Radiological Accident Research Articles

Intercomparison of translocation and dicentric frequencies between laboratories in a follow-up of the radiological accident in Estonia

Purpose : To perform an interlaboratory comparison of FISH chromosome painting and to study the time-course of translocations and dicentrics in three accident victims exposed to radiation. Also, to use the data in the validation of the FISH technique as a retrospective dosimeter. Materials and methods : Twelve blood samples were collected during 4 years from three subjects exposed to radiation in an accident in Estonia in 1994 involving γ -radiation from a 137Cs source. Two of the subjects were exposed during approximately 7 h, both receiving a protracted dose of about 1 Gy and also localized exposure. The third subject received a protracted whole-body dose of 2.7Gy during 4 weeks as well as a short-term partialbody dose. Preparations from 48-h metaphase cultures were painted by the FISH technique using routine methods and probe cocktails in four laboratories. Samples from each subject were analysed in two different laboratories that used different combinations of whole chromosome probes. The PAINT nomenclature was applied when recording chromosome aberrations. Results : The intercomparison of FISH analysis data showed reasonable similarities between laboratories, the largest discrepancy being 21% in the frequency of two-way translocations in subject 3. Half-time calculations, based on combined data sets from two laboratories, showed that dicentrics decreased rapidly with half-times of approximately 2 years. In all cases, the initial dicentric yields were lower than the initial translocation yields. During the 4-year follow-up, the frequencies of all translocations in cells containing only simple rearrangements fell on average to about 65% of their initial value. Two-way translocations were slightly more persistent than all translocations. The average halftime was about 8 years for two-way translocations and around 6 years for all translocations. Cells containing complex rearrangements were few in number and they disappeared with time. In general, the inclusion of complex cells caused a more rapid fall in aberration yield. Conclusions : In general, the results imply that relatively consistent scoring data were obtained with different chromosome painting protocols. They also support the idea that the reduction of translocations with time is associated with partial-body irradiation.

Psychological Effects of Nuclear and Radiological Warfare

Not since 1945 has the world experienced nuclear warfare, although there has been the threat of nuclear terrorism and a large number of nuclear/radiological accidents. Most people fear a nuclear/radiological threat even more than a conventional explosion due both to their inability to perceive the presence of radiation with the ordinary human senses and to concerns about perceived long-lasting radiation effects. Studies of radiological accidents have found that for every actually contaminated casualty, there may be as many as 500 people who are concerned, eager to be screened for contamination, sometimes panicked, and showing psychosomatic reactions mimicking actual radiation effects. Data from the Hiroshima and Nagasaki attacks revealed widespread acute reactions such as psychic numbing, severe anxiety, and disorganized behavior, and there were later chronic effects such as survivor guilt and psychosomatic reactions. Such responses would likely be common in any future nuclear/radiological accident, terrorist attack, or warfare.

Response to radiological accidents: the role of the International Atomic Energy Agency

The International Atomic Energy Agency has, under its Statute, specifically defined functions relating to radiation safety, in particular, responsibilities for the development of standards of safety and provision for their application. These functions are fulfilled through the development of a wide range of standards, including those on preparedness and response to nuclear accidents or radiological emergencies. It also devotes considerable effort to assisting countries in applying those standards. In addition, the Agency has responsibilities placed on it by virtue of a number of Conventions, two of which are relevant to nuclear accidents or radiological emergencies: the Convention on Early Notification of a Nuclear Accident (Early Notification Convention) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention). Under the Assistance Convention, assistance may include medical response. This paper provides an overview of the Agency's work regarding emergency preparedness and response, with specific reference to a number of recent events. It also discusses new initiatives regarding the safety and security of radiation sources, which have, as a principal objective, the reduction of the risk of such events.

On the Disposal of Contaminated Milk in Coastal Waters

Estimates have been made of the reduction in dissolved oxygen levels in coastal waters that would result from the disposal of contaminated milk following a radiological accident. Two contrasting sites were chosen: the Bristol Channel near Hinkley Point and the coast of Cumbria near Sellafield. The results suggest that the dilution would be sufficiently strong near Hinkley Point, due to vigorous tidal mixing, that the impact on the DO levels of the coastal waters would be negligible. However, at both Sellafield and Heysham the disposal of milk could result in a reduction of the DO by 1–2 mg l −1. In contrast to shallow estuarine waters, the recovery of oxygen levels due to the effects of re-aeration through surface gas exchange is unlikely to be significant due to the depth of the coastal waters. However, the recovery of the dissolved oxygen levels to ambient conditions following the completion of the discharge would occur on a time scale of about 17 days due to mixing of the DO deficit plume into the surrounding waters.

