years of 2001 and 2002 show that the monthly doses received by the pilots surpass the one it limits established for the public in general, for what they should be considered as personnel occupationally exposed. (Author)

Effective dose and dose to crystalline lens during angiographic procedures

International Nuclear Information System (INIS)

Pages, J.

1998-01-01

The highest radiation doses levels received by radiologists are observed during interventional procedures. Doses to forehead and neck received by a radiologist executing angiographic examinations at the department of radiology at the academic hospital (AZ-VUB) have been measured for a group of 34 examinations. The doses to crystalline lens and the effective doses for a period of one year have been estimated. For the crystalline lens the maximum dose approaches the ICRP limit, that indicates the necessity for the radiologist to use leaded glasses. (N.C.)

Proposal of dose constraint values to the patient in diagnostic radiology

International Nuclear Information System (INIS)

Arranz, L.; Sastre, J.M.; Ferrer, N.; Andres, J.C. De; Guibelalde, E.; Tobarra, B.; Madrid, G.

1996-01-01

A dose constraint is the value of an individual dose not to be exceeded in the individual dose distribution considered in an optimization process. The objective of a dose constraints is to set a ceiling to the doses to individual from a source, practice or task which are considered acceptable in the optimization process at the design stage. Implicitly, as C. Zuur states, dose constraints are below the relevant dose limit and usually should be established as local or national levels. Exposures for medical purposes are not subject to dose limits and hence dose constraints were recommended by the ICRP just for occupational and public exposures. However, as an effective tool for optimization for medical exposures, ICRP-60 in paragraph 180 recognizes the value of applying this concept to patient diagnostic radiology with some peculiarities: 'Considerations should be given to the use of dose constraints, or investigation levels, selected by the appropriate professional or regulatory agency, for application in some common diagnostic procedures. They should be applied with flexibility to allow higher cases where indicated by sound clinical judgement.' This paper analyzes retrospectively the dose levels imparted to patient in some common examinations (chest, lumbar spine and mammography) at different optimization stages of different facilities to propose some local constraints for diagnostic examinations. Dose values have been obtained under routine working conditions. Centres included in the survey have been chosen all over Spain, classifying them with particular attention to the following aspects: -Organizational aspects of the diagnostic radiology service, i.e., operational, technical and clinical criteria, as well as quality requirements. - Evaluation and revision of routine medical protocols. -Quality control of the radiological equipment. - Quality criteria for the surveillance of the weekly procedures, with requirements of proper training of die technical staff

Impact of ICRP publication 68

International Nuclear Information System (INIS)

Carter, M.W.; Woods, D.A.

1996-01-01

ICRP Publication 61 was a temporary replacement for ICRP Publication 30. It gave ALIs but not the underlying dose conversion factors. ICRP Publication 68 has now been issued to replace Publication 61; it contains the dose conversion factors but not the ALIs, so comparison is impossible without carrying out calculations. This paper presents comparisons between the two publications and calculates the ICRP Publication 68 ALIs for some of the more common radionuclides. (author)

Committed effective dose determination in cereal flours by gamma-ray spectrometry

International Nuclear Information System (INIS)

Scheibel, Viviane

2006-01-01

The health impact from radionuclides ingestion of foodstuffs was evaluated by the committed effective doses determined in commercial samples of South-Brazilian cereal flours (soy, wheat, corn, manioc, rye, oat, barley and rice flour). The radioactivity traces of 228 Th, 228 Ra, 226 Ra, 40 K, 7 Be and 137 Cs were measured by gamma-ray spectrometry employing a 66% relative efficiency HPGe detector. The energy resolution for the 1332.46 keV line of 60 Co was 2.03 keV. The committed effective doses were calculated with the activities analyzed in the present flour samples, the foodstuff rates of consumption (Brazilian Institute of Geography and Statistics) and the ingestion dose coefficients (International Commission of Radiological Protection). The reliability median activities were verified with χ 2 tests, assuring the fittings quality. The highest concentration levels of 228 Th and 40 K were 3.5 ± 0.4 and 1469 ± 17 Bq.kg -1 for soy flour, respectively, with 95% of confidence level. The lower limit of detection for 137 Cs ranged from 0.04 to 0.4 Bq.kg -1 . The highest committed effective dose was 0.36 μSv.y -1 for 228 Ra in manioc flour (adults). All committed effective doses determined at the present work were lower than the UNSCEAR limits of 140 μSv.y -1 and much lower than the ICRP (1991) limits of 1 mSv.y -1 , for general public. There are few literature references for natural and artificial radionuclides in foodstuffs and mainly for committed effective doses. This work brings the barley flour data, which is not present at the literature and 7 Be data which is not encountered in foodstuffs at the literature, besides all the other flours data information about activities and committed effective doses. (author)

Some aspects of the fetal doses given in ICRP Publication 88

International Nuclear Information System (INIS)

Phipps, A.W.; Harrison, J.D.; Fell, T.P.; Eckerman, K.F.; Nosske, D.

2003-01-01

The International Commission on Radiological Protection (ICRP) has recently published dose coefficients (dose per unit intake, Sv Bq -1 ) for the offspring of women exposed to radionuclides during or before pregnancy. These dose estimates include in utero doses to the embryo and fetus and doses delivered postnatally to the newborn child from radionuclides retained at birth. This paper considers the effect on doses of the time of radionuclide intake and examines the proportion of dose delivered in utero and postnatally for different radionuclides. Methods used to calculate doses to the fetal skeleton are compared. For many radionuclides, doses are greatest for intakes early in pregnancy but important exceptions for which doses are greatest for intakes later in pregnancy, are iodine isotopes and isotopes of the alkaline earth elements, including strontium. While radionuclides such as 131 I deliver dose largely in utero even for intakes late in pregnancy, others such as 239 Pu deliver dose largely postnatally, even for intakes early during pregnancy. For alpha emitters deposited in the skeleton, the assumption made is of uniform distribution of the radionuclide and of target cells for leukaemia and bone cancer in utero; that is, the developing bone structure is not considered. However, for beta emitters, the bone structure was considered. Both approaches can be regarded as reasonably conservative, given uncertainties in particular in the location of the target cells and the rapid growth and remodelling of the skeleton at this stage of development. (author)

Radiation protection to the family and the members of the public following administration of a radiopharmaceutical to a patient

International Nuclear Information System (INIS)

Gardin, I.; Chomant, J.; Vera, P.

2001-01-01

This paper reviews the published data relating to radiation hazards to the family and close friends or the members of the public, associated with nuclear medicine patients. The new annual dose limit of 1 mSv proposed by the ICRP for members of the public and the concept of dose constraints should modify the French legislation and the radioprotection guidance. Dose constraints are set prospectively and are not expected to be exceeded. They are no legal dose limits. They can be higher in the case of the family and close friends than the dose limit of 1 mSv. The European Commission proposes dose constraints values of 3 mSv for the family and close friends (adults) and 0.3 mSv for the members of the public, as the United Kingdom's recommendations are respectively 5 mSv and 1 mSv. For diagnostic studies, the quantities of radioactivity currently administered do not necessitate any special precautions or restrictions to be place on the patient. The main exception was found in the situation of an out patient given 111 In who had to look after a fretful infant with close contact time of 9 hours per day. For breast-feeding, comprehensive set of recommendations, including no interruption or interruption during only a few hours were proposed to ensure that the effective dose to the infant does not exceed 1 mSv. Nevertheless, as a precaution, breast-feeding interruption should be recommended, whatever the radiopharmaceutical, or if possible, to defer the medical exploration. The main radiation protection problem occurs for therapeutic treatment with gamma ray emitters such as 131 I for the treatment of thyroid pathology. There is a range of published recommendations for limiting the exposure of close friends and the members of the public. These advises include private and public transports, return to work, sleeping with partner and close contact with children. The recommendations proposed by the European Commission for the members of the public are quite restrictive if

On determination of limit of effective dose for living bodies concerning control areas of nuclear law material mines

International Nuclear Information System (INIS)

1977-01-01

The Notification is based on the prescriptions of the Safety Regulation of Metal Mines. The permissible levels of effective dose for living bodies and others concerning control areas are defined as follows: the effective dose of external radiation for living bodies should be less than 30 millirems in a consecutive week; the concentrations of radioactive substances in the air or in the water possibly drunk by men are specified respectively for Rn 220, Rn 222, Th and U; the densities of such substances on the surfaces of things contaminated by such elements in refineries should be less than 10 micro-micro-curies per centi-meter 2 , etc. Such permissible levels in residential quarters are defined as follows: the effective dose of external radiation for living bodies should be less than 10 millirems in a consecutive week; the concentrations of radioactive substances in the air or in the water possibly drunk by men are specified respectively for Rn 220, Rn 222, Th and U, etc. The permissible exposure dose for miners working regularly in control areas should be less than 3 rems in three consecutive months. The permissible limit of accumulated dose should be less than the figure, in the unit of rem, which is obtained by multiplying the figure of age of the miner concerned minus 18 by 5. (Okada, K.)

Radiation dose rates from adult patients receiving 131I therapy for thyrotoxicosis

International Nuclear Information System (INIS)

O'Doherty, M.J.; Kettle, A.G.; Eustance, C.N.P.; Mountford, P.J.; Coakley, A.J.

1993-01-01

Recommendations for restricting the exposure to radiation of members of the public coming into contact with thyrotoxic patients treated with 131 I are currently based on the activity retained by the patient, and not on the doses likely to be received by such individuals. In order to examine whether these current recommendations restrict these doses to less than the current annual limit of 5 mSv, and to identify the implications of a reduction in this limit to 1 mSv, measurements were made of the dose rates at distances of 0.1, 0.5 and 1.0 m from 60 patients just before they left the nuclear medicine department. These measurements were repeated 1, 3, 6, 8 and 10 days after administration for 30 patients, and the radioactivity in samples of saliva taken on each of these days and secreted in sweat over the first 24 h were also measured. Doses were estimated for administered activities of approximately 200-600 MBq, assuming appropriate values for the times and distances spent near other individuals while travelling, at work, at home and near to young children considered in three age groups. Periods of restriction were derived which would reduce these doses to 5 or 1 mSv. (Author)

Derived limits for occupational exposure to uranium mine and mill dusts in the air and on surfaces

International Nuclear Information System (INIS)

Carter, M.W.

1983-01-01

Limits are derived for the concentration of uranium mine and mill dusts in the air based on ICRP30 and assumptions regarding the isotopic make up of the dusts. From these limits using a resuspension factor, limits for surface contamination are derived. Calculations are presented of the dose to the basal layer of the skin from mine and mill dusts on the skin. From these calculations limits for skin contamination are derived. A calculation of a limit based on direct ingestion is also presented. Exposure limits for the public are not considered

Analysis of the external doses received by workers involved in the mitigation of the Goiania radiological accident

Energy Technology Data Exchange (ETDEWEB)

Mauricio, C.L.P., E-mail: claudia@ird.gov.br [Instituto de Radioproteção e Dosimetria, Rio de Janeiro, RJ (Brazil). Div. de Dosimetria

2017-07-01

In 1987, after identification that a stolen head of a Cs-137 radiotherapy irradiator was violated, it starts, in Goiania, the screening of the involved persons, the decontamination and the collection of the radiative waste. The contaminated areas were isolated and the professionals who worked within these areas received individual film monitors and TLD rings, provided by the Instituto de Radioproteção e Dosimetria (IRD), to evaluate their external dose. The aim of this paper is to present a statistical analysis of the external occupational doses received by this intervention staff. The used data were extracted from the Goiania accident database, maintained by IRD. A total of 1091 workers were monitored, some for only a few days and others for almost one year. All the total external occupational doses, received during these works, including the management of the radiative waste, were lower than the individual annual dose limit of 50 mSv for practices. Only one dose exceeded the value of 20 mSv. Their estimated mean effective doses were about 1.0 mSv, which is the annual dose limit for public exposure. About 80% of the doses were lower than this value. (author)

Dealing with initial chemotherapy doses: a new basis for treatment optimization in limited small-cell lung cancer

International Nuclear Information System (INIS)

Le Chevalier, T.; Le Cesne, A.; Arriagada, R.

1995-01-01

Treatment of patients with small-cell lung cancer (SCLC) remains disappointing despite high initial complete response rates. The dramatic initial chemosensitivity of tumor cells is frustrated by the early emergence of chemoresistant clonogenic cells, regardless of front line treatments. Although the dose relationship is fairly well established regarding the response rate, its effect on survival is inconclusive. From 1980 to 1988, 202 patients with limited SCLC were included in four consecutive protocols using an alternating schedule of thoracic radiotherapy and chemotherapy. Despite an increase of chemotherapy and/or total radiation doses, no significant difference was observed between the four protocols in terms of response rate, disease free and overall survival. However, a retrospective analysis performed on a total of 131 consecutive patients led us to propose the hypothesis that a moderate increase in the initial dose, ie first course, of cisplatin and cyclophosphamide could improve overall survival. From 1988 to 1991, 105 patients were subsequently included in a large randomized trial raising this question. The treatment difference only concerned the initial doses of cisplatin (80 vs 100 mg/m 2 ) and cyclophosphamide (900 vs 1200 mg/m 2 ). The trial was closed after inclusion of 105 patients, 32 months after the start of the study because at that time overall survival was significantly better in the higher-dose group (p = 0.001). The emergence of this debatable concept opens new directions in the therapeutic strategy of SCLC and the contribution of hematopoietic growth factors may be a great interest in the management of this disease. (authors). 27 refs., 1 tab

Estimated neutron dose to embryo and foetus during commercial flight

International Nuclear Information System (INIS)

Chen, J.; Lewis, B. J.; Bennett, L. G. I.; Green, A. R.; Tracy, B. L.

