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Simon SL, Bouville A, Beck HL, Anspaugh LR, Thiessen KM, Hoffman FO, Shinkarev S. Dose Estimation for Exposure to Radioactive Fallout from Nuclear Detonations. HEALTH PHYSICS 2022; 122:1-20. [PMID: 34898514 PMCID: PMC8677604 DOI: 10.1097/hp.0000000000001501] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/05/2023]
Abstract
ABSTRACT In recent years, the prospects that a nuclear device might be detonated due to a regional or global political conflict, by violation of present nuclear weapons test ban agreements, or due to an act of terrorism, has increased. Thus, the need exists for a well conceptualized, well described, and internally consistent methodology for dose estimation that takes full advantage of the experience gained over the last 70 y in both measurement technology and dose assessment methodology. Here, the models, rationale, and data needed for a detailed state-of-the-art dose assessment for exposure to radioactive fallout from nuclear detonations discussed in five companion papers are summarized. These five papers present methods and data for estimating radionuclide deposition of fallout radionuclides, internal and external dose from the deposited fallout, and discussion of the uncertainties in the assessed doses. In addition, this paper includes a brief discussion of secondary issues related to assessments of radiation dose from fallout. The intention of this work is to provide a usable and consistent methodology for both prospective and retrospective assessments of exposure from radioactive fallout from a nuclear detonation.
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Affiliation(s)
- Steven L. Simon
- National Cancer Institute, National Institutes of Health, Bethesda, MD
| | - André Bouville
- National Cancer Institute, National Institutes of Health, Bethesda, MD (retired)
| | | | - Lynn R. Anspaugh
- Department of Radiology, University of Utah (Emeritus), Henderson, NV
| | | | | | - Sergey Shinkarev
- State Research Center-Burnasyan Federal Medical Biophysical Center, Federal Medical Biological Agency, Moscow, Russian Federation
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Giussani A, Lopez MA, Romm H, Testa A, Ainsbury EA, Degteva M, Della Monaca S, Etherington G, Fattibene P, Güclu I, Jaworska A, Lloyd DC, Malátová I, McComish S, Melo D, Osko J, Rojo A, Roch-Lefevre S, Roy L, Shishkina E, Sotnik N, Tolmachev SY, Wieser A, Woda C, Youngman M. Eurados review of retrospective dosimetry techniques for internal exposures to ionising radiation and their applications. RADIATION AND ENVIRONMENTAL BIOPHYSICS 2020; 59:357-387. [PMID: 32372284 PMCID: PMC7369133 DOI: 10.1007/s00411-020-00845-y] [Citation(s) in RCA: 11] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 11/08/2019] [Accepted: 04/15/2020] [Indexed: 05/17/2023]
Abstract
This work presents an overview of the applications of retrospective dosimetry techniques in case of incorporation of radionuclides. The fact that internal exposures are characterized by a spatially inhomogeneous irradiation of the body, which is potentially prolonged over large periods and variable over time, is particularly problematic for biological and electron paramagnetic resonance (EPR) dosimetry methods when compared with external exposures. The paper gives initially specific information about internal dosimetry methods, the most common cytogenetic techniques used in biological dosimetry and EPR dosimetry applied to tooth enamel. Based on real-case scenarios, dose estimates obtained from bioassay data as well as with biological and/or EPR dosimetry are compared and critically discussed. In most of the scenarios presented, concomitant external exposures were responsible for the greater portion of the received dose. As no assay is available which can discriminate between radiation of different types and different LETs on the basis of the type of damage induced, it is not possible to infer from these studies specific conclusions valid for incorporated radionuclides alone. The biological dosimetry assays and EPR techniques proved to be most applicable in cases when the radionuclides are almost homogeneously distributed in the body. No compelling evidence was obtained in other cases of extremely inhomogeneous distribution. Retrospective dosimetry needs to be optimized and further developed in order to be able to deal with real exposure cases, where a mixture of both external and internal exposures will be encountered most of the times.