Ambient dose equivalent rate in Goiânia 12 years after the 137Cs radiological accident.

This paper describes the situation of ambient dose equivalent rates in four of the main foci of 137Cs contamination in the city of Goiânia, Brazil, in 1999, 12 y after one of the worst radiological accidents in the world. During the decontamination, all the buildings of the three highly contaminated sites were demolished and the top soil removed. Afterwards, the soil of two of these lots was covered with concrete, and they remain vacant today. The soil of the third of these lots, identified here as E, previously known as junkyard II, was covered only with clean soil. Three to four years after the accident, new houses were constructed on this lot, and some very poor people live and work there collecting recyclable material. Gamma ray spectrometry, with a portable survey meter, was performed in the quoted places along with outdoor measurements in many other locations of Goiânia. The average ambient dose equivalent rate due to natural background radiation from radionuclides in the soil and cosmic radiation in non-contaminated areas of the city of Goiânia is 62 nSv h(-1). In most of the highly contaminated sites during the accident, the average ambient dose equivalent rate ranged from around 100 to 1,000 nSv h(-1). The only exception was site E, where values of ambient dose equivalent rate as high as 2.6 microSv h(-1) were found.

The Medical Response to Nuclear and Radiological Accidents in China

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Radioactivity teaching: Environmental consequences of the radiological accident in Goiânia (Brazil)

Ionizing radiation and its effects on human beings, radiation protection, and radiological accident prevention are topics usually not included in the physics courses at the Brazilian universities. As a consequence, high school teachers are not able to enlighten their students when radiological or nuclear accidents occur. This paper presents a teaching program on ionizing radiation physics, to be applied to undergraduate physics students and to physics high school teachers. It is based on the environmental consequences of the 1987 radiological accident in Goiânia. This program was applied to two undergraduate physics students, in 1999, at the Universidade Federal Fluminense, Brazil. Results of the gamma ray spectrometry measurements of samples collected in Goiânia by the students are presented.

The Radiological Accident in Lilo. International Atomic Energy Agency, pp. 103, 2000 (IAEA, Vienna, Austria), £20 ISBN 92‐0‐101300‐0The Radiological Accident in Istanbul. International Atomic Energy Agency, pp. 75, 2000 (IAEA, Vienna, Austria), £16 ISBN 92-0-101400-7The Radiological Accident in Yanango. International Atomic Energy Agency, pp. 41, 2000, (IAEA, Vienna, Austria), £11 ISBN 92-0-101500-3

Book reviewThe Radiological Accident in Lilo. International Atomic Energy Agency, pp. 103, 2000 (IAEA, Vienna, Austria), £20 ISBN 92‐0‐101300‐0 The Radiological Accident in Istanbul. International Atomic Energy Agency, pp. 75, 2000 (IAEA, Vienna, Austria), £16 ISBN 92-0-101400-7 The Radiological Accident in Yanango. International Atomic Energy Agency, pp. 41, 2000, (IAEA, Vienna, Austria), £11 ISBN 92-0-101500-3K FaulknerK FaulknerSearch for more papers by this authorPublished Online:28 Jan 2014https://doi.org/10.1259/bjr.74.879.740297SectionsPDF/EPUBFull Text ToolsAdd to favoritesDownload CitationsTrack Citations ShareShare onFacebookTwitterLinked InEmail About Previous article Next article FiguresReferencesRelatedDetailsCited byEvaluation of X-ray ionizing radiation on Plasmodium berghei invasion of erythrocytes15 February 2022 | Bionatura, Vol. 7, No. 1Use of Reliability Block Diagram and Fault Tree Techniques in Reliability Analysis of Emergency Diesel Generators of Nuclear Power Plants1 August 2019 | International Journal of Mathematical, Engineering and Management Sciences, Vol. 4, No. 4Development of a Computer Tool to Support the Teaching of Materials Technology1 August 2017 | Materials Science Forum, Vol. 903Application of Metallographic Methods for Thermal Ageing Evaluation on Samples from Primary Piping of NPP1 March 2017 | Materials Science Forum, Vol. 891Exploring the Characteristics of Organizational Factors on Safety Climate in Taiwan1 June 2011 | Applied Mechanics and Materials, Vol. 58-60 Volume 74, Issue 879March 2001Pages: 209-296 © The British Institute of Radiology History Published onlineJanuary 28,2014 Metrics Download PDF