2005-01-01

A study has been carried out to assess the radiation exposure from cosmic-ray neutrons to the embryo and foetus of pregnant aircrew and air travellers in consideration of the radiation exposure from cosmic-ray neutrons to the embryo and foetus. A Monte Carlo analysis was performed to determine the equivalent dose from neutrons to the brain and body of an embryo at 8 weeks and to the foetus at the 3, 6 and 9 month periods. Neutron fluence-to-absorbed dose conversion coefficients for the foetal brain and for the entire foetal body (isotropic irradiation geometry) have been determined at the four developmental stages. The equivalent dose rate to the foetus during commercial flights has been further evaluated considering the fluence-to-absorbed dose conversion coefficients, a neutron spectrum measured at an altitude of 11.3 km and an ICRP-92 radiation-weighting factor for neutrons. This study indicates that the foetus can exceed the annual dose limit of 1 mSv for the general public after, for example, 15 round trips on commercial trans-Atlantic flights. (authors)

Normal tissue dose-effect models in biological dose optimisation

International Nuclear Information System (INIS)

Alber, M.

2008-01-01

Sophisticated radiotherapy techniques like intensity modulated radiotherapy with photons and protons rely on numerical dose optimisation. The evaluation of normal tissue dose distributions that deviate significantly from the common clinical routine and also the mathematical expression of desirable properties of a dose distribution is difficult. In essence, a dose evaluation model for normal tissues has to express the tissue specific volume effect. A formalism of local dose effect measures is presented, which can be applied to serial and parallel responding tissues as well as target volumes and physical dose penalties. These models allow a transparent description of the volume effect and an efficient control over the optimum dose distribution. They can be linked to normal tissue complication probability models and the equivalent uniform dose concept. In clinical applications, they provide a means to standardize normal tissue doses in the face of inevitable anatomical differences between patients and a vastly increased freedom to shape the dose, without being overly limiting like sets of dose-volume constraints. (orig.)

Understanding the Limitations to the Right to Strike in Essential and Public Services in the SADC Region

Directory of Open Access Journals (Sweden)

Rochelle le Roux

2016-05-01

Full Text Available The nature of the limitations to the right to strike in essential and public services in the nine sub-regional countries of Southern Africa – South Africa, Botswana, Lesotho, Namibia, Swaziland, Malawi, Mozambique, Zambia and Zimbabwe – is examined in this contribution. While all of these countries share common influences and face common challenges, there appears to be a vast disparity in the approaches taken to the right to strike in public and essential services in the region. A brief overview of the demographics and labour markets in the countries under discussion is sketched, the salient features of the ILO's approach to strike in essential and public services is highlighted, and a broad overview of the contrasting and disparate approaches to essential and public services in the region is provided. The focus is, however, on the legislative approach taken to essential service employees in South Africa. It is concluded that – with the exception of South Africa and Namibia – the limitations to the right to strike of public sector employees exceed those endorsed by international conventions, and the broad definition of essential services generally relied upon effectively

Open and fast available dose rate data for the public. Challenges and opportunities of internet based communication

International Nuclear Information System (INIS)

Zaehringer, M.; Luff, R.; Schiesewitz, M.

2014-01-01

The BfS website ''ODLInfo'' had been operational for many years when it suddenly became frequently visited by the public due to the Fukushima accident. BfS responded with increased polling frequency of the gamma probes in the network and a higher frequency in update of the web site. Not yet validated data were also published. The web site was extended by explanatory text and additional functionalities, including a complete translation into english language. Many questions directed to BfS by E-mail and related to this web site had to be answered. This was used as a valuable feedback for improving the its design. Additional services were implemented for providers of special applications of smartphones. The market is characterized by a great variability between serious and lurid apps. BfS seeks to support providers in giving explanatory help. Similar websites exist on European and international level. The EU is publishing data from member states on the EURDEP site. NGOs established platforms for uploading and visualizing private dose rate measurements in Japan after 11 march 2011. This development has important implication for emergency preparedness. Information platforms must be authentic and timely. They must compete with alternative data sources in contents and presentation. Data must be presented understandable. Ideally, the public can understand the data and set it into relation to reference values. Often people want to compare their own measurements - sometimes collected with low quality equipment - with official data. Radiation issues are much better understood by the lay public if visible effects in the variability of the measured dose rate are explained.

Dose estimates to the public from 210Po ingestion via dietary sources at Kalpakkam (India)

International Nuclear Information System (INIS)

Kannan, V.; Iyengar, M.A.R.; Ramesh, R.

2001-01-01

Distribution of one of the natural radionuclides 210 Po activity in food of plant origin such as cereals, pulses, vegetables and food of animal origin such fish, crab, prawn, chicken, egg etc. were determined in and around Kalpakkam up to a distance of 32 km radius. The general range of 210 Po activity levels in all the dietary components (excluding milk and drinking water which are reported in mBq l -1 ) ranged widely from ≤10 to 122,641 mBq kg -1 fresh, the minimum being in vegetables and maximum being in the edible portions (muscle) of crab samples. 210 Po levels in drinking water and milk samples ranged between 0.6-2.6 and 8-12 mBq l -1 respectively. 210 Po content in cereals ranged from ≤32 to 745 mBq kg -1 and in pulses it was found to vary between ≤32 and 294 mBq kg -1 . The range of 210 Po activity in different types of vegetables was found to be ≤10-653 mBq kg -1 . Among the different varieties of vegetables, 210 Po was significantly higher in leafy vegetables (28-653 mBq kg -1 ) as compared to rooty and other types of vegetables which ranged from ≤10-180 mBq kg -1 . In food of animal origin, the observed minimum activity of 210 Po was 8 mBq l -1 in milk and the maximum observed was 122,641 mBq kg -1 in the muscles of crab. It was also observed that 210 Po activity was found to be in higher levels in the food of aquatic animal origin (1414-122,641 mBq kg -1 ) than in the food of terrestrial animal origin (other than milk) which varied from 41 to 963 mBq kg -1 . It is evident from the present study that the foods of animal origin especially crab, fish and prawn deliver significantly greater dose (93-3364 μSv yr -1 ) to the public compared to foods of plant origin whose mean dose ranged 0.08-128 μSv yr -1 . The study showed evidence to suggest that the total ingestion dose due to 210 Po received by the Kalpakkam public through dietary sources is significantly higher than the ingestion dose received due to fallout sources such as 137 Cs and 90 Sr

Procedures, activities and doses in nuclear medicine cycle in Brazil; Procedimentos, atividades e doses no ciclo da medicina nuclear no Brasil

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Silvia Maria Velasques de

2005-07-01

With the aim of characterizing nuclear medicine procedures performed in Brazil, activities of radiopharmaceuticals used and effective doses to patients, data was collected from nuclear medicine institutions in three regions of the country, namely the Southeast, the Northeast and the South regions, representing public hospitals, university hospitals, private and philanthropic institutions with low, medium and high levels of consumption of radiopharmaceuticals. The three chosen regions are responsible for 92% of radiopharmaceutical consumption and imaging equipment in the country. Accordingly, it was requested of some participating institutions to fulfill manually from individual patients data, to record gender, age, weight, height and activities used, for each type of exam as well as the equipment used. In others, the researcher collected data personally. Per institution, nuclear medicine diagnostic procedures ranged from 700 to 13,000 per year, most of which are myocardial and bone imaging procedures, and imaging equipment ranged, from 1 to 8 machines, one or two head SPECT's (hybrid or not). 26.782 patients protocols were analysed, 24.371 adults and 2.411 children and teenagers. For adult patients, differences were observed in the amount of activities used in diagnostic procedures between public and private institutions, with lower average activities used in public institutions. Activities administered to children and their effective doses were difficult to evaluate due to the incompleteness of individual records. Appropriate individual patient records could be adopted without affecting hospitals routine and contributing for a comprehensive evaluation of the radiation protection of nuclear medicine patients. Data from 8.881 workers were analysed, 346 working at nuclear medicine institutions. For monitored workers and measurably exposed workers in nuclear medicine, the values 2.3 mSv and 5.4 mSv, respectively, for effective annual doses are greater than data

Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11

International Nuclear Information System (INIS)

Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

1988-09-01

Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs

Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11

Energy Technology Data Exchange (ETDEWEB)

Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

1988-09-01

Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs.

Effective dose evaluation of NORM-added consumer products using Monte Carlo simulations and the ICRP computational human phantoms.

Science.gov (United States)

Lee, Hyun Cheol; Yoo, Do Hyeon; Testa, Mauro; Shin, Wook-Geun; Choi, Hyun Joon; Ha, Wi-Ho; Yoo, Jaeryong; Yoon, Seokwon; Min, Chul Hee

2016-04-01

The aim of this study is to evaluate the potential hazard of naturally occurring radioactive material (NORM) added consumer products. Using the Monte Carlo method, the radioactive products were simulated with ICRP reference phantom and the organ doses were calculated with the usage scenario. Finally, the annual effective doses were evaluated as lower than the public dose limit of 1mSv y(-1) for 44 products. It was demonstrated that NORM-added consumer products could be quantitatively assessed for the safety regulation. Copyright © 2016 Elsevier Ltd. All rights reserved.

Doses to road transport workers from radioactive materials

International Nuclear Information System (INIS)

Lawrence, B.E.; van der Vooren, A.

1988-12-01

Each year approximately 750,000 packages of radioactive materials are shipped throughout Canada. Regulatory controls on these shipments are designed to keep radiation doses received by transport workers well within acceptable limits. Since many of these workers are not monitored for radiation exposure, however, little factual information has been available in Canada to support theoretical estimates. A study to document actual radiation doses received by a select group of transport workers that is actively involved in the shipment of radioactive materials, was carried out in 1987 and 1988. This study involved the monitoring of 31 candidates from nine transport companies from across the country that handle medical isotopes, industrial isotopes, uranium fuel cycle materials and associated radioactive wastes. Each of the candidates (consisting of driver, dock workers, sorters, and supervisors) was issued personal thermoluminescent dosimeter (TLD) badges that were worn each day during the six month monitoring period. Some of the candidates were also issued cab or area dosimeters that were left in the cabs of the vehicles or in work areas so that the dose received in these areas could be differentiated from total personal exposure. During the monitoring program, the candidates filled out reporting sheets at the end of each working day to document information such as the quantity of materials handled, handling times and vehicle size. This information and the dosimetry data were used in the development of correlations between materials handled and doses reported so that doses for other handling similar materials could be estimated. Based on the results of the study, it was learned that while most of the transport workers receive doses that are at or near background levels, other (particularly those handling medical isotopes) are exposed to levels of radiation that may result in their receiving doses above the 5 mSv per annum limit set for members of the general public. On

Precedents For Authorization Of Contents Using Dose Rate Measurements

International Nuclear Information System (INIS)

Abramczyk, G.; Bellamy, S.; Nathan, S.; Loftin, B.

2012-01-01

For the transportation of Radioactive Material (RAM) packages, the requirements for the maximum allowed dose rate at the package surface and in its vicinity are given in Title 10 of the Code of Federal Regulations, Section 71.47. The regulations are based on the acceptable dose rates to which the public, workers, and the environment may be exposed. As such, the regulations specify dose rates, rather than quantity of radioactive isotopes and require monitoring to confirm the requirements are met. 10CFR71.47 requires that each package of radioactive materials offered for transportation must be designed and prepared for shipment so that under conditions normally incident to transportation the radiation level does not exceed 2 mSv/h (200 mrem/h) at any point on the external Surface of the package, and the transport index does not exceed 10. Before shipment, the dose rate of the package is determined by measurement, ensuring that it conforms to the regulatory limits, regardless of any analyses. This is the requirement for all certified packagings. This paper discusses the requirements for establishing the dose rates when shipping RAM packages and the precedents for meeting these requirements by measurement.

Radiological protection in medicine. ICRP Publication 105

International Nuclear Information System (INIS)

2011-01-01

This report was prepared to underpin the Commission's 2007 Recommendations with regard to the medical exposure of patients, including their comforters and carers, and volunteers in biomedical research. It addresses the proper application of the fundamental principles (justification, optimisation of protection, and application of dose limits) of the Commission's 2007 Recommendations to these individuals. With regard to medical exposure of patients, it is not appropriate to apply dose limits or dose constraints, because such limits would often do more harm than good. Often, there are concurrent chronic, severe, or even life-threatening medical conditions that are more critical than the radiation exposure. The emphasis is then on justification of the medical procedures and on the optimisation of radiological protection. In diagnostic and interventional procedures, justification of procedures (for a defined purpose and for an individual patient), and management of the patient dose commensurate with the medical task, are the appropriate mechanisms to avoid unnecessary or unproductive radiation exposure. Equipment features that facilitate patient dose management, and diagnostic reference levels derived at the appropriate national, regional, or local level, are likely to be the most effective approaches. In radiation therapy, the avoidance of accidents is a predominant issue. With regard to comforters and carers, and volunteers in biomedical research, dose constraints are appropriate. Over the last decade, the Commission has published a number of documents that provided detailed advice related to radiological protection and safety in the medical applications of ionising radiation. Each of the publications addressed a specific topic defined by the type of radiation source and the medical discipline in which the source is applied, and was written with the intent of communicating directly with the relevant medical practitioners and supporting medical staff. This report

ICRP Publication 105. Radiological Protection in Medicine

International Nuclear Information System (INIS)

Aubert, Bernard; Biau, Alain; Derreumaux, Sylvie; Etard, Cecile; Rannou, Alain; Rehel, Jean-Luc; Roch, Patrice Elle a ete validee par le Professeur Jean-Marc Cosset

2011-01-01

This report was prepared to underpin the Commission's 2007 Recommendations with regard to the medical exposure of patients, including their comforters and carers, and volunteers in biomedical research. It addresses the proper application of the fundamental principles (justification, optimisation of protection, and application of dose limits) of the Commission's 2007 Recommendations to these individuals. With regard to medical exposure of patients, it is not appropriate to apply dose limits or dose constraints, because such limits would often do more harm than good. Often, there are concurrent chronic, severe, or even life-threatening medical conditions that are more critical than the radiation exposure. The emphasis is then on justification of the medical procedures and on the optimisation of radiological protection. In diagnostic and interventional procedures, justification of procedures (for a defined purpose and for an individual patient), and management of the patient dose commensurate with the medical task, are the appropriate mechanisms to avoid unnecessary or unproductive radiation exposure. Equipment features that facilitate patient dose management, and diagnostic reference levels derived at the appropriate national, regional, or local level, are likely to be the most effective approaches. In radiation therapy, the avoidance of accidents is a predominant issue. With regard to comforters and carers, and volunteers in biomedical research, dose constraints are appropriate. Over the last decade, the Commission has published a number of documents that provided detailed advice related to radiological protection and safety in the medical applications of ionising radiation. Each of the publications addressed a specific topic defined by the type of radiation source and the medical discipline in which the source is applied, and was written with the intent of communicating directly with the relevant medical practitioners and supporting medical staff. This

Proposed derivation of skin contamination and skin decontamination limits

International Nuclear Information System (INIS)

Schieferdecker, H.; Koelzer, W.; Henrichs, K.