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Affiliation(s)
- A Giussani
- BfS-Bundesamt für Strahlenschutz, Ingolstädter Landstr. 1, 85764, Oberschleißheim, Germany.
| | - M A Lopez
- CIEMAT - Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Av.da Complutense 40, 28040, Madrid, Spain
| | - H Romm
- BfS-Bundesamt für Strahlenschutz, Ingolstädter Landstr. 1, 85764, Oberschleißheim, Germany
| | - A Testa
- ENEA Casaccia Research Center, Via Anguillarese 301, Santa Maria di Galeria, 00123, Rome, Italy
| | - E A Ainsbury
- Public Health England - Centre for Radiation, Chemical and Environmental Hazards, Chilton, Didcot, OX11 0RQ, Oxon, UK
| | - M Degteva
- Urals Research Center for Radiation Medicine (URCRM), Vorovskt str. 68A, Chelyabinsk, 454141, Russia
| | - S Della Monaca
- Istituto Superiore di Sanità, Viale Regina Elena 299, 00161, Rome, Italy
| | - G Etherington
- Public Health England - Centre for Radiation, Chemical and Environmental Hazards, Chilton, Didcot, OX11 0RQ, Oxon, UK
| | - P Fattibene
- Istituto Superiore di Sanità, Viale Regina Elena 299, 00161, Rome, Italy
| | - I Güclu
- Cekmece Nuclear Research and Training Center Radiobiology Unit Yarımburgaz, Turkish Atomic Energy Authority, Istanbul, Turkey
| | - A Jaworska
- DSA-Norwegian Radiation and Nuclear Safety Authority, Skøyen, P. O. Box 329, 0213, Oslo, Norway
| | - D C Lloyd
- Public Health England - Centre for Radiation, Chemical and Environmental Hazards, Chilton, Didcot, OX11 0RQ, Oxon, UK
| | - I Malátová
- SURO-National Radiation Protection Institute, Bartoskova 28, 14000, Prague, Czech Republic
| | - S McComish
- US Transuranium and Uranium Registries, Washington State University, Richland, WA, USA
| | - D Melo
- Melohill Technology, 1 Research Court, Rockville, MD, 20850, USA
| | - J Osko
- National Centre for Nuclear Research, A. Soltana 7, 05400, Otwock, Poland
| | - A Rojo
- ARN-Nuclear Regulatory Authority of Argentina, Av. del Libertador 8250, Buenos Aires, Argentina
| | - S Roch-Lefevre
- Institut de Radioprotection et de Sûreté Nucléaire, IRSN, Pôle Santé et Environnement, Direction de la Santé, Fontenay-aux-Roses, France
| | - L Roy
- Institut de Radioprotection et de Sûreté Nucléaire, IRSN, Pôle Santé et Environnement, Direction de la Santé, Fontenay-aux-Roses, France
| | - E Shishkina
- Urals Research Center for Radiation Medicine (URCRM), Vorovskt str. 68A, Chelyabinsk, 454141, Russia
- Chelyabinsk State University (ChelSU), 129, Bratiev Kashirinih Street, Chelyabinsk, 454001, Russia
| | - N Sotnik
- Southern Urals Biophysics Institute (SUBI), Ozyorsk, Chelyabinsk Region, 456780, Russia
| | - S Y Tolmachev
- US Transuranium and Uranium Registries, Washington State University, Richland, WA, USA
| | - A Wieser
- Institute of Radiation Medicine, Helmholtz Zentrum München, Ingolstädter Landstr. 1, 85764, Neuherberg, Germany
| | - C Woda
- Institute of Radiation Medicine, Helmholtz Zentrum München, Ingolstädter Landstr. 1, 85764, Neuherberg, Germany
| | - M Youngman
- Public Health England - Centre for Radiation, Chemical and Environmental Hazards, Chilton, Didcot, OX11 0RQ, Oxon, UK
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Toyoda S, Murahashi M, Ivannikov A. ESR tooth enamel retrospective dosimetry quoted as spin numbers. RADIAT MEAS 2020. [DOI: 10.1016/j.radmeas.2020.106333] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Zhumadilov KS, Ivannikov AI, Stepanenko VF, Toyoda S, Skvortsov VG, Hoshi M. EPR DOSIMETRY STUDY FOR POPULATION RESIDING IN THE VICINITY OF FALLOUT TRACE FOR NUCLEAR TEST ON 7 AUGUST 1962. RADIATION PROTECTION DOSIMETRY 2016; 172:260-264. [PMID: 27473700 DOI: 10.1093/rpd/ncw178] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/06/2023]
Abstract
The method of electron paramagnetic resonance (EPR) dosimetry using extracted teeth has been applied to human tooth enamel to obtain individual absorbed doses of residents of settlements in the vicinity of the central axis of radioactive fallout trace from the contaminating surface nuclear test on 7 August 1962. Most of the settlements (Kurchatov, Akzhar, Begen, Buras, Grachi, Mayskoe, Semenovka) are located from 70 to 120 km to the North-East from the epicenter of the explosion at the Semipalatinsk Nuclear Test Site (SNTS). This region is basically an agricultural region. A total of 57 teeth samples were collected from these sites. Eight teeth from residents of the Kokpekty settlement, which was not subjected to any radioactive contamination and located 400 km to the Southeast from SNTS, were chosen as a control. The principal findings, using this method, were that the average excess dose obtained after subtraction of the natural background radiation was 13 mGy and ranged up to about 100 mGy all for residents in this region.
