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Sample records for goiania radiological accident

  1. Radiological accident of Goiania

    International Nuclear Information System (INIS)

    Palacios, Elias; Gimenez, J.C.

    1988-01-01

    The accident of Goiania that took place in September, 1987, was the consequence of the dismantlement of the teletherapy equipment containing a Cs 137 source. The activity of the source was of about 5,2.10 13 Bq(1.400 Ci) and was made up by 1.10 -1 Kg of ClCs. This is one of the worst accidents, involving medical or industrial source, which happened up to the moment. The accident and the criteria adopted to face the emergency are described. The characteristics of the irradiation and superficial and internal contamination of the persons affected caused any dosimetric evaluation to be particularly difficult. The emergency control managed by capable persons was carried out with the expected difficulties in some areas within the Goiania city. About 90 % of the material could be recovered, in the removal works, in order to be treated as radioactive waste. Conclusions that should be taken into account in Argentina are reached. The authors of the article took part in the emergency by helping the brazilian Authorities within the Mutual Assistance Agreement between Argentina and Braxil. (M.E.L.) [es

  2. Lessons of the radiological accident in Goiania

    International Nuclear Information System (INIS)

    Alves, R.N.; Xavier, A.M.; Heilbron, P.F.L.

    1998-01-01

    On the basis of the lessons teamed from the radiological accident of Goiania, actions are described which a nuclear regulatory body should undertake while responding to an accident of this nature. (author)

  3. Preliminary report about Goiania radiological accident, Brazil

    International Nuclear Information System (INIS)

    Oliveira, A.R. de.

    1988-05-01

    The events that originate the Goiania radiological accident involving the rupture of Cesium 137 source, the source characteristics, the medical aspects related to the triage of victims, the medical attendance, and the special measurements of decontamination in the Goiania General Hospital (HGG), are described. (M.C.K.) [pt

  4. Report about the radiological accident in Goiania

    International Nuclear Information System (INIS)

    Schrimer, H.P.; Gomes, C.A.; Recio, J.C.A.

    1997-01-01

    This work reports the activities developed by the technical groups who worked during the radiological accident in Goiania, held on September 1997. Several aspects of the accident are described. The final solution for the disposal of the radioactive wastes generated during the accident is presented, according to the Brazilian waste management policy. (author)

  5. Report on the radiological accident in Goiania, Goias, Brazil

    International Nuclear Information System (INIS)

    Alves, R.N.

    1988-01-01

    The report describes the radiological accident occured in Goiania, Brazil, in september 1987. The following aspects concerning the accident are presented in specific chapters: 1- evaluation of the accident and the first aids, 2- attendance to the victims of Goiania radiological accident, 3- decontamination, 4- radioactive wastes arising from the accident, 5- working personnel and technical cooperation, 6- equipments and 7- radiation protection: limits and recommendations [pt

  6. The radiological accident in Goiania

    International Nuclear Information System (INIS)

    1988-01-01

    The report is based on a meeting held in Brazil, 19-27 July 1988. It describes how the accident occurred, examines how it was managed and how its consequences were contained, and sets out observations and recommendations based upon lessons learned. Many people received large doses of radiation, due to both external and internal exposure. Four of the casualties ultimately died and 28 people suffered radiation burns. Residences and public places were contaminated. The decontamination necessitated the demolition of seven residences and various other buildings, and the removal of the topsoil from large areas. In total 3,500 m 3 of radioactive waste was generated. Refs, figs, tabs and photographs

  7. Ten years after the radiological accident of Goiania, a reflection

    International Nuclear Information System (INIS)

    Nouailhetas, Y.; Xavier, A.M.

    1998-01-01

    This work contains a reflection on the impact of the radiological protection measures taken in the city of Goiania in the aftermath of the accident involving caesium-137, along with a discussion on the biological foundation of these actions. (author)

  8. Goiania radiological accident: five years talking with the population

    International Nuclear Information System (INIS)

    Rozental, J.J.

    1993-01-01

    This article presents an overview five years after the Goiania radiological accident. It reviews from a number of important aspects the psychological impact and conflicting opinions, the public hearings and debates and, particularly describes the victims that still have difficulties to understand the accident and its consequences. (B.C.A.). 05 refs

  9. How the radiological accident of Goiania was initially determined

    International Nuclear Information System (INIS)

    Ferreira, W.M.

    2000-01-01

    Mainly the initial actions adopted to minimise the consequences of radiological accident involving the public are very important for bringing the situation to the normality. In this work the author presents a short history about the radiological accident with a 137 Cs source occurred in the city of Goiania, Brazil in 1987 as well as the actions adopted by him during the first hours after the detection of the accident. (author)

  10. Public monitoring during the radiological accident in Goiania

    International Nuclear Information System (INIS)

    Ferreira, W.M.

    2000-01-01

    During the radiological accident with Cs 137 occurred at Goiania, Brazil, many people were contaminated. To identify the people with possible contamination a large place in the center of the city was selected for screening people with a possibility of contamination. This paper describes the work involved monitoring about 112.800 persons in a period of three month. (author)

  11. Report about the radiological accident in Goiania; Documentario do acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Schrimer, H.P.; Gomes, C.A.; Recio, J.C.A. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Rejeitos Radioativos

    1997-12-31

    This work reports the activities developed by the technical groups who worked during the radiological accident in Goiania, held on September 1997. Several aspects of the accident are described. The final solution for the disposal of the radioactive wastes generated during the accident is presented, according to the Brazilian waste management policy. (author) 7 refs., 6 figs., 2 tabs.; hebe at cnen.gov.br

  12. The radiological accident in Goiania. Environmental aspects

    International Nuclear Information System (INIS)

    Rochedo, E.R.R.