1986-01-01

From the primary dose limits for the skin, secondary dose limits were derived for skin contamination which can be used in practical radiation protection work. Analogous to the secondary dose limit for the maximum permissible body burden in the case of incorporation, dose limits for the 'maximum permissible skin burden' were calculated, with the help of dose factors, for application in the case of skin contamination. They can be derived from the skin dose limit values. For conditions in which the skin is exposed to temporary contamination, a limit of skin contamination was derived for immediately removable contamination and for one day of exposure. For non-removable contamination a dose limit of annual skin contamination was defined, taking into account the renewal of the skin. An investigation level for skin contamination was assumed, as a threshold, above which certain measures must be taken; these to include appropriate washing not more than three times, with the subsequent procedure determined by the level of residual contamination. The dose limits are indicated for selected radionuclides. (author)

Exposure to Non-Ionizing Radiation and Public Health: Basic Concepts and Safety Limits

International Nuclear Information System (INIS)

Ubeda-Maeso, A.; Vargas-Marcos, F.; Trillo-Ruiz, M.A.

2003-01-01

The potential health effects of exposure to non-ionizing electromagnetic radiation in public and residential environments are a source of increasing concern for both the public and authorities on environmental health. This work briefly summarizes the theoretical and experimental bases supporting the safety levels proposed by international committees. It also reviews the recent scientific literature on bioeffects on non-ionizing radiation that may prove potentially relevant to the validation or modification of present exposure limits. Because of their social interest, special consideration will be given to power frequency fields (50-60 Hz) and to the radio communication signals of mobile phones. We will also describe how interpretations of scientific evidence from sources other than international committees have generated some controversy and provided basis for more restrictive limits, such as those adopted in Europe by Switzerland and Italy. In addition, this work identifies some gaps in the present scientific knowledge of bioelectromagnetics. Such gaps are largely responsible for the existing controversy and differences in risk perception. This is why more research aimed at broadening and deepening our understanding of biological responses to non-ionizing radiation is urgently needed. (author)

Radiation dose rates from adult patients undergoing nuclear medicine investigations

International Nuclear Information System (INIS)

Mountford, P.J.; O'Doherty, M.J.; Forge, N.I.; Jeffries, A.; Coakley, A.J.

1991-01-01

Adult patients undergoing nuclear medicine investigations may subsequently come into close contact with members of the public and hospital staff. In order to expand the available dosimetry and derive appropriate recommendations, dose rates were measured at 0.1, 0.5 and 1.0 m from 80 adult patients just before they left the nuclear medicine department after undergoing one of eight 99 Tc m studies, an 123 I thyroid, an 111 In leucocyte or a 201 Tl cardiac scan. The maximum departure dose rates at these distances of 150, 30 and 7.3 μSv h -1 were greater than those found in similar published studies of adult and paediatric patients. To limit the dose to an infant to less than 1 mSv, an 111 In leucocyte scan is the only investigation for which it may be necessary to restrict close contact between the infant and a radioactive parent, depending on the dose rate near the surface of the patient, the parent's habits and how fretful is the infant. It is unlikely that a ward nurse will receive a dose of 60 μSv in a working day if caring for just one radioactive adult patient, unless the patient is classified as totally helpless and had undergone a 99 Tc m marrow, bone or brain scan. The data and revised calculations of effective exposure times based on a total close contact time of 9 h in every 24 h period should allow worst case estimates of radiation dose to be made and recommendations to be formulated for other circumstances, including any future legislative changes in dose limits or derived levels. (author)

Report of questionnaire concerning the conditions and exposure doses at thoracoabdominal radiography and CT

International Nuclear Information System (INIS)

2009-01-01

Japan Association of Radiological Technologists, at 2 years after its presentation of the Guideline for Medical Radiation Exposure (2006), made a questionnaire in the title on its homepage on Nov. 6-Dec. 5, 2008, and this paper is its report. The questionnaire asked the conditions and exposure doses at thoracoabdominal radiography and CT: in the former, asked were conditions like the machine/detector, tube voltage, filter, incident angle, entrance plane dose (EPD) (mGy) etc., and 237 facilities including 56 public hospitals and 15 universities answered. EPD calculated by numerical dose determination was found to be 0.22 and 0.76 mGy at the frontal and lateral thoracic projection, respectively, which were less than the upper limit defined in International Atomic Energy Agency (IAEA) guidance (0.4 and 1.5 mGy). However, doses in 6 and 2.6% of facilities at the respective projection exceeded the IAEA levels. EPD at the frontal abdominal projection calculated was 2.22 mGy, and all facilities met with the IAEA demand level (<10 mGy). In the CT questionnaire, conditions asked were the machine manufacturer/brand, scanning mode and range, tube voltage, rotation time, beam width and pitch, slice width, CTDIvol (CT Dose Index weighted/pitch) (mGy) and so on, which 212 facilities involving 58 public hospitals and 14 universities answered. CTDIvol was found to be 91.7 mGy at head CT which greatly exceeded the maximal levels of International Commission of Radiological Protection (ICRP), IAEA and the Association (60, 50 and 65 mGy, respectively). CTDIvol at thoracic CT was 15.2 mGy (no standard upper limit at present), and at abdominal CT, 20.0 mGy (the same as the Association level). The latter suggested the suitable dose setting at this CT. Thus the problem at head CT was much highlighted here. (K.T.)

Assessing the reliability of dose coefficients for exposure to radioiodine by members of the public, accounting for dosimetric and risk model uncertainties.

Science.gov (United States)

Puncher, M; Zhang, W; Harrison, J D; Wakeford, R

2017-06-26

Assessments of risk to a specific population group resulting from internal exposure to a particular radionuclide can be used to assess the reliability of the appropriate International Commission on Radiological Protection (ICRP) dose coefficients used as a radiation protection device for the specified exposure pathway. An estimate of the uncertainty on the associated risk is important for informing judgments on reliability; a derived uncertainty factor, UF, is an estimate of the 95% probable geometric difference between the best risk estimate and the nominal risk and is a useful tool for making this assessment. This paper describes the application of parameter uncertainty analysis to quantify uncertainties resulting from internal exposures to radioiodine by members of the public, specifically 1, 10 and 20-year old females from the population of England and Wales. Best estimates of thyroid cancer incidence risk (lifetime attributable risk) are calculated for ingestion or inhalation of 129 I and 131 I, accounting for uncertainties in biokinetic model and cancer risk model parameter values. These estimates are compared with the equivalent ICRP derived nominal age-, sex- and population-averaged estimates of excess thyroid cancer incidence to obtain UFs. Derived UF values for ingestion or inhalation of 131 I for 1 year, 10-year and 20-year olds are around 28, 12 and 6, respectively, when compared with ICRP Publication 103 nominal values, and 9, 7 and 14, respectively, when compared with ICRP Publication 60 values. Broadly similar results were obtained for 129 I. The uncertainties on risk estimates are largely determined by uncertainties on risk model parameters rather than uncertainties on biokinetic model parameters. An examination of the sensitivity of the results to the risk models and populations used in the calculations show variations in the central estimates of risk of a factor of around 2-3. It is assumed that the direct proportionality of excess thyroid cancer

Population dose assessment from radiodiagnosis in Portugal

International Nuclear Information System (INIS)

Serro, R.; Carreiro, J.V.; Galvao, J.P.; Reis, R.

1992-01-01

A survey of radiodiagnostic installations was carried out in Portugal covering 75 premises including public hospitals, local and regional public health centres. A total of 175 X ray tubes was surveyed using the new NEXT methodology covering data on premises, tube and operator, and projection. Average value of voltage, current-time product, HVL, ratio of beam area to film area and source to film distance for the eleven most frequent projections are reported as well as the skin entrance exposure and the doses to some organs. The weighted average dose values per projection and for the different organs allowed an estimate of the whole-body dose per caput. From the gonadal doses the genetic significant dose was also estimated

Implications of the new dose limit crystalline in operational radiation protection in interventional medicine; Implicaciones del nuevo limite de dosis en cristalino en la proteccion radiologica operacional en intervencionismo

Energy Technology Data Exchange (ETDEWEB)

Roch Gonzalez, M.; Garcia Castanon, P.; Giner Sala, M.; Rodriguez Martin, G.; Espana Lopez, M. L.

2013-07-01

The objective of this study is to evaluate the implications of this new limit of equivalent dose in the lens can be assumed in the radiation protection of cardiologists, radiologists, nursing professionals, etc. that perform their work in units of intervention, both in terms of additional protective measures and the classification of them as workers exposed. (Author)

The Limit of Public Policy : Endogenous Preferences

NARCIS (Netherlands)

Bar-Gill, O.; Fershtman, C.

2000-01-01

In designing public policy it is not enough to consider the possible reaction of individuals to the chosen policy.Public policy may also affect the formation of preferences and norms in a society.The endogenous evolution of preferences, in addition to introducing a conceptual difficulty in

The cost and benefit analysis of a contaminated area remediation: case study of dose level selection

Energy Technology Data Exchange (ETDEWEB)

Lauria, D.C. [Instituto de Radioproteccion e Dosimetria- IRD/CNEN, Av. Salvador Allende s/n, Barra de Tijuca, Rio de Janeiro- RJ (Brazil)]. e-mail: dejanira@ird.gov.br

2006-07-01

In recent years there has been an increasing awareness of the radiological impact of non-nuclear industries that extract and/or process ores and minerals containing naturally occurring radioactive material (NORM). Without radiological rules, these industrial activities may result in significant radioactive contamination of installations and sites. Depending on the potential hazardous to the environment and public health, the radioactive contaminated sites may require remediation. The extent of the site cleanup is a function of the size, localization, complexity, potential risks and on possible future uses envisioned for the site. Since worker and public health, public anxiety and economics factors are involved; the selection of an appropriate dose level can be quite complicated. This paper discusses the selection of a dose level criterion to remedy a site, which was contaminated by wastes from monazite processing. The site is located in the Sao Paulo city; the most densely populated Brazilian City. In its 60,000 square meters of area, a preliminary survey showed contaminated zones covering an area of 6,500 square meters. In some places, contamination was found below the superficial layer of the soil, being the radionuclide vertical distribution not uniform. The {sup 228} Ra soil activity concentration reached values up to 33,000 Bq/kg while those for {sup 226} Ra reached values up to 6,700 Bq/kg. Based on pathway analysis model and considering both the current land use and a hypothetical residential scenario, the residual contamination levels of radionuclides in soil have been derived for dose values of 10 mSv/y (dose level for intervention), 5 mSv/y, 3 mSv/y, 1 mSv/y (dose limit for practices) and 0.3 mSv/y (dose constraint for practices). An optimized value o f annual dose of about 5 mSv/y would be a good option for intervention level, but taking into account the public concern and anxiety, the site location and size, and the remediation costs, it is suggested

The cost and benefit analysis of a contaminated area remediation: case study of dose level selection

International Nuclear Information System (INIS)

Lauria, D.C.

2006-01-01

In recent years there has been an increasing awareness of the radiological impact of non-nuclear industries that extract and/or process ores and minerals containing naturally occurring radioactive material (NORM). Without radiological rules, these industrial activities may result in significant radioactive contamination of installations and sites. Depending on the potential hazardous to the environment and public health, the radioactive contaminated sites may require remediation. The extent of the site cleanup is a function of the size, localization, complexity, potential risks and on possible future uses envisioned for the site. Since worker and public health, public anxiety and economics factors are involved; the selection of an appropriate dose level can be quite complicated. This paper discusses the selection of a dose level criterion to remedy a site, which was contaminated by wastes from monazite processing. The site is located in the Sao Paulo city; the most densely populated Brazilian City. In its 60,000 square meters of area, a preliminary survey showed contaminated zones covering an area of 6,500 square meters. In some places, contamination was found below the superficial layer of the soil, being the radionuclide vertical distribution not uniform. The 228 Ra soil activity concentration reached values up to 33,000 Bq/kg while those for 226 Ra reached values up to 6,700 Bq/kg. Based on pathway analysis model and considering both the current land use and a hypothetical residential scenario, the residual contamination levels of radionuclides in soil have been derived for dose values of 10 mSv/y (dose level for intervention), 5 mSv/y, 3 mSv/y, 1 mSv/y (dose limit for practices) and 0.3 mSv/y (dose constraint for practices). An optimized value o f annual dose of about 5 mSv/y would be a good option for intervention level, but taking into account the public concern and anxiety, the site location and size, and the remediation costs, it is suggested the

Public radiation exposure due to radon transport from a uranium mine

International Nuclear Information System (INIS)

Akber, R.A.; Johnston, A.; Pfitzner, J.