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Affiliation(s)
- Kassym Sh Zhumadilov
- L.N. Gumilyov Eurasian National University, Munaitpasova Str.,13, Astana 010008, Kazakhstan
| | | | | | - Shin Toyoda
- Department of Applied Physics Faculty of Science Okayama University of Science , 700-0005, Japan
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Bailiff I, Sholom S, McKeever S. Retrospective and emergency dosimetry in response to radiological incidents and nuclear mass-casualty events: A review. RADIAT MEAS 2016. [DOI: 10.1016/j.radmeas.2016.09.004] [Citation(s) in RCA: 56] [Impact Index Per Article: 7.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/09/2023]
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Land CE, Kwon D, Hoffman FO, Moroz B, Drozdovitch V, Bouville A, Beck H, Luckyanov N, Weinstock RM, Simon SL. Accounting for shared and unshared dosimetric uncertainties in the dose response for ultrasound-detected thyroid nodules after exposure to radioactive fallout. Radiat Res 2015; 183:159-173. [PMID: 25574587 PMCID: PMC4423551 DOI: 10.1667/rr13794.1] [Citation(s) in RCA: 46] [Impact Index Per Article: 5.1] [Reference Citation Analysis] [Abstract] [MESH Headings] [Grants] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/03/2022]
Abstract
Dosimetic uncertainties, particularly those that are shared among subgroups of a study population, can bias, distort or reduce the slope or significance of a dose response. Exposure estimates in studies of health risks from environmental radiation exposures are generally highly uncertain and thus, susceptible to these methodological limitations. An analysis was published in 2008 concerning radiation-related thyroid nodule prevalence in a study population of 2,994 villagers under the age of 21 years old between August 1949 and September 1962 and who lived downwind from the Semipalatinsk Nuclear Test Site in Kazakhstan. This dose-response analysis identified a statistically significant association between thyroid nodule prevalence and reconstructed doses of fallout-related internal and external radiation to the thyroid gland; however, the effects of dosimetric uncertainty were not evaluated since the doses were simple point "best estimates". In this work, we revised the 2008 study by a comprehensive treatment of dosimetric uncertainties. Our present analysis improves upon the previous study, specifically by accounting for shared and unshared uncertainties in dose estimation and risk analysis, and differs from the 2008 analysis in the following ways: 1. The study population size was reduced from 2,994 to 2,376 subjects, removing 618 persons with uncertain residence histories; 2. Simulation of multiple population dose sets (vectors) was performed using a two-dimensional Monte Carlo dose estimation method; and 3. A Bayesian model averaging approach was employed for evaluating the dose response, explicitly accounting for large and complex uncertainty in dose estimation. The results were compared against conventional regression techniques. The Bayesian approach utilizes 5,000 independent realizations of population dose vectors, each of which corresponds to a set of conditional individual median internal and external doses for the 2,376 subjects. These 5,000 population dose vectors reflect uncertainties in dosimetric parameters, partly shared and partly independent, among individual members of the study population. Risk estimates for thyroid nodules from internal irradiation were higher than those published in 2008, which results, to the best of our knowledge, from explicitly accounting for dose uncertainty. In contrast to earlier findings, the use of Bayesian methods led to the conclusion that the biological effectiveness for internal and external dose was similar. Estimates of excess relative risk per unit dose (ERR/Gy) for males (177 thyroid nodule cases) were almost 30 times those for females (571 cases) and were similar to those reported for thyroid cancers related to childhood exposures to external and internal sources in other studies. For confirmed cases of papillary thyroid cancers (3 in males, 18 in females), the ERR/Gy was also comparable to risk estimates from other studies, but not significantly different from zero. These findings represent the first reported dose response for a radiation epidemiologic study considering all known sources of shared and unshared errors in dose estimation and using a Bayesian model averaging (BMA) method for analysis of the dose response.