Qualification of a numerical anthropomorphic model dedicated to radiological accidents

In the case of accidental exposure to ionising radiation, estimation of the ahsorhed dose in the organism is an important indicator for evaluating the hiological consequences. To complete the clinical and hiological investigations, physical dosimetry methods can he used to provide an estimate of the absorhed dose and its distribution in the organism. This article describes the development of calculation tools in physical dosimetry, in particular a numerical anthropomorphic pbantom which can he adapted to each individual. A standard model was developed from the data avaiiahle in the ICPR Publication 23. A set of tests was carried out with the model dimensions heing modifed to study the effect of morphology on the dose calculation. A comparison was made with another standard model used in internal dosimetry. These studies highlight the parameters to he taken into account in the model, depending on whether the accident is local or global. Caracterisation d'un modele anthropomorphe numerique pour la reconstitution d'accident radiologique.

Qualifying Numerical Tools for Reconstructing Physical Doses in the Case of Accidental Exposure to Ionising Radiation

Nowadays, when accidental exposure to ionising radiation occurs, clinical observations, and biological and physical investigations are usually taken into account to estimate the seriousness of the irradiation and, subsequently, to determine suitable therapy. A supplementary means based on a realistic numerical simulation of the accident situation may also be used, in order to assess the absorbed dose distribution inside the body. This can be particularly useful for localised irradiation, for which biological dosimetry is more often of limited relevance. This paper mainly describes the qualification of the computer code, the geometrical models and the techniques to reduce uncertainties. For specific configurations corresponding to the most frequent radiological accidents, all uncertainties are evaluated.

An Approach to Evaluating the Societal Risks and Agricultural Impacts from a Proposed Plutonium Processing Facility

The authors recently evaluated the potential societal risk from a proposed plutonium processing facility at the Pantex Plant near Amarillo, Texas. The societal risk from the proposed facility was compared to that of existing facilities and operations at the Pantex Plant. In addition, the research team investigated potential agricultural impacts by making use of source terms from postulated, bounding accidents identified in the societal risk assessment. The design of the proposed facility was not well defined due to the preliminary stage of the design process. Data from a wide variety of sources were used to infer radiological accident frequencies, source terms, and consequences. Data sources included environmental impact statements, safety analysis reports, Federal regulations and standards, international and U.S. advisory committee reports, and articles in professional publications. Safety documents for existing operations were reviewed, and a consistent analysis method applied to the postulated accidents for the proposed facility. The derived societal risk for the proposed facility could then be compared to that from existing operations and facilities. Areas of land contaminated to different levels by an accident were used as the measure of the agricultural consequence. Derived response levels (DRLs) were calculated that corresponded to protective action guides (PAGs) used in emergency situations. These values were used in conjunction with the HotSpot computer code (Homann 1994) to determine the areas of land where the deposition levels for the various accident scenarios exceeded the DRLs corresponding to particular PAGs.

A gamma camera for measurements of internal contamination after a radiological accident

After a radiological accident with the release of large amounts of radionuclides into the environment, measurements of the external and internal exposure of the public will be urgently required. The aim of this study was to investigate the properties of a gamma camera with regard to measurements of internal contamination. The gamma camera was used as a detector without any imaging function. The lowest minimum detectable activity, 100 Bq 131I in thyroid measured over the neck and 400 Bq 137Cs in the whole body measured over the trunk (1 min measuring time), was found when using the lowest (50 keV-450 keV) energy interval among the three investigated (also 550-750 keV and 450-550 keV), in measurements without a collimator. The mechanical difficulties in handling a gamma camera without a collimator may also have to be considered. It is essential to pay attention to the influence of body size on both background and sensitivity. Provided proper calibrations are carried out and routines for measurements are established, a gamma camera is useful for fast identification and quantification of internal contamination with gamma-emitting radionuclides down to levels so low that in most situations they give a low contribution to the effective dose.