1992-01-01

Radon and radon daughter concentrations at locations several kilometres away from a uranium mine are due both to the background sources and the mine-related sources. The contribution of these two types of sources should be distinguished because the authorised limits on public radiation dose apply only to the mine-related sources. Such a distinction can be achieved by measuring radon and radon daughter concentration in the wind sectors containing only the background sources and those in the wind sectors containing both the background and the mine-related sources. This approach has been used to make estimates of public radiation dose due to radon transport from the Ranger Uranium Mine in Australia. The residential town of Jabiru, the non-residential working town of Jabiru East, and the aboriginal camp sites in the vicinity of the mine were considered. The results indicate that, for the groups of population considered, the annual mine-related dose varies between 0.04 and 0.2 mSv. (author)

Estimating Effective Dose of Radiation From Pediatric Cardiac CT Angiography Using a 64-MDCT Scanner: New Conversion Factors Relating Dose-Length Product to Effective Dose.

Science.gov (United States)

Trattner, Sigal; Chelliah, Anjali; Prinsen, Peter; Ruzal-Shapiro, Carrie B; Xu, Yanping; Jambawalikar, Sachin; Amurao, Maxwell; Einstein, Andrew J

2017-03-01

The purpose of this study is to determine the conversion factors that enable accurate estimation of the effective dose (ED) used for cardiac 64-MDCT angiography performed for children. Anthropomorphic phantoms representative of 1- and 10-year-old children, with 50 metal oxide semiconductor field-effect transistor dosimeters placed in organs, underwent scanning performed using a 64-MDCT scanner with different routine clinical cardiac scan modes and x-ray tube potentials. Organ doses were used to calculate the ED on the basis of weighting factors published in 1991 in International Commission on Radiological Protection (ICRP) publication 60 and in 2007 in ICRP publication 103. The EDs and the scanner-reported dose-length products were used to determine conversion factors for each scan mode. The effect of infant heart rate on the ED and the conversion factors was also assessed. The mean conversion factors calculated using the current definition of ED that appeared in ICRP publication 103 were as follows: 0.099 mSv · mGy -1 · cm -1 , for the 1-year-old phantom, and 0.049 mSv · mGy -1 · cm -1 , for the 10-year-old phantom. These conversion factors were a mean of 37% higher than the corresponding conversion factors calculated using the older definition of ED that appeared in ICRP publication 60. Varying the heart rate did not influence the ED or the conversion factors. Conversion factors determined using the definition of ED in ICRP publication 103 and cardiac, rather than chest, scan coverage suggest that the radiation doses that children receive from cardiac CT performed using a contemporary 64-MDCT scanner are higher than the radiation doses previously reported when older chest conversion factors were used. Additional up-to-date pediatric cardiac CT conversion factors are required for use with other contemporary CT scanners and patients of different age ranges.

Individual dose due to radioactivity accidental release from fusion reactor

Energy Technology Data Exchange (ETDEWEB)

Nie, Baojie [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China); Ni, Muyi, E-mail: muyi.ni@fds.org.cn [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); Wei, Shiping [Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); University of Science and Technology of China, Hefei, Anhui, 230027 (China)

2017-04-05

Highlights: • Conservative early dose of different unit fusion radioactivity release were assessed. • Data of accident level in INES for fusion reactor were proposed. • Method of environmental restoration time after fusion accident was proposed. • The maximum possible accident level for ITER like fusion reactor is 6. • We need 34–52 years to live after the fusion hypothetical accident. - Abstract: As an important index shaping the design of fusion safety system, evaluation of public radiation consequences have risen as a hot topic on the way to develop fusion energy. In this work, the comprehensive public early dose was evaluated due to unit gram tritium (HT/HTO), activated dust, activated corrosion products (ACPs) and activated gases accidental release from ITER like fusion reactor. Meanwhile, considering that we cannot completely eliminate the occurrence likelihood of multi-failure of vacuum vessel and tokamak building, we conservatively evaluated the public radiation consequences and environment restoration after the worst hypothetical accident preliminarily. The comparison results show early dose of different unit radioactivity release under different conditions. After further performing the radiation consequences, we find it possible that the hypothetical accident for ITER like fusion reactor would result in a level 6 accident according to INES, not appear level 7 like Chernobyl or Fukushima accidents. And from the point of environment restoration, we need at least 69 years for case 1 (1 kg HTO and 1000 kg dust release) and 34–52 years for case 2 (1 kg HTO and 10kg–100 kg dust release) to wait the contaminated zone drop below the general public safety limit (1mSv per year) before it is suitable for human habitation.

Measurement of dose equivalent distribution on-board commercial jet aircraft

International Nuclear Information System (INIS)

Kubancak, J.; Ambrozova, I.; Ploc, O.; Pachnerova Brabcova, K.; Stepan, V.; Uchihori, Y.

2014-01-01

The annual effective doses of aircrew members often exceed the limit of 1 mSv for the public due to the increased level of cosmic radiation at the flight altitudes, and thus, it is recommended to monitor them [International Commission on Radiation Protection. 1990 Recommendations of the International Commission on Radiological Protection. ICRP Publication 60. Ann. ICRP 21(1-3), (1991)]. According to the Monte Carlo simulations [Battistoni, G., Ferrari, A., Pelliccioni, M. and Villari, R. Evaluation of the doses to aircrew members taking into consideration the aircraft structures. Adv. Space Res. 36, 1645-1652 (2005) and Ferrari, A., Pelliccioni, M. and Villari, R. Evaluation of the influence of aircraft shielding on the aircrew exposure through an aircraft mathematical model. Radiat. Prot. Dosim. 108(2), 91-105 (2004)], the ambient dose equivalent rate H*(10) depends on the location in the aircraft. The aim of this article is to experimentally evaluate H*(10) on-board selected types of aircraft. The authors found that H*(10) values are higher in the front and the back of the cabin and lesser in the middle of the cabin. Moreover, total dosimetry characteristics obtained in this way are in a reasonable agreement with other data, in particular with the above-mentioned simulations. (authors)

New recommendations for dose equivalent

International Nuclear Information System (INIS)

Bengtsson, G.

1985-01-01

In its report 39, the International Commission on Radiation Units and Measurements (ICRU), has defined four new quantities for the determination of dose equivalents from external sources: the ambient dose equivalent, the directional dose equivalent, the individual dose equivalent, penetrating and the individual dose equivalent, superficial. The rationale behind these concepts and their practical application are discussed. Reference is made to numerical values of these quantities which will be the subject of a coming publication from the International Commission on Radiological Protection, ICRP. (Author)

SUDOQU, a new dose-assessment methodology for radiological surface contamination.

Science.gov (United States)

van Dillen, Teun; van Dijk, Arjan

2018-06-12

A new methodology has been developed for the assessment of the annual effective dose resulting from removable and fixed radiological surface contamination. It is entitled SUDOQU (SUrface DOse QUantification) and it can for instance be used to derive criteria for surface contamination related to the import of non-food consumer goods, containers and conveyances, e.g., limiting values and operational screening levels. SUDOQU imposes mass (activity)-balance equations based on radioactive decay, removal and deposition processes in indoor and outdoor environments. This leads to time-dependent contamination levels that may be of particular importance in exposure scenarios dealing with one or a few contaminated items only (usually public exposure scenarios, therefore referred to as the 'consumer' model). Exposure scenarios with a continuous flow of freshly contaminated goods also fall within the scope of the methodology (typically occupational exposure scenarios, thus referred to as the 'worker model'). In this paper we describe SUDOQU, its applications, and its current limitations. First, we delineate the contamination issue, present the assumptions and explain the concepts. We describe the relevant removal, transfer, and deposition processes, and derive equations for the time evolution of the radiological surface-, air- and skin-contamination levels. These are then input for the subsequent evaluation of the annual effective dose with possible contributions from external gamma radiation, inhalation, secondary ingestion (indirect, from hand to mouth), skin contamination, direct ingestion and skin-contact exposure. The limiting effective surface dose is introduced for issues involving the conservatism of dose calculations. SUDOQU can be used by radiation-protection scientists/experts and policy makers in the field of e.g. emergency preparedness, trade and transport, exemption and clearance, waste management, and nuclear facilities. Several practical examples are worked

Biostatistical approaches for modeling U-shaped dose-response curves and study design considerations in assessing the biological effects of low doses

International Nuclear Information System (INIS)

Downs, T.

1992-01-01

The demonstration of hormetic effects is rendered difficult for a number of reasons: The spontaneous rate must be large enough for a difference to be detectable. In contrast with detrimental effects, there is a limited range of doses over which beneficial effects are likely to be found. Publication bias hampers publication of low-dose beneficial effects and discourages research in the area. Some scientists actually believe that hormetic effects are contary to reason. All these factors contribute to lessen the chances of detecting hormetic effects through synthesis of the scientific literature. The extra statistical power obtained from mathematical modeling is not available for hormetic studies when appropriate models are not available. Even a simple statistical device such as a test for linear trend does not work well for U-shaped data. The first part of this two-part chapter deals with the probabilities of determining qualitatively what kinds of health effects may result from exposures to substances, and the second part with characterizing quantitative relationships between such health effects and exposures. The health effects may be beneficial in some situations, and detrimental in others

Effective dose in the manufacturing process of rutile covered welding electrodes.

Science.gov (United States)

Herranz, M; Rozas, S; Pérez, C; Idoeta, R; Núñez-Lagos, R; Legarda, F

2013-03-01

Shielded metal arc welding using covered electrodes is the most common welding process. Sometimes the covering contains naturally occurring radioactive materials (NORMs). In Spain the most used electrodes are those covered with rutile mixed with other materials. Rutile contains some detectable natural radionuclides, so it can be considered a NORM. This paper mainly focuses on the use of MCNP (Monte Carlo N-Particle Transport Code) as a predictive tool to obtain doses in a factory which produces this type of electrode and assess the radiological impact in a specific facility after estimating the internal dose.To do this, in the facility, areas of highest radiation and positions of workers were identified, radioactive content of rutile and rutile covered electrodes was measured, and, considering a worst possible scenario, external dose at working points has been calculated using MCNP. This procedure has been validated comparing the results obtained with those from a pressurised ionisation chamber and TLD dosimeters. The internal dose has been calculated using DCAL (dose and risk calculation). The doses range between 8.8 and 394 μSv yr(-1), always lower than the effective dose limit for the public, 1 mSv yr(-1). The highest dose corresponds to the mixing area.

Feasibility study for the assessment of the exposed dose with TENORM added in consumer products

International Nuclear Information System (INIS)

Yoo, Do Hyeon; Lee, Hyun Cheol; Shin, Wook-Geun; Min, Chul Hee; Ha, Wi-Ho; Yoo, Jae Ryong; Yoon, Seok-Won; Lee, Jiyon; Choi, Won-Chul

2015-01-01

Consumer products including naturally occurring radioactive material have been distributed widely in human life. The potential hazard of the excessively added technically enhanced naturally occurring radioactive material (TENORM) in consumer products should be assessed. The aim of this study is to evaluate the organ equivalent dose and the annual effective dose with the usage of the TENORM added in paints. The activities of gammas emitted from natural radionuclides in the five types of paints were measured with the high-purity germanium detector, and the annual effective dose was assessed with the computational human phantom and the Monte Carlo method. The results show that uranium and thorium series were mainly measured over the five paints. Based on the exposure scenario of the paints in the room, the highest effective dose was evaluated as <1 mSv y -1 of the public dose limit. (authors)

Preliminary evaluation of the activity concentration limits for consumer goods containing NORM

Energy Technology Data Exchange (ETDEWEB)

Jang, Mee; Chung, Kun Ho; Ji, Young Yong; Lim, Jong Myung; Kang, Mun Ja; Choi, Guen Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-06-15

To protect the public from natural radioactive materials, the 'Act on safety control of radioactive rays around living environment' was established in Korea. There is an annual effective dose limit of 1 mSv for products, but the activity concentration limit for products is not established yet. To suggest the activity concentration limits for consumer goods containing NORM, in this research, we assumed the 'small room model' surrounding the ICRP reference phantom to simulate the consumer goods in contact with the human bodies. Using the Monte Carlo code MCNPX, we evaluate the effective dose rate for the ICRP reference phantom in a small room with dimension of phantom size and derived the activity concentration limit for consumer goods. The consumer goods have about 1600, 1200 and 19000 Bq·kg{sup -1} for {sup 226}Ra, {sup 232}Th and {sup 40}K, and the activity concentration limits are about six times comparing with the values of building materials. We applied the index to real samples, though we did not consider radioactivity of {sup 40}K, indexes of the some samples are more than 6. However, this index concept using small room model is very conservative, for the consumer goods over than index 6, it is necessary to reevaluate the absorbed dose considering real usage scenario and material characteristics. In this research, we derived activity concentration limits for consumer goods in contact with bodies and the results can be used as preliminary screening tool for consumer goods as index concept.