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Affiliation(s)
| | - Deukwoo Kwon
- Sylvester Comprehensive Cancer Center, University of Miami, Miami, Florida
| | | | - Brian Moroz
- National Cancer Institute, Bethesda, Maryland
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Rodzi M, Zhumadilov K, Ohtaki M, Ivannikov A, Bhattacharjee D, Fukumura A, Hoshi M. Estimation of background radiation doses for the Peninsular Malaysia's population by ESR dosimetry of tooth enamel. RADIATION AND ENVIRONMENTAL BIOPHYSICS 2011; 50:451-458. [PMID: 21404066 DOI: 10.1007/s00411-011-0358-9] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 10/05/2010] [Accepted: 02/20/2011] [Indexed: 05/30/2023]
Abstract
Background radiation dose is used in dosimetry for estimating occupational doses of radiation workers or determining radiation dose of an individual following accidental exposure. In the present study, the absorbed dose and the background radiation level are determined using the electron spin resonance (ESR) method on tooth samples. The effect of using different tooth surfaces and teeth exposed with single medical X-rays on the absorbed dose are also evaluated. A total of 48 molars of position 6-8 were collected from 13 district hospitals in Peninsular Malaysia. Thirty-six teeth had not been exposed to any excessive radiation, and 12 teeth had been directly exposed to a single X-ray dose during medical treatment prior to extraction. There was no significant effect of tooth surfaces and exposure with single X-rays on the measured absorbed dose of an individual. The mean measured absorbed dose of the population is 34 ± 6.2 mGy, with an average tooth enamel age of 39 years. From the slope of a regression line, the estimated annual background dose for Peninsular Malaysia is 0.6 ± 0.3 mGy y(-1). This value is slightly lower than the yearly background dose for Malaysia, and the radiation background dose is established by ESR tooth measurements on samples from India and Russia.
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Affiliation(s)
- Mohd Rodzi
- Research Institute for Radiation Biology and Medicine, Hiroshima University, 1-2-3 Kasumi, Minami Ku., Hiroshima, 734-8553, Japan.
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Simon SL, Bouville A, Kleinerman R. Current use and future needs of biodosimetry in studies of long-term health risk following radiation exposure. HEALTH PHYSICS 2010; 98:109-17. [PMID: 20065672 PMCID: PMC2806653 DOI: 10.1097/hp.0b013e3181a86628] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Abstract] [MESH Headings] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/28/2023]
Abstract
Biodosimetry measurements can potentially be an important and integral part of the dosimetric methods used in long-term studies of health risk following radiation exposure. Such studies rely on accurate estimation of doses to the whole body or to specific organs of individuals in order to derive reliable estimates of cancer risk. However, dose estimates based on analytical dose reconstruction (i.e., models) or personnel monitoring measurements (i.e., film badges) can have substantial uncertainty. Biodosimetry can potentially reduce uncertainty in health risk studies by corroboration of model-based dose estimates or by using them to assess bias in dose models. While biodosimetry has begun to play a more significant role in long-term health risk studies, its use is still generally limited in that context due to one or more factors including inadequate limits of detection, large inter-individual variability of the signal measured, high per-sample cost, and invasiveness. Presently, the most suitable biodosimetry methods for epidemiologic studies are chromosome aberration frequencies from fluorescence in situ hybridization (FISH) of peripheral blood lymphocytes and electron paramagnetic resonance (EPR) measurements made on tooth enamel. Both types of measurements, however, are usually invasive and require biological samples that can be difficult to obtain. Moreover, doses derived from these methods are not always directly relevant to the tissues of interest. To increase the value of biodosimetry to epidemiologic studies, a number of issues need to be considered, including limits of detection, effects of inhomogenous exposure of the body, how to extrapolate from the tissue sampled to the tissues of interest, and how to adjust dosimetry models applied to large populations based on sparse biodosimetry measurements. The requirements of health risk studies suggest a set of characteristics that, if satisfied by new biodosimetry methods, would increase the overall usefulness of biodosimetry in determining radiation health risks.