Transport Data Collection and Reporting in the Czech Republic

AbstractThe State Office for Nuclear Safety (SONS) as the responsible body for the safe transport of radioactive materials in the Czech Republic is required to maintain a national system for registration of: (i) the approvals of special form radioactive material, package designs and shipments; (ii) the records of exposure of persons coming into contact with ionising radiation sources at their work (including radiation exposures resulting from radioactive material transport); and (iii) the reports on radiological accidents (including reports on accidents in radioactive material transport). The system is described of registration of the above mentioned items in the Czech Republic following on from the obligations of the SONS stipulated in the Act No. 18/1997 on Peaceful Utilization of Nuclear Energy and Ionizing Radiation Act (‘Atomic Act’). The importance of the International Atomic Energy Agency databases PACKTRAM, SHITPTRAM, EXTRAM, EVTRAM and REDTRAM is discussed from SONS point of view.

The Goi nia 137Cs Accident - A Review of the Internal and Cytogenic Dosimetry

The Goiânia radiological accident involved a large number of individuals who became internally contaminated and/or were externally exposed to a stolen 137Cs source. The results of bioassay and cytogenetic monitoring during the emergency phase and the follow-up of the accident are reviewed. An age-weight specific Cs retention model was developed. The effectiveness of Prussian Blue, a drug given to enhance the elimination of Cs from the body, was evaluated. Internal committed absorbed doses were estimated using monitoring data and were compared with results from preliminary dose assessments. A summary of a model for the kinetics of elimination of chromosomal aberrations is also presented.

Chromosomal instability in in vivo radiation exposed subjects

. Purpose : To investigate whether delayed chromosomal instability arises in human peripheral T lymphocytes exposed in vivo to gamma irradiation. Materials and methods : Long-term cultures were established from lymphocytes obtained from subjects involved in the radiological accident in Estonia in 1994. Two individuals exposed to a high dose, one individual with low exposure and one apparently unexposed person were studied. Two Estonian controls not involved with the accident were also analysed. Cells were grown for 6-42 days and chromosomal aberrations were assessed from G-banded metaphases. In addition, FISH chromosome painting analysis was performed on short-term cultures established from whole blood. Results : No obvious sign of chromosomal instability was observed in the in vivo follow-up of the frequencies of chromosomal aberrations in lymphocytes of radiation accident victims performed by the FISH technique (48h cultures established at different time intervals after the exposure). However, when the lymphocytes were cultured long term in vitro, chromosomal instability was observed. There was no dose-response, and the appearance of chromosomally unstable cells in long-term cultures was also observed in a subject exposed to a dose of less than 0.1Gy. Moreover, in contrast with previous findings, chromosomal instability was also observed in cells from non-exposed control individuals. The chromosomal changes observed in the controls were less complex than the aberrations in the cultures derived from individuals exposed to high doses. Conclusions : Chromosomal instability was observed in long-term cultures of donors with in vivo exposure to gamma -radiation. No doseresponse was apparent. However, in contrast with previous findings, signs of chromosomal instability were observed also in long-term cultures from non-exposed controls. Further studies are needed to assess possible inter-individual differences in the induction of chromosomal instability.

Monitoring Strategy in Support of Radiological Emergency Management

Monitoring radioactive contamination after a radiological accident provides decision-makers with information on whether or not to take protective action. The monitoring strategy discussed concerns the response phase of the accident, which is subdivided into two stages. In the first, early monitoring stage, given the very short time span available for protective action, data have to be available within several hours after the radioactive release. The main purpose of measurements in this stage is to test and adjust model predictions. This implies measuring activity concentration in air, ambient dose rate and surface contamination. In the second, extensive monitoring stage, emphasis is on monitoring foodstuffs (milk, vegetables and meat) and drinking water. Depending on the expected gradient in the contamination and the purpose of the measurements a basic monitoring density of about 50 km x 50 km is observed. Within a radius of 10 km from nuclear facilities extra monitoring stations will be necessary.