Preliminary evaluation of the activity concentration limits for consumer goods containing NORM

International Nuclear Information System (INIS)

Jang, Mee; Chung, Kun Ho; Ji, Young Yong; Lim, Jong Myung; Kang, Mun Ja; Choi, Guen Sik

2016-01-01

To protect the public from natural radioactive materials, the 'Act on safety control of radioactive rays around living environment' was established in Korea. There is an annual effective dose limit of 1 mSv for products, but the activity concentration limit for products is not established yet. To suggest the activity concentration limits for consumer goods containing NORM, in this research, we assumed the 'small room model' surrounding the ICRP reference phantom to simulate the consumer goods in contact with the human bodies. Using the Monte Carlo code MCNPX, we evaluate the effective dose rate for the ICRP reference phantom in a small room with dimension of phantom size and derived the activity concentration limit for consumer goods. The consumer goods have about 1600, 1200 and 19000 Bq·kg -1 for 226 Ra, 232 Th and 40 K, and the activity concentration limits are about six times comparing with the values of building materials. We applied the index to real samples, though we did not consider radioactivity of 40 K, indexes of the some samples are more than 6. However, this index concept using small room model is very conservative, for the consumer goods over than index 6, it is necessary to reevaluate the absorbed dose considering real usage scenario and material characteristics. In this research, we derived activity concentration limits for consumer goods in contact with bodies and the results can be used as preliminary screening tool for consumer goods as index concept

Reconstructive dosimetry and radiation doses evaluation of members of the public due to radiological accident in industrial radiography; Dosimetria reconstrutiva e avaliacao de dose de individuos do publico devido a acidente radiologico em radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

Lima, Camila Moreira Araujo de

2016-07-01

Radiological accidents have occurred mainly in the practices recognized as high risk radiological and classified by the IAEA as Categories 1 and 2, and highlighted the radiotherapy, industrial irradiators and industrial radiography. In Brazil, since there were five major cases in industrial radiography, which involved 7 radiation workers and 19 members of the public, causing localized radiation lesions on the hands and fingers. One of these accidents will be the focus of this work. In this accident, a {sup 192}Ir radioactive source was exposed for more than 8 hours in the workplace inside a company, exposing radiation workers, individuals of the public and people from the surrounding facilities, including children of a school. The radioactive source was also handled by a security worker causing severe radiation injuries in the hand and fingers. In this paper, the most relevant and used techniques of reconstructive dosimetry internationally are presented. To estimate the radiation doses received by exposed individuals in various scenarios of radiological accident in focus, the following computer codes were used: Visual Monte Carlo Dose Calculation (VMC), Virtual Environment for Radiological and Nuclear Accidents Simulation (AVSAR) and RADPRO Calculator. Through these codes some radiation doses were estimated, such as, 33.90 Gy in security worker's finger, 4.47 mSv in children in the school and 55 to 160 mSv for workers in the company during the whole day work. It is intended that this work will contribute to the improvement of dose reconstruction methodology for radiological accidents, having then more realist radiation doses. (author)

Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-09-01

This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

International Nuclear Information System (INIS)

Jannik, G. T.; Dixon, K. L.

2016-01-01

This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

''Low dose'' and/or ''high dose'' in radiation protection: A need to setting criteria for dose classification

International Nuclear Information System (INIS)

Sohrabi, M.

1997-01-01

The ''low dose'' and/or ''high dose'' of ionizing radiation are common terms widely used in radiation applications, radiation protection and radiobiology, and natural radiation environment. Reading the title, the papers of this interesting and highly important conference and the related literature, one can simply raise the question; ''What are the levels and/or criteria for defining a low dose or a high dose of ionizing radiation?''. This is due to the fact that the criteria for these terms and for dose levels between these two extreme quantities have not yet been set, so that the terms relatively lower doses or higher doses are usually applied. Therefore, setting criteria for classification of radiation doses in the above mentioned areas seems a vital need. The author while realizing the existing problems to achieve this important task, has made efforts in this paper to justify this need and has proposed some criteria, in particular for the classification of natural radiation areas, based on a system of dose limitation. (author)

Dosimetric consideration of polonium-210 for Tiruchirappalli public

International Nuclear Information System (INIS)

Shaheed, K.; Somasundaram, S.S.N.; Shahul Hameed, P.

1997-01-01

This paper deals with the committed effective dose equivalent from polonium-210 to the public of Tiruchirappalli district in south India on consumption of cereals, vegetables and animal food. It is demonstrated that the activity of 210 Po is non-uniformly distributed between cereals, vegetables and animal food. Among cereals, the green gram recorded a higher activity of 210 Po (0.62 Bq.kg -1 ) than the others tested. The study also recorded a relatively enhanced activity in raw rice (0.90 Bq.kg -1 ) than in boiled rice (0.03 Bq.kg -1 ). Among vegetables, the tubers accumulated more 210 Po than the shoot growing vegetables. The muscle of prawn (Macrobrachium rosenbergii) recorded the highest level of 210 Po activity (13.9 Bq.kg -1 ) among the animal food. With reference to dosimetry, the animal food was identified to contribute higher radiation dose (0.38-29.5 μSv.y -1 ) than the cereals (0.05 - 1.9 μSv.y -1 ) and vegetables (0.05 - 1.9 μSv.y -1 ). Among animal food, the fish contributed a substantial level of α radiation dose to man. Though activity in raw rice was higher than the activity in boiled rice, the dose delivered from raw rice was substantially low since the average consumption of this rice represents only 7 kg.y -1 when compared to the consumption of boiled rice (108 kg.y -1 ). From the dose estimates made, it was evident that the total dose received by the general public (2.7 μSv.y -1 ) from 210 Po was well below the dose limit of 1mSv.y -1 . (author)

Limitations of high dose carrier based formulations.

Science.gov (United States)

Yeung, Stewart; Traini, Daniela; Tweedie, Alan; Lewis, David; Church, Tanya; Young, Paul M

2018-06-10

This study was performed to investigate how increasing the active pharmaceutical ingredient (API) content within a formulation affects the dispersion of particles and the aerosol performance efficiency of a carrier based dry powder inhalable (DPI) formulation, using a custom dry powder inhaler (DPI) development rig. Five formulations with varying concentrations of API beclomethasone dipropionate (BDP) between 1% and 30% (w/w) were formulated as a multi-component carrier system containing coarse lactose and fine lactose with magnesium stearate. The morphology of the formulation and each component were investigated using scanning electron micrographs while the particle size was measured by laser diffraction. The aerosol performance, in terms of aerodynamic diameter, was assessed using the British pharmacopeia Apparatus E cascade impactor (Next generation impactor). Chemical analysis of the API was observed by high performance liquid chromatography (HPLC). Increasing the concentration of BDP in the blend resulted in increasing numbers and size of individual agglomerates and densely packed BDP multi-layers on the surface of the lactose carrier. BDP present within the multi-layer did not disperse as individual primary particles but as dense agglomerates, which led to a decrease in aerosol performance and increased percentage of BDP deposition within the Apparatus E induction port and pre-separator. As the BDP concentration in the blends increases, aerosol performance of the formulation decreases, in an inversely proportional manner. Concurrently, the percentage of API deposition in the induction port and pre-separator could also be linked to the amount of micronized particles (BDP and Micronized composite carrier) present in the formulation. The effect of such dose increase on the behaviour of aerosol dispersion was investigated to gain greater insight in the development and optimisation of higher dosed carrier-based formulations. Copyright © 2018 Elsevier B.V. All

Dose from radiological examinations

International Nuclear Information System (INIS)

Imamura, Keiko; Uji, Teruyuki; Sakuyama, Keiko; Fujikawa, Mitsuhiro; Fujii, Masamichi

1976-01-01

Relatively high gonad doses, several hundred to one thousand mR, have been observed in case of pelvis, hip-joint, coccyx, lower abdomen and lumber examination. Dose to the ovary is especially high in barium enema and I.V.P. examinations. About 12 per cent of the 4-ray examination are high-dose. The gonad dose is relatively high in examination of abdomen and lower extremities, in infants. The dose to the eyes is especially high, 1.0 to 2.5R per exposure, in temporal bone and nasal sinuses tomography. X-ray doses have been compared with dose limits recommended by ICRP and with the gonad dose from natural radiations. The gonad dose in lumbar examination, barium enema, I.V.P. etc. is as high as the maximum permissible dose per year recommended by ICRP. Several devices have been made for dose reduction in the daily examinations: (1) separating the radiation field from the gonad by one centimeter decreases the gonad dose about one-half. (2) using sensitive screens and films. In pelvimetry and in infant hip-joint examination, the most sensitive screen and film are used. In the I.V.P. examination of adult, use of MS screen in place of FS screen decreases the dose to one-third, in combination with careful setting of radiation field, (3) use of grid increases the dose about 50 percent and the lead rubber protection (0.1mm lead equivalent) decreases the gonad dose to one-thirtieth in the spinal column examination of infant, (4) A lead protector, 1mm thickness and 2.5cm in diameter, on the eyes decreases the dose to about one-eighth in the face and nead examinations. These simple and effective methods for dose reduction. Should be carried out in as many examinations as possible in addition to observing dose limits recommended by ICRP. (Evans, J.)

From dust to dose: Effects of forest disturbance on increased inhalation exposure

International Nuclear Information System (INIS)

Whicker, Jeffrey J.; Pinder, John E.; Breshears, David D.; Eberhart, Craig F.

2006-01-01

inhalation doses for workers ranging from 15% to 38%. Despite the potential for increased doses resulting from these forest disturbances, the estimated annual dose rate for the public was -1 , which is far below the dose limits for public exposures, and the upper-bound dose rate for a LANL worker was estimated to be 140 μSv yr -1 , far below the 5 x 10 4 μSv yr -1 occupational dose limit. These results show the importance of ecosystem disturbance in increasing mobility of soil-bound contaminants, which can ultimately increase exposure. However, it is important to investigate the magnitude of the increases when deciding appropriate strategies for management and long-term stewardship of contaminated lands

Rectal balloon use limits vaginal displacement, rectal dose, and rectal toxicity in patients receiving IMRT for postoperative gynecological malignancies.

Science.gov (United States)

Wu, Cheng-Chia; Wuu, Yen-Ruh; Yanagihara, Theodore; Jani, Ashish; Xanthopoulos, Eric P; Tiwari, Akhil; Wright, Jason D; Burke, William M; Hou, June Y; Tergas, Ana I; Deutsch, Israel

2018-01-01

Pelvic radiotherapy for gynecologic malignancies traditionally used a 4-field box technique. Later trials have shown the feasibility of using intensity-modulated radiotherapy (IMRT) instead. But vaginal movement between fractions is concerning when using IMRT due to greater conformality of the isodose curves to the target and the resulting possibility of missing the target while the vagina is displaced. In this study, we showed that the use of a rectal balloon during treatment can decrease vaginal displacement, limit rectal dose, and limit acute and late toxicities. Little is known regarding the use of a rectal balloon (RB) in treating patients with IMRT in the posthysterectomy setting. We hypothesize that the use of an RB during treatment can limit rectal dose and acute and long-term toxicities, as well as decrease vaginal cuff displacement between fractions. We performed a retrospective review of patients with gynecological malignancies who received postoperative IMRT with the use of an RB from January 1, 2012 to January 1, 2015. Rectal dose constraint was examined as per Radiation Therapy Oncology Group (RTOG) 1203 and 0418. Daily cone beam computed tomography (CT) was performed, and the average (avg) displacement, avg magnitude, and avg magnitude of vector were calculated. Toxicity was reported according to RTOG acute radiation morbidity scoring criteria. Acute toxicity was defined as less than 90 days from the end of radiation treatment. Late toxicity was defined as at least 90 days after completing radiation. Twenty-eight patients with postoperative IMRT with the use of an RB were examined and 23 treatment plans were reviewed. The avg rectal V40 was 39.3% ± 9.0%. V30 was65.1% ± 10.0%. V50 was 0%. Separate cone beam computed tomography (CBCT) images (n = 663) were reviewed. The avg displacement was as follows: superior 0.4 + 2.99 mm, left 0.23 ± 4.97 mm, and anterior 0.16 ± 5.18 mm. The avg magnitude of displacement was superior

A risk-informed basis for establishing non-fixed surface contamination limits for spent fuel transportation casks

International Nuclear Information System (INIS)

Rawl, R.R.; Eckerman, K.F.; Bogard, J.S.; Cook, J.R.