    2000-01-01

    In 1987 a radioactive source containing CsCl powder was removed from a teletherapy machine in Goiania, Brazil. Subsequently it was ruptured in a residential garden, causing the dissemination of the 137 Cs powder over about 1 km 2 in an urbanized area of the city. The radioactive material was passed on to several people with consequent contamination of their families, houses, and surrounding environments. Mechanisms of resuspension/deposition spread the material over roofs, trees and home gardens. Environmental surveys were performed by helicopter and by car; contaminated places were mapped following monitoring with hand held instruments and an extensive environmental sample monitoring programme was undertaken. Dose assessments were performed: the criteria established by the authorities for decontamination were a dose of 5 mSv in the first year and an average lifetime dose of 1 mSv per year. The first-year dose criterion was found to be the most restrictive. Significant contamination was found at 85 houses: 41 of these had to be evacuated. Houses were first decontaminated indoors, by washing, scraping and/or removing contaminated items and furniture, and then outdoors by tearing out walls, roofs and pavements. Layers of soil were removed from contaminated gardens. Follow-up monitoring of the environment showed that several years after the accident, the residual activity had not migrated and no further spread through resuspension or deposition had occurred. A weathering half-life of 13 years was observed for gamma dose rates. Lessons learned included the need to improve several aspects of emergency response preparedness such as general management and interface between institutions, medical and paramedical support teams, dealing with the media and adequate prospective models for dose assessment. (author)

  13. The radiological accident in Goiania 10 years later: an evaluation

    International Nuclear Information System (INIS)

    Nouailhetas, Yannick; Xavier, Ana Maria

    1997-01-01

    This article presents a reflection on the impact on the population of the actions taken in the city of Goiania, following the 137-Cs accident and the biological fundamental on which this actions should be based upon. (author)

  14. Medical aspects of 137Cs decorporation: The Goiania radiological accident

    International Nuclear Information System (INIS)

    Farina, R.; Brandao-Mello, C.E.; Oliveira, A.R.

    1991-01-01

    In September 1987, the Goiania radiological accident involving a source of 137 Cs culminated in about 140 victims who presented internal and/or external contamination and/or external exposure to radiation and/or radiation burns. Internal contamination was verified through analysis of urine and fecal samples. Internal contamination was also evaluated by measurements performed at the whole-body counter installed in Goiania in November 1987. To enhance the decorporation of 137Cs, patients were treated with the following: (1) Prussian Blue, oral administration, in 46 patients; (2) diuretics, oral administration, in 17 patients; (3) induced perspiration, increasing 137 Cs elimination. These procedures were done under rigorous clinical evaluation and considering the data from assay of excreta and data obtained from the whole-body counter. The doses of Prussian Blue exceeded about 6.5 times the dose previously indicated in the literature. It was the first time diuretics were used in humans to treat 137 Cs internal contamination. The results of these procedures are discussed

  15. The radiological accident in Goiania, Brazil an overwiew

    International Nuclear Information System (INIS)

    Mendoca, A.H.

    1988-01-01

    The Cs-137 radiological accident which occurred in Goiania, Brazil, the largest of its kind, consisted of an accidental dispersion of 1370 Ci contained in the radiotherapy source by the rupture of its shield and capsule. The dissemination of the 19 g of the radioactive material, in the form of cesium chloride, way by a) displacement and personal contact of the people involved, b) commercialization of the raw materials collected in the junkyard and c) wind and rainwater transport. Such dispersion occurred in the period between the capsule rupture on September 17th and 29th when CNEN was informed of the accident. With the CNEN intervention ground and aero radiometric surveys were carried out and population monitored. Seven main radioactive points were identified in the city districts around this junkyard, some of them with exposure levels of up to 100 R/h at one meter. More than 118,000 people were monitored out of which 244 presented internal or external contamination. Medical care was provided to 129 people, but only fifty were hospitalized. Thirteen developed severe bone-marrow depression, among them four died. The drainage system was monitored as well as an environmental monitoring network has been established at the urban area around the main contaminations focus. Up to now, the results have shown the urban area as the most affected one. Soil and leaves samples presented specific activities of up to 10 5 Bq/kg within 50 m apart the main focus. Decontamination work resulted in more than 2,000 drums of 200 l/each, several metal containers and boxes. The wastes were removed to a temporary repository 20 km away from Goiania

  16. The psychological impact of the radiological accident in Goiania

    International Nuclear Information System (INIS)

    Carvalho, A.B. de.

    1988-01-01

    This work describes the psychological impact of an accident caused by the violation of a capsule containing Cesium 137 in the city of Goiania, Goias, Brazil, in September of 1987. Its object is to confirm the importance of having mental health teams working, not only with accident victims, but also side by side with the rescue teams in the event of radiation accidents. (author) [pt

  17. Dosimetric and medical aspects of the radiological accident in Goiania in 1987

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    In September 1987, in Goiania, a city of one million inhabitants and capital of the Brazilian State of Goias, a rotating assembly of the shielding head of a teletherapy unit was removed and the capsule containing 50.9 TBq (