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Affiliation(s)
- Steven L Simon
- Division of Cancer Epidemiology and Genetics, National Cancer Institute, National Institutes of Health, Bethesda, MD 20892, USA.
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Sholom S, Desrosiers M, Chumak V, Luckyanov N, Simon SL, Bouville A. UV effects in tooth enamel and their possible application in EPR dosimetry with front teeth. HEALTH PHYSICS 2010; 98:360-8. [PMID: 20065706 PMCID: PMC2808200 DOI: 10.1097/01.hp.0000348002.69740.bd] [Citation(s) in RCA: 11] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/23/2023]
Abstract
The effects of ultraviolet (UV) radiation on ionizing radiation biodosimetry were studied in human tooth enamel samples using the technique of electron paramagnetic resonance (EPR) in X-band. For samples in the form of grains, UV-specific EPR spectra were spectrally distinct from those produced by exposure to gamma radiation. From larger enamel samples, the UV penetration depth was determined to be in the 60-120 mum range. The difference in EPR spectra from UV exposure and from exposure to gamma radiation samples was found to be a useful marker of UV equivalent dose (defined as the apparent contribution to the gamma dose in mGy that results from UV radiation absorption) in tooth enamel. This concept was preliminarily tested on front teeth from inhabitants of the region of the Semipalatinsk Nuclear Test Site (Kazakhstan) who might have received some exposure to gamma radiation from the nuclear tests conducted there as well as from normal UV radiation in sunlight. The technique developed here to quantify and subtract the UV contribution to the measured tooth is currently limited to cumulative dose measurements with a component of UV equivalent dose equal to or greater than 300 mGy.
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Affiliation(s)
- S Sholom
- Laboratory of External Exposure Dosimetry, Research Center for Radiation Medicine, Kiev, Ukraine.
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Zhumadilov K, Stepanenko V, Ivannikov A, Zhumadilov Z, Zharlyganova D, Toyoda S, Tanaka K, Endo S, Hoshi M. Measurement of absorbed doses from X-ray baggage examinations to tooth enamel by means of ESR and glass dosimetry. RADIATION AND ENVIRONMENTAL BIOPHYSICS 2008; 47:541-545. [PMID: 18648837 DOI: 10.1007/s00411-008-0184-x] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 04/01/2008] [Accepted: 07/12/2008] [Indexed: 05/26/2023]
Abstract
The contribution of radiation from X-ray baggage scans at airports on dose formation in tooth samples was investigated by electron spin resonance (ESR) dosimetry and by glass dosimetry. This was considered important, because tooth samples from population around the Semipalatinsk Nuclear Test Site (SNTS), Kazakhstan, had been transported in the past to Hiroshima University for retrospective dose assessment of these residents. Enamel samples and glass dosimeters were therefore examined at check-in time at Kansai airport (Osaka, Japan), Dubai airport (Dubai, United Arab Emirates) and Domodedovo airport (Moscow, Russia). These airports are on the route from Kazakhstan to Japan. Three different potential locations of the samples were investigated: in pocket (without X-ray scans), in a small bag (with four X-ray scans) and in large luggage (with two X-ray scans). The doses obtained by glass and ESR dosimetry methods were cross-compared. As expected, doses from X-ray examinations measured by glass dosimetry were in the microGy range, well below the ESR detection limit and also below the doses measured in enamel samples from residents of the SNTS.
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Affiliation(s)
- Kassym Zhumadilov
- Research Institute for Radiation Biology and Medicine, Hiroshima University, 1-2-3 Kasumi, Minami-ku, Hiroshima 734-8553, Japan.
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