2004-01-01

The current limits for non-fixed contamination on packages used to transport radioactive materials were introduced in the 1961 edition of the International Atomic Energy Agency (IAEA) transport regulations and were based on radiation protection guidance and practices in use at that time. The limits were based on exposure scenarios leading to intakes of radionuclides by inhalation and external irradiation of the hands. These considerations are collectively referred to as the Fairbairn model. Although formulated over 40 years ago, the model remains unchanged and is still the basis of current regulatory-derived limits on package non-fixed surface contamination. There can also be doses that while not resulting directly from the contamination, are strongly influenced by and attributable to transport regulatory requirements for contamination control. For example, actions necessary to comply with the current derived limits for light-water-reactor (LWR) spent nuclear fuel (SNF) casks can result in significant external doses to workers. This is due to the relatively high radiation levels around the loaded casks, where workers must function during the measurement of contamination levels and while decontaminating the cask. In order to optimize the total dose received due to compliance with cask contamination levels, it is necessary to take into account all the doses that vary as a result of the regulatory limit. Limits for non-fixed surface contamination on spent fuel casks should be established by using a model that considers and optimizes the appropriate exposure scenarios both in the workplace and in the public environment. A risk-informed approach is needed to ensure optimal use of personnel and material resources for SNF-based packaging operations. This paper is a summary of a study sponsored by the US Nuclear Regulatory Commission and performed by Oak Ridge National Laboratory that examined the dose implications for removable surface contamination limits on spent fuel

Committed effective dose determination in cereal flours by gamma-ray spectrometry; Determinacao das doses efetivas por ingestao de farinhas de cereais atraves da espectrometria de raios gama

Energy Technology Data Exchange (ETDEWEB)

Scheibel, Viviane

2006-07-01

The health impact from radionuclides ingestion of foodstuffs was evaluated by the committed effective doses determined in commercial samples of South-Brazilian cereal flours (soy, wheat, corn, manioc, rye, oat, barley and rice flour). The radioactivity traces of {sup 228}Th, {sup 228}Ra, {sup 226}Ra, {sup 40}K, {sup 7}Be and {sup 137}Cs were measured by gamma-ray spectrometry employing a 66% relative efficiency HPGe detector. The energy resolution for the 1332.46 keV line of {sup 60}Co was 2.03 keV. The committed effective doses were calculated with the activities analyzed in the present flour samples, the foodstuff rates of consumption (Brazilian Institute of Geography and Statistics) and the ingestion dose coefficients (International Commission of Radiological Protection). The reliability median activities were verified with {chi}{sup 2} tests, assuring the fittings quality. The highest concentration levels of {sup 228}Th and {sup 40}K were 3.5 {+-} 0.4 and 1469 {+-} 17 Bq.kg{sup -1} for soy flour, respectively, with 95% of confidence level. The lower limit of detection for {sup 137}Cs ranged from 0.04 to 0.4 Bq.kg{sup -1}. The highest committed effective dose was 0.36 {mu}Sv.y{sup -1} for {sup 228}Ra in manioc flour (adults). All committed effective doses determined at the present work were lower than the UNSCEAR limits of 140 {mu}Sv.y{sup -1} and much lower than the ICRP (1991) limits of 1 mSv.y{sup -1}, for general public. There are few literature references for natural and artificial radionuclides in foodstuffs and mainly for committed effective doses. This work brings the barley flour data, which is not present at the literature and {sup 7}Be data which is not encountered in foodstuffs at the literature, besides all the other flours data information about activities and committed effective doses. (author)

Comparison of Radiation Dose Rates with the Flux to Dose Conversion Factors Recommended in ICRP-74 and ICRP-116

International Nuclear Information System (INIS)

Jeong, Hae Sun; Kil, A Reum; Lee, Jo Eun; Jeong, Hyo Joon; Kim, Eun Han; Han, Moon Hee; Hwang, Won Tae

2016-01-01

The evaluation of radiation shielding has been performed for the design and maintenance of various facilities using radioactive sources such as nuclear fuel, accelerator, and radionuclide. The conversion of flux to dose mainly used in nuclear and radiation fields has been generally made with the dose coefficients presented in ICRP Publication 74 (ICRP- 74), which are produced based on ICRP Publication 60. On the other hand, ICRP Publication 116 (ICRP-116), which adopts the protection system of ICRP Publication 103, has recently been published and provides the dose conversion coefficients calculated with a variety of Monte Carlo codes. The coefficients have more than an update of those in ICRP-74, including new particle types and a greatly expanded energy range. In this study, a shielding evaluation of a specific container for neutron and gamma sources was performed with the MCNP6 code. The dose rates from neutron and gamma-ray sources were calculated using the MCNP6 codes, and these results were based on the flux to dose conversion factors recommended in ICRP-74 and ICRP-116. As a result, the dose rates evaluated with ICRP-74 were generally shown higher than those with ICRP-116. For neutrons, the difference is mainly occurred by the decrease of radiation weighting factors in a part of energy ranges in the ICRP-116 recommendations. For gamma-rays, the ICRP-74 recommendation applied with the kerma approximation leads to overestimated results than the other assessment

SU-G-JeP3-06: Lower KV Image Dose Are Expected From a Limited-Angle Intra-Fractional Verification (LIVE) System for SBRT Treatments

Energy Technology Data Exchange (ETDEWEB)

Ding, G [Vanderbilt University Nashville, TN (United States); Yin, F; Ren, L [Duke University Medical Center, Durham, NC (United States)

2016-06-15

Purpose: In order to track the tumor movement for patient positioning verification during arc treatment delivery or in between 3D/IMRT beams for stereotactic body radiation therapy (SBRT), the limited-angle kV projections acquisition simultaneously during arc treatment delivery or in-between static treatment beams as the gantry moves to the next beam angle was proposed. The purpose of this study is to estimate additional imaging dose resulting from multiple tomosynthesis acquisitions in-between static treatment beams and to compare with that of a conventional kV-CBCT acquisition. Methods: kV imaging system integrated into Varian TrueBeam accelerators was modeled using EGSnrc Monte Carlo user code, BEAMnrc and DOSXYZnrc code was used in dose calculations. The simulated realistic kV beams from the Varian TrueBeam OBI 1.5 system were used to calculate dose to patient based on CT images. Organ doses were analyzed using DVHs. The imaging dose to patient resulting from realistic multiple tomosynthesis acquisitions with each 25–30 degree kV source rotation between 6 treatment beam gantry angles was studied. Results: For a typical lung SBRT treatment delivery much lower (20–50%) kV imaging doses from the sum of realistic six tomosynthesis acquisitions with each 25–30 degree x-ray source rotation between six treatment beam gantry angles were observed compared to that from a single CBCT image acquisition. Conclusion: This work indicates that the kV imaging in this proposed Limited-angle Intra-fractional Verification (LIVE) System for SBRT Treatments has a negligible imaging dose increase. It is worth to note that the MV imaging dose caused by MV projection acquisition in-between static beams in LIVE can be minimized by restricting the imaging to the target region and reducing the number of projections acquired. For arc treatments, MV imaging acquisition in LIVE does not add additional imaging dose as the MV images are acquired from treatment beams directly during the

Derivation of dose conversion factors for tritium

Energy Technology Data Exchange (ETDEWEB)

Killough, G. G.

1982-03-01

For a given intake mode (ingestion, inhalation, absorption through the skin), a dose conversion factor (DCF) is the committed dose equivalent to a specified organ of an individual per unit intake of a radionuclide. One also may consider the effective dose commitment per unit intake, which is a weighted average of organ-specific DCFs, with weights proportional to risks associated with stochastic radiation-induced fatal health effects, as defined by Publication 26 of the International Commission on Radiological Protection (ICRP). This report derives and tabulates organ-specific dose conversion factors and the effective dose commitment per unit intake of tritium. These factors are based on a steady-state model of hydrogen in the tissues of ICRP's Reference Man (ICRP Publication 23) and equilibrium of specific activities between body water and other tissues. The results differ by 27 to 33% from the estimate on which ICRP Publication 30 recommendations are based. The report also examines a dynamic model of tritium retention in body water, mineral bone, and two compartments representing organically-bound hydrogen. This model is compared with data from human subjects who were observed for extended periods. The manner of combining the dose conversion factors with measured or model-predicted levels of contamination in man's exposure media (air, drinking water, soil moisture) to estimate dose rate to an individual is briefly discussed.

Derivation of dose conversion factors for tritium

International Nuclear Information System (INIS)

Killough, G.G.

1982-03-01

For a given intake mode (ingestion, inhalation, absorption through the skin), a dose conversion factor (DCF) is the committed dose equivalent to a specified organ of an individual per unit intake of a radionuclide. One also may consider the effective dose commitment per unit intake, which is a weighted average of organ-specific DCFs, with weights proportional to risks associated with stochastic radiation-induced fatal health effects, as defined by Publication 26 of the International Commission on Radiological Protection (ICRP). This report derives and tabulates organ-specific dose conversion factors and the effective dose commitment per unit intake of tritium. These factors are based on a steady-state model of hydrogen in the tissues of ICRP's Reference Man (ICRP Publication 23) and equilibrium of specific activities between body water and other tissues. The results differ by 27 to 33% from the estimate on which ICRP Publication 30 recommendations are based. The report also examines a dynamic model of tritium retention in body water, mineral bone, and two compartments representing organically-bound hydrogen. This model is compared with data from human subjects who were observed for extended periods. The manner of combining the dose conversion factors with measured or model-predicted levels of contamination in man's exposure media (air, drinking water, soil moisture) to estimate dose rate to an individual is briefly discussed

The evaluation the magnitude radiation exposure dose rate in digital radiography room design

Science.gov (United States)

Dwiyanto, Agung; Setia Budi, Wahyu; Hardiman, Gagoek

2017-12-01

This study discusses the dose rate in digital radiography room, buit according to meet the provisions of KEMENKES No.1014 / Menkes / SK / XI / 2008 and Regulation of BAPETEN No. 8 / 2011. The provisions primary concern of radiation safety, not comfort, by considering the space design. There are five aspects to consider in designing the space: functionality, comfort, security, movement activities and aesthetics. However provisions only met three aspects of the design, which are a function, security and movement activity. Therefore, it is necessary to evaluate digital radiography room in terms of its ability to control external radiation exposure to be safe and comfortable The dose rate is measured by the range of primary and secondary radiation in the observation points by using Surveymeter. All data are obtained by the preliminary survey prior to the study. Furthermore, the review of digital radiography room is done based on architectural design theory. The dose rate for recommended improvement room is recalculated using the same method as the actual room with the help of computer modeling. The result of dose rate calculation at the inner and outer part of digital radiography observation room shows that in-room dose for a week at each measuring point exceeds the allowable dose limit both for staff and public. During a week of observation, the outdoor dose at some measuring points exceeds the dose limit set by the KEMENKES No.1014 / Menkes / SK / XI / 2008 and Regulation BEPETEN No 8/2011. Meanwhile, the result of dose rate calculation in the inner and outer part of the improved digital radiography room can meet the applicable regulations better.

Pediatric Obesity: Pharmacokinetic Alterations and Effects on Antimicrobial Dosing.

Science.gov (United States)

Natale, Stephanie; Bradley, John; Nguyen, William Huy; Tran, Tri; Ny, Pamela; La, Kirsten; Vivian, Eva; Le, Jennifer

2017-03-01

Limited data exist for appropriate drug dosing in obese children. This comprehensive review summarizes pharmacokinetic (PK) alterations that occur with age and obesity, and these effects on antimicrobial dosing. A thorough comparison of different measures of body weight and specific antimicrobial agents including cefazolin, cefepime, ceftazidime, daptomycin, doripenem, gentamicin, linezolid, meropenem, piperacillin-tazobactam, tobramycin, vancomycin, and voriconazole is presented. PubMed (1966-July 2015) and Cochrane Library searches were performed using these key terms: children, pharmacokinetic, obesity, overweight, body mass index, ideal body weight, lean body weight, body composition, and specific antimicrobial drugs. PK studies in obese children and, if necessary, data from adult studies were summarized. Knowledge of PK alterations stemming from physiologic changes that occur with age from the neonate to adolescent, as well as those that result from increased body fat, become an essential first step toward optimizing drug dosing in obese children. Excessive amounts of adipose tissue contribute significantly to body size, total body water content, and organ size and function that may modify drug distribution and clearance. PK studies that evaluated antimicrobial dosing primarily used total (or actual) body weight (TBW) for loading doses and TBW or adjusted body weight for maintenance doses, depending on the drugs' properties and dosing units. PK studies in obese children are imperative to elucidate drug distribution, clearance, and, consequently, the dose required for effective therapy in these children. Future studies should evaluate the effects of both age and obesity on drug dosing because the incidence of obesity is increasing in pediatric patients. © 2017 Pharmacotherapy Publications, Inc.

A limitation of the split-dose method for evaluating rCBF changes using 99mTc-ECD and SPECT

International Nuclear Information System (INIS)

Odano, Ikuo; Takahashi, Makoto; Noguchi, Eikichi; Ohtaki, Hiro; Shibaki, Mitsurou; Kasahara, Tosifumi; Hatano, Masayoshi; Ohkubo, Masaki.

1997-01-01

The purpose of the study is to validate the split-dose method corrected with dose ratio of 99m Tc-ECD for brain perfusion scan. A dose of 600 MBq of 99m Tc-ECD was divided into two with various dose ratios from 1 : 1 to 1 : 4, and injected to eleven patients with various cerebral diseases. A lesser dose of 99m Tc-ECD was injected under a control state for the first SPECT scan, and 15 min SPECT scan was performed 10 min after injection with a triple-head high resolution gamma camera. After the scan, the other dose of 99m Tc-ECD was injected under the same control state and the second SPECT scan was performed as same as above. A ratio of the activity of the first scan to the net activity of the second scan corrected by dose ratio, defined as K, was measured in brain regions of each subject. Expected value of K was 1, but the value was distributed with large variations in each subject. The mean % error of the K value was 10.4±4.9%. Hence it is considered that activity changes by more than 20% from the control values should be required to detect a significant rCBF change in an activation SPECT study. Then, we proposed a new method in which the activity of both two SPECT scans was normalized by cerebellar or occipital activity and compared. The ratio obtained by the proposed method came closer to 1 with less variations and with less mean % error in comparison with those of K value obtained by the dose-correction method. Although the proposed method has a limitation in the use of an activation study loaded with Diamox, it may be useful to evaluate an alteration of rCBF in the study such as postural testing or finger-moving test. (author)

75 FR 33818 - Nationwide Limited Public Interest Waiver of Section 1605 (Buy American Requirement) of American...

Science.gov (United States)

2010-06-15

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Indian Health Service Nationwide Limited Public Interest... Funds Provided Under ARRA AGENCY: Indian Health Service, HHS. ACTION: Notice. SUMMARY: The Indian Health... generally familiar with the conditions of availability, the potential alternatives for each detailed...

Risk from ionizing radiation to the clinical staff and incidental public in the course of therapy with I-131

International Nuclear Information System (INIS)

Chas, J.; Janiak, M.K.; Kowalczyk, A.; Siekierzynski, M.; Dziuk, E.