Radiation risk estimation in human populations: Lessons from the radiological accident in Brazil

The development of radiological and nuclear technologies and the deployment of nuclear weapons have made ionizing radiation one of the most studied human mutagens. Exposure to ionizing radiation produces DNA damage which can result in mutation and cancer, making the risk associated with human exposure a critical issue. In this paper we estimate the risk associated with radiation exposure for individuals exposed to 137Cs during the 1987 Goiânia radiological accident. Using combined regression slopes from both the in vivo hprt mutant frequency and micronucleus frequency data we estimated a doubling dose of 173 (±47) cGy for these two endpoints. This is in close agreement with the published estimates for low dose rate and chronic exposure to low-LET radiation. We obtained risk estimates of about 24-fold increase in dominant disorders in the post-exposure generation of the directly exposed population. No detectable increase was found in the population at large. The risk of carcinogenesis in the directly exposed population was found to be increased by a factor in the range of 1.4 to 1.5. The small sample size in this study requires a large element of caution with respect to risk estimates interpretation. Moreover, the doubling dose estimates prepared here are derived from lymphocytes. This somatic data may require additional considerations for both cancer and certainly germ-line events. Nevertheless, the risk of carcinogenesis and genetic harm for this population are good indicators of the potential genetic damage imposed by ionizing radiation to the Goiânia population.

Evaluation of radiological consequences of nuclear accidents with the computer model PARK / Bewertung der radiologischen Konsequenzen kerntechnischer Unfallszenarien mit Hilfe des Programmsystems PARK

Considering the radiological consequences of a nuclear accident, this paper investigates the dose relevance of the exposure pathways, ingested radionuclides and foodstuff as relate to the season during which the accident occurs. Assumed is an atmospheric release according to release category no 2 of the 'Deutsche Risikostudie Kernkraftwerke (DRS)'. The calculations include the dry deposition (fallout) of radionuclides as well as wet deposition (washout). Contaminations and doses to be expected in a distance of 200 km are calculated using the radioecological computer model PARK (Program System for the Assessment and Mitigation of Radiological Consequences). In the case of a nuclear accident occurring in summer, ingestion is identified as the most relevant pathway. Essentially, only a few radionuclides contribute to the ingestion dose. Results show that it is not recommendable to rely solely on experience gained from the Chernobyl event when assessing consequences of radiological accidents.

Nature of mutation in the human hprt gene following in vivo exposure to ionizing radiation of cesium-137.

The current study comprises the analysis of mutations in 10 individuals accidentally exposed to cesium-137 during the 1987 radiological accident in Goiânia, Brazil. Their exposures were among the highest experienced, ranging from 1 to 7 Gy. Peripheral T-lymphocyte samples were obtained 3.3 years after the original exposure and mutation was studied at the hprt locus using the 6-thioguanine-resistance selection assay. The mutational spectrum for the exposed population is comprised of 90 independent mutants. Based on T-cell receptor analysis, only 5% (5/95) were clonally related. Mutants were initially studied using RT-PCR and directly sequenced using an automated laser fluorescent DNA sequencer. Mutants that repeatedly failed to produce cDNAs were studied using a multiplex PCR assay with genomic DNA. Missense mutations were the most frequent event recovered, comprising 40% (23/57) of the spectral sample. An excess of events involving A:T base pairs was observed, exhibiting a significant difference (chi 2 = 12.7, P = 0.0004) when compared to the spontaneous spectrum. This finding may reflect the effect of ionizing radiation-induced damage, suggesting a potential similarity to radiation effects in prokaryotes. At the genomic level, 36.7% (33/90) of the mutants exhibited gross structural alterations, as detected by multiplex PCR. Deletion events were over-represented in our spectral sample, displaying a twofold increase when compared to the frequency observed in the spontaneous mutation database.

The Communication of Radiological Risk to Populations Exposed to a Radiological Accident: Considerations Concerning the Accident in Goi nia

The main purpose of this paper is to describe the reactions of a population subjected to the effects of a radiological accident and receiving information about radiation effects for the first time. The behaviour of the victims during various phases of the accident is discussed.