1997-01-01

The aim of the study was to assess the risk to the personnel and neighbouring patients exposed to ionizing radiation during their stay at the Isotopic Therapy Clinic in Warsaw where therapeutic applications of I-131 are routinely performed. To this end, thermoluminescent dosimeters were deposited in various places throughout the Clinical ward and the absorbed doses were read after 125 days of the exposition. Additionally, exposure dose rates were determined at the skin surface over the thyroid gland at 0.5 and 1.0 m away from 71 patients treated with I-131 for hyperthyroidism or thyroid cancer (as a supplementary therapy after thyroidectomy) and the potential dose equivalents were calculated. From these values ''restriction times'', i.e., the amounts of time needed for the potential dose equivalents to decline below the limit recommended for occupational or public exposures to ionizing radiation were derived. The results indicate that - a) the probability to exceed the recommended annual dose limit by the personnel (50 mSv y -1 ) and neighbouring patients not subjected to radiotherapy (1 mSv y -1 ) during their exposition at the Isotopic Therapy Clinic to the I-131 treated patients is practically equal to zero; b) no restrictions in terms of limiting the duration of contact with the I-131-treated patients are necessary during the occupational exposures of the personnel of the Clinic; and c) the treated patients may incur some risk to the general public only when injected with high doses of I-131 and/or only within about 3 days upon the application of the radionuclide. (author)

Image quality evaluation and patient dose assessment of medical fluoroscopic X-ray systems: A national study

International Nuclear Information System (INIS)

Economides, S.; Hourdakis, C. J.; Kalivas, N.; Kalathaki, M.; Simantirakis, G.; Tritakis, P.; Manousaridis, G.; Vogiatzi, S.; Kipouros, P.; Boziari, A.; Kamenopoulou, V.

2008-01-01

This study presents the results from a survey conducted by the Greek Atomic Energy Commission (GAEC), during the period 1998-2003, in 530 public and private owned fluoroscopic X-ray systems in Greece. Certain operational parameters for conventional and remote control systems were assessed, according to a quality control protocol developed by GAEC on the basis of the current literature. Public (91.5%) and private (81.5%) owned fluoroscopic units exhibit high-contrast resolution values over 1 lp mm -1 . Moreover, 88.5 and 87.1% of the fluoroscopic units installed in the public and private sector, respectively, present Maximum Patient Entrance Kerma Rate values lower than 100 mGy min -1 . Additionally, 68.3% of the units assessed were found to perform within the acceptance limits. Finally, the third quartile of the Entrance Surface Dose Rate distribution was estimated according to the Dose Reference Level definition and found equal to 35 mGy min -1 . (authors)

Measurement of natural radioactivity in Jordanian building materials and their contribution to the public indoor gamma dose rate.

Science.gov (United States)

Sharaf, J M; Hamideen, M S

2013-10-01

This study is undertaken to determine the activity concentration of (226)Ra, (232)Th and (40)K in samples of commonly used building materials in Jordan. Samples of seven different materials were collected from construction sites and local agencies supplying raw construction materials and analyzed using a HPGe gamma-ray spectrometer, taking into account self-attenuation in bulk samples. The average specific activity concentrations of (226)Ra, (232)Th, and (40)K ranged from 2.84 to 41.52, 0.78 to 58.42. and 3.74 to 897 Bq/kg, respectively. All the samples had radium equivalent activities well below the limit of 370 Bq/kg set by the Organization for Economic Cooperation and Development (OECD, 1979). External and internal hazard indices, absorbed dose and annual effective dose rate associated with the radionuclides of interest were calculated and compared with the international legislation and guidance. In general, most of the activities did not exceed the recommended international limits, except for granite and ceramic samples which are usually used as secondary building materials in Jordan. Copyright © 2013 Elsevier Ltd. All rights reserved.

Dose constraints in paediatric radiotherapy; Contraintes de dose en radiotherapie pediatrique

Energy Technology Data Exchange (ETDEWEB)

Bernier, V. [Groupe de radiotherapie pediatrique SFCE, Centre Alexis-Vautrin, 54 - Nancy (France)

2010-10-15

The author discusses the issue of dose constraints for organs at risk when performing paediatric radiotherapy, and outlines that this issue is only partially resolved by the QUANTEC publication (quantitative estimates of normal tissue effects in the clinic). Then, he presents a guide elaborated by the French group of paediatric radiotherapists. This guide reviews organs at risk, imagery delineation requirements, dose constraints and short-, medium- and long-term consequences of organ irradiation. Short communication

Radiation protection limits and review procedure

International Nuclear Information System (INIS)

Dafauti, Sunita; Gopalakrishnan, R.K.; Pradeepkumar, K.S.

2017-01-01

The primary means of controlling radiation exposure in planned exposure situations in nuclear facilities/radiological laboratories are by good design of facilities, equipment, operating procedures and by ensuring appropriate training to all plant occupational workers. In planned exposure situations, exposure at some level can be expected to occur. For planned exposure situations, exposures are subject to control for ensuring that the specified dose limits for occupational exposure and those for public exposure are not exceeded and optimization is applied to attain the desired level of protection and safety. The person or organization responsible for any facility or activity that gives rise to radiation exposure should have the prime responsibility for protection and safety, which cannot be delegated

75 FR 65010 - Nationwide Limited Public Interest Waiver Under Section 1605 (Buy American) of the American...

Science.gov (United States)

2010-10-21

... intellectual content and dollar-value items associated with solar PV energy generation. The Buy American...)(ii)]. However, determining where final manufacturing occurs in the context of the solar production... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Nationwide Limited Public...

Procedures, activities and doses in nuclear medicine cycle in Brazil

International Nuclear Information System (INIS)

Oliveira, Silvia Maria Velasques de

2005-01-01

With the aim of characterizing nuclear medicine procedures performed in Brazil, activities of radiopharmaceuticals used and effective doses to patients, data was collected from nuclear medicine institutions in three regions of the country, namely the Southeast, the Northeast and the South regions, representing public hospitals, university hospitals, private and philanthropic institutions with low, medium and high levels of consumption of radiopharmaceuticals. The three chosen regions are responsible for 92% of radiopharmaceutical consumption and imaging equipment in the country. Accordingly, it was requested of some participating institutions to fulfill manually from individual patients data, to record gender, age, weight, height and activities used, for each type of exam as well as the equipment used. In others, the researcher collected data personally. Per institution, nuclear medicine diagnostic procedures ranged from 700 to 13,000 per year, most of which are myocardial and bone imaging procedures, and imaging equipment ranged, from 1 to 8 machines, one or two head SPECT's (hybrid or not). 26.782 patients protocols were analysed, 24.371 adults and 2.411 children and teenagers. For adult patients, differences were observed in the amount of activities used in diagnostic procedures between public and private institutions, with lower average activities used in public institutions. Activities administered to children and their effective doses were difficult to evaluate due to the incompleteness of individual records. Appropriate individual patient records could be adopted without affecting hospitals routine and contributing for a comprehensive evaluation of the radiation protection of nuclear medicine patients. Data from 8.881 workers were analysed, 346 working at nuclear medicine institutions. For monitored workers and measurably exposed workers in nuclear medicine, the values 2.3 mSv and 5.4 mSv, respectively, for effective annual doses are greater than data

Implications in dosimetry of the implementation of the revised dose limit to the lens of the eye

International Nuclear Information System (INIS)

Broughton, J.; Shah, B.; Cantone, M.C.; Ginjaume, M.; Czarwinski, R.

2015-01-01

In 2012, International Radiation Protection Association (IRPA) established a Task Group to provide an assessment of the impact of the implementation of the ICRP-revised dose limit for the lens of the eye for occupational exposure. Associated Societies (ASs) of IRPA were asked to provide views and comments on the basis of a questionnaire addressing three principal topics: (i) implications for dosimetry, (ii) implications for methods of protection and (iii) wider implications of implementing the revised limits. A summary of the collated responses regarding dosimetry is presented and discussed. There is large agreement on the most critical aspects and difficulties in setting up an appropriate monitoring programme for the lens of the eyes. The recent international standards and technical documents provide guidance for some of the concerns but other challenges remain in terms of awareness, acceptance and practicalities. (authors)

Radiation by the numbers: developing an on-line Canadian radiation dose calculator as a public engagement and education tool

Energy Technology Data Exchange (ETDEWEB)

Dalzell, M.T.J. [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, Saskatchewan (Canada)

2016-06-15

Concerns arising from misunderstandings about radiation are often cited as a main reason for public antipathy towards nuclear development and impede decision-making by governments and individuals. A lack of information about everyday sources of radiation exposure that is accessible, relatable and factual contributes to the problem. As part of its efforts to be a fact-based source of information on nuclear issues, the Sylvia Fedoruk Canadian Centre for Nuclear Innovation has developed an on-line Canadian Radiation Dose Calculator as a tool to provide context about common sources of radiation. This paper discusses the development of the calculator and describes how the Fedoruk Centre is using it and other tools to support public engagement on nuclear topics. (author)

Use of radiobiological indices to guide dose escalation of the prostate cancer patients

International Nuclear Information System (INIS)

Burman, Chandra; Happersett, Laura; Kutcher, Gerald; Leibel, Steven; Zelefsky, Michael; Fuks, Zvi; Ling, C. Clifton

1997-01-01

Purpose: In the radiation treatment of localized prostate carcinoma, a portion of the anterior rectal wall is included in the planning target volume (PTV). Thus, in dose escalation studies, radiation induced rectal complication may limit the dose that can be delivered safely. In this study we investigate the potential of increasing tumor control without increasing rectal complication by limiting the rectal volume receiving the high prescription dose. The evaluation is with the aid of radiobiological indices. Methods and Materials: Two types of 3D conformal treatment plans were performed for a group of ten patients, for prescription doses of 75.6 to 95.0 Gy. Type I plan involved 6 fields (2 lateral, 2 anterior oblique and 2 posterior oblique), with the dose prescribed to the maximum isodose line encompassing the PTV. Type II plan comprised a primary treatment (using the 6 fields of the first plan) of 72 Gy to the PTV, and a boost with 6 posterior obliques to deliver the additional dose, except to the portion of the rectal wall included by the PTV. Based on the composite 3D dose distribution, TCP and rectal NTCP were calculated with the Goitein and Lyman models, respectively, using parameters derived from our clinical experience and from the 1991 NCI Collaborating Work Group publication. Results: In the figure, the calculated values of TCP, NTCP and TCP * [1-NTCP] (or uncomplicated control), averaged over the 10 patients, are plotted against the prescription dose. The dotted and solid lines are for type I (with uniform PTV dose) and type II (with reduction in rectal dose for the boost) plans, respectively, and the error bars represent the range of computed values for the 10 patients. For type I plans, the increase in TCP, from 75% at 75.6 Gy to 98% at 95 Gy, must be balanced against the rise in rectal NTCP to >20%. The TCP for type II plan is slightly less, but with little increase in NTCP with prescription dose. Thus, the uncomplicated control continues to increase

Comodore V2007: assessment doses for the public from atmospheric and liquid discharges

International Nuclear Information System (INIS)

Devin, Patrick; Kerouanton, David; Delgove, Laure; Giordanetto, Anne; Petit, Jany; Perrier, Gilles; Brun, Frederic; Garnier, Francois; Bernard, Christophe

2008-01-01

Protecting the environment and the public from radioactive hazard is a top priority for all companies operating in the nuclear domain. In order to quantify dose impact on members of the public due to annual discharges of its nuclear installations, AREVA developed the COMODORE code in collaboration with Institute of Radiation Protection and Nuclear Safety (IRSN). COMODORE is a synthesis of 3 software validated by IRSN (ACADIE, COTRAM and AQUAREJ). ACADIE is a code elaborated by IRSN and the Treatment Business Unit of AREVA synthesizing the works of the GRNC (Nord-Cotentin Radioecology Group) created by the French government to deal with the estimation of exposure levels to ionizing radiation and associated risks of leukemia for populations in the Nord-Cotentin. COMODORE is a version of ACADIE designed to be adaptable to any other AREVA site. Thus, the operators of the south east of France (Pierrelatte, Marcoule and Romans sites) carried out the adaptation of COMODORE for theirs specificities (for instance, uranium in the terrestrial model). At the moment, COMODORE is used in routine by the AREVA operators to assess the annual dosimetric impact and is also being adapted with SGN to model the radiological impact of uranium ore treatment residues repositories. This tool contributes to the transparency by giving stake holders environmental data they need. (author)

Publication ethics from the perspective of PhD students of health sciences: a limited experience.

Science.gov (United States)

Arda, Berna

2012-06-01

Publication ethics, an important subtopic of science ethics, deals with determination of the misconducts of science in performing research or in the dissemination of ideas, data and products. Science, the main features of which are secure, reliable and ethically obtained data, plays a major role in shaping the society. As long as science maintains its quality by being based on reliable and ethically obtained data, it will be possible to maintain its role in shaping the society. This article is devoted to the presentation of opinions of PhD candidate students in health sciences in Ankara concerning publication ethics. The data obtained from 143 PhD students from the fields of medicine, dentistry, pharmacy and veterinary reveal limited but unique experiences. It also shows that plagiarism is one of the worst issues in the publication ethics from the perspective of these young academics.

Detection limits of absorbed dose of ionizing radiation in molluscan shells as determined by e.p.r. spectroscopy

International Nuclear Information System (INIS)

Stachowicz, W.; Michalik, J.; Burlinska, G.; Sadlo, J.; Dziedzic-Goclawska, A.; Ostrowski, K.

1995-01-01

The exposure of waters to ionizing radiation from radionuclides imprisoned in dumped nuclear waste containers, freed in nuclear submarine accidents or released in underwater magma eruptions are difficult to be evaluated by conventional radiometric methods. Ionizing radiation evokes stable paramagnetic centers in crystalline lattice of mineral components in bone skeletons of mammals and fishes as well as in exoskeletons of mollusca. They give rise in e.p.r. to specific, extremely stable signals which are proposed to be applied as indicators of radiation exposure levels. In the present study the e.p.r. detection limits of the dose of ionizing radiation absorbed in shells of fresh water and marine mollusca (selected species) have been estimated. It has been found that with fresh water mollusca the dose of 1-2 Gy can be detected, while the sea water mollusca by one order of magnitude lower, i.e. about 0.1 Gy. (author)

What is correct: equivalent dose or dose equivalent

International Nuclear Information System (INIS)

Franic, Z.

1994-01-01

In Croatian language some physical quantities in radiation protection dosimetry have not precise names. Consequently, in practice either terms in English or mathematical formulas are used. The situation is even worse since the Croatian language only a limited number of textbooks, reference books and other papers are available. This paper compares the concept of ''dose equivalent'' as outlined in International Commission on Radiological Protection (ICRP) recommendations No. 26 and newest, conceptually different concept of ''equivalent dose'' which is introduced in ICRP 60. It was found out that Croatian terminology is both not uniform and unprecise. For the term ''dose equivalent'' was, under influence of Russian and Serbian languages, often used as term ''equivalent dose'' even from the point of view of ICRP 26 recommendations, which was not justified. Unfortunately, even now, in Croatia the legal unit still ''dose equivalent'' defined as in ICRP 26, but the term used for it is ''equivalent dose''. Therefore, in Croatian legislation a modified set of quantities introduced in ICRP 60, should be incorporated as soon as possible

Analysis of workers' dose records from the Greek Dose Registry Information System

International Nuclear Information System (INIS)

Kamenopoulou, V.; Dimitriou, P.; Proukakis, Ch.

1995-01-01

The object of this work is the study of the individual film badge annual dose information of classified workers in Greece, monitored and assessed by the central dosimetry service of the Greek Atomic Energy Commission. Dose summaries were recorded and processed by the Dose Registry Information System. The statistical analysis refers to the years 1989-93 and deals with the distribution of individuals in the occupational groups, the mean annual dose, the collective dose, the distribution of the dose over the different specialties and the number of workers that have exceeded any of the established dose limits. Results concerning the annual dose summaries, demonstrate a year-by-year reduction in the mean individual dose to workers in the health sector. Conversely, exposures in the industrial sector did not show any decreasing tendency during the period under consideration. (Author)

Determination of organ doses and effective doses in radiooncology

International Nuclear Information System (INIS)

Roth, J.; Martinez, A.E.

2007-01-01

Background and Purpose: With an increasing chance of success in radiooncology, it is necessary to estimate the risk from radiation scatter to areas outside the target volume. The cancer risk from a radiation treatment can be estimated from the organ doses, allowing a somewhat limited effective dose to be estimated and compared. Material and Methods: The doses of the radiation-sensitive organs outside the target volume can be estimated with the aid of the PC program PERIDOSE developed by van der Giessen. The effective doses are determined according to the concept of ICRP, whereby the target volume and the associated organs related to it are not taken into consideration. Results: Organ doses outside the target volume are generally < 1% of the dose in the target volume. In some cases, however, they can be as high as 3%. The effective doses during radiotherapy are between 60 and 900 mSv, depending upon the specific target volume, the applied treatment technique, and the given dose in the ICRU point. Conclusion: For the estimation of the radiation risk, organ doses in radiooncology can be calculated with the aid of the PC program PERIDOSE. While evaluating the radiation risk after ICRP, for the calculation of the effective dose, the advanced age of many patients has to be considered to prevent that, e.g., the high gonad doses do not overestimate the effective dose. (orig.)

Background radiation dose of dumpsites in Ota and Environs

Science.gov (United States)

Usikalu, M. R.; Ola, O. O.; Achuka, J. A.; Babarimisa, I. O.; Ayara, W. A.

2017-05-01

In-situ measurement of background radiation dose from selected dumpsites in Ota and its environs was done using Radialert Nuclear Radiation Monitor (Digilert 200). Ten measurements were taken from each dumpsite. The measured background radiation range between 0.015 mRhr-1 for AOD and 0.028 mRhr-1 for SUS dumpsites. The calculated annual equivalent doses vary between 1.31 mSvyr-1 for AOD and 2.28 mSv/yr for SUS dumpsites. The air absorbed dose calculated ranged from 150 nGyhr-1 to 280 nGy/hr for AOD and SUS dumpsites respectively with an average value of 217 nGyhr-1 for all the locations. All the estimated parameters were higher than permissible limit set for background radiation for the general public. Conclusively, the associated challenge and radiation burden posed by the wastes on the studied locations and scavengers is high. Therefore, there is need by the regulatory authorities to look into the way and how waste can be properly managed so as to alleviate the effects on the populace leaving and working in the dumpsites vicinity.

Concept and approaches used in assessing individual and collective doses from releases of radioactive effluents

International Nuclear Information System (INIS)

1988-06-01

To guide on the applications of the principles for limiting radioactive releases contained in Safety Series 77, the Agency is in the process of preparing a number of safety guides. The first one is this present document which deals with the principal aspects of the methods for the assessment of the individual and collective dose. It aims at giving a general guidance to those responsible for establishing programmes for the determination of individual doses as well as collective doses in connection with licensing a site for a nuclear installation. The document is concerned with the principles applied for calculating individual and collective doses from routine releases of radionuclides to the atmosphere and hydrosphere but not releases directly to the geosphere, as in waste management. These areas will be covered by other Agency publications. 75 refs, figs and tabs

Reference computations of public dose and cancer risk from airborne releases of plutonium. Nuclear safety technical report

Energy Technology Data Exchange (ETDEWEB)

Peterson, V.L.

1993-12-23

This report presents results of computations of doses and the associated health risks of postulated accidental atmospheric releases from the Rocky Flats Plant (RFP) of one gram of weapons-grade plutonium in a form that is respirable. These computations are intended to be reference computations that can be used to evaluate a variety of accident scenarios by scaling the dose and health risk results presented here according to the amount of plutonium postulated to be released, instead of repeating the computations for each scenario. The MACCS2 code has been used as the basis of these computations. The basis and capabilities of MACCS2 are summarized, the parameters used in the evaluations are discussed, and results are presented for the doses and health risks to the public, both the Maximum Offsite Individual (a maximally exposed individual at or beyond the plant boundaries) and the population within 50 miles of RFP. A number of different weather scenarios are evaluated, including constant weather conditions and observed weather for 1990, 1991, and 1992. The isotopic mix of weapons-grade plutonium will change as it ages, the {sup 241}Pu decaying into {sup 241}Am. The {sup 241}Am reaches a peak concentration after about 72 years. The doses to the bone surface, liver, and whole body will increase slightly but the dose to the lungs will decrease slightly. The overall cancer risk will show almost no change over this period. This change in cancer risk is much smaller than the year-to-year variations in cancer risk due to weather. Finally, x/Q values are also presented for other applications, such as for hazardous chemical releases. These include the x/Q values for the MOI, for a collocated worker at 100 meters downwind of an accident site, and the x/Q value integrated over the population out to 50 miles.

Estimation of the contribution of neutrons to the equivalent dose for personnel occupationally exposed and public in medical facilities: X-ray with energy equal or greater than 10MV

International Nuclear Information System (INIS)

Gonzalez, Alfonso Mayer; Jimenez, Roberto Ortega; Sanchez, Mario A. Reyes; Moranchel y Mejia, Mario

2013-01-01

In Mexico the use of electron accelerators for treating cancerous tumors had grown enormously in the last decade. When the treatments are carried out with X-ray beam energy below 10 MV the design of the shielding of the radioactive facility is determined by analyzing the interaction of X-rays, which have a direct impact and dispersion, with materials of the facility. However, when it makes use of X-ray beam energy equal to or greater than 10 MV the neutrons presence is imminent due to their generation by the interaction of the primary beam X-ray with materials head of the accelerator and of the table of treatment, mainly. In these cases, the design and calculation of shielding considers the generation of high-energy neutrons which contribute the equivalent dose that public and Occupationally Staff Exposed (POE) will receive in the areas surrounding the facility radioactive. However, very few measurements have been performed to determine the actual contribution to the neutron dose equivalent received by POE and public during working hours. This paper presents an estimate of the actual contribution of the neutron dose equivalent received by public and POE facilities in various radioactive medical use, considering many factors. To this end, measurements were made of the equivalent dose by using a neutron monitor in areas surrounding different radioactive installations (of Mexico) which used electron accelerators medical use during treatment with X-ray beam energy equal to or greater than 10 MV. The results are presented after a statistical analysis of a wide range of measures in order to estimate more reliability real contribution of the neutron dose equivalent for POE and the public. (author)

Geologic disposal of spent nuclear fuel and nuclear waste: Ethical and technical bases for standards and criteria to protect public health

International Nuclear Information System (INIS)

Pigford, T.H.

1999-01-01

The proposed geologic repositories being designed in the US and in other countries that have nuclear power plants need well-defined goals and criteria to protect public health. The criteria must be stringent enough to build confidence in the adequacy of public health protection in the face of legal and political challenges. Yet, there are emerging pressures for relaxation of traditional approaches to protect public health when applied to buried radioactive waste. To build acceptance by the scientific community and the public, both the benefits and consequences of proposed relaxed standards must be dealt with openly and understandably. Arguments over safety standards center on six key issues. (1) For how long must public health protection be assured? Should protection be based on calculated radiation doses to people living for many tens of thousands of years in the future, until peak values of calculated radiation have appeared, or should the protection period be limited to a few thousand years? (2) Whom to protect? Should protection be based on protecting the critical group of future people who unknowingly eat food and drink water contaminated by released radioactivity or should it be based on limiting the average exposure, averaged over all persons projected to live within 'the vicinity' of the repository site? (3) How much radiation exposure should be allowed? Should future people be protected to the same level of radiation exposure as now required for licensed nuclear facilities, or should greater exposures be allowed because future people might be better protected by medical breakthroughs or by their taking remedial action to detect and clean up radioactivity that reaches the environment? (4) Can future people be excluded from using contaminated water drawn from near the site? Should protection of future people be based on doses calculated for ground water extracted from present farming wells, where distance and dilution resulted in lower calculated contaminant

Job-related doses in light water reactors

International Nuclear Information System (INIS)

Schnuer, K.

1993-01-01

The Treaty of 1957 establishing the European Atomic Energy Community, (EURATOM) was an essential prerequisite for the development of a strong nuclear industry in Europe. Among other things the Treaty provides that the Community shall lay down Basic Safety Standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation and ensure that they are applied. Following adoption of the Council Directive of 1980, the European Commission defined the basic principles of Justification, Optimization and Limitation to be applied in order to ensure the greatest possible protection of workers and the general public. Subsequently the Commission took initiatives in order to find ways of implementing these three basic principles in practical radiation protection. In 1980 the Commission in close collaboration with the leading nuclear power station operators, set up its own system of 'occupational radiation dose statistics from light water reactors operating in Western Europe'. This was designed for PWRs and BWRs, and the Commission benefited from the experience of neighbouring non-EC countries such as Sweden, Finland, Switzerland and Spain (not yet a member) operating nuclear power stations made by different manufacturers. The paper provides some general information on developments and trends in collective and individual doses to workers in nuclear power stations, based on a unique European databank of approximately 1000 operating reactor years. 9 figs

Savannah River Site dose control

International Nuclear Information System (INIS)

Smith, L.S.

1992-01-01

Health physicists from the Brookhaven National Laboratory (BNL) visited the Savannah River Site (SRS) as one of 12 facilities operated by the Department of Energy (DOE) contractors with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). Their charter was to review, evaluate and summarize as low as reasonably achievable (ALARA) techniques, methods and practices as implemented. This presentation gives an overview of the two selected ALARA practices implemented at the SRS: Administrative Exposure Limits and Goal Setting. These dose control methods are used to assure that individual and collective occupational doses are ALARA and within regulatory limits

Effective dose: a radiation protection quantity

CERN Document Server

Menzel, H G

2012-01-01

Modern radiation protection is based on the principles of justification, limitation, and optimisation. Assessment of radiation risks for individuals or groups of individuals is, however, not a primary objective of radiological protection. The implementation of the principles of limitation and optimisation requires an appropriate quantification of radiation exposure. The International Commission on Radiological Protection (ICRP) has introduced effective dose as the principal radiological protection quantity to be used for setting and controlling dose limits for stochastic effects in the regulatory context, and for the practical implementation of the optimisation principle. Effective dose is the tissue weighted sum of radiation weighted organ and tissue doses of a reference person from exposure to external irradiations and internal emitters. The specific normalised values of tissue weighting factors are defined by ICRP for individual tissues, and used as an approximate age- and sex-averaged representation of th...

Establishment of detailed eye model of adult chinese male and dose conversion coefficients calculation under neutron exposure

International Nuclear Information System (INIS)

Zhu, Hongyu; Qiu, Rui; Ren, Li; Zhang, Hui; Li, Junli; Wu, Zhen; Li, Chunyan

2017-01-01

The human eye lens is sensitive to radiation. ICRP-118 publication recommended a reduction of the occupational annual equivalent dose limit from 150 to 20 mSv, averaged over defined periods of 5 y. Therefore, it is very important to build a detailed eye model for the accurate dose assessment and radiation risk evaluation of eye lens. In this work, a detailed eye model was build based on the characteristic anatomic parameters of the Chinese adult male. This eye model includes seven main structures, which are scleral, choroid, lens, iris, cornea, vitreous body and aqueous humor. The lens was divided into sensitive volume and insensitive volume based on different cell populations. The detailed eye model was incorporated into the converted polygon-mesh version of the Chinese reference adult male whole-body surface model. After the incorporation, dose conversion coefficients for the eye lens were calculated for neutron exposure at AP, PA and LAT geometries with Geant4, the neutron energies were from 0.001 eV to 10 MeV. The calculated lens dose coefficients were compared with those of ICRP-116 publication. Significant differences up to 97.47% were found at PA geometry. This could mainly be attributed to the different geometry characteristic of eye model and parameters of head in different phantom between the present work and ICRP-116 publication. (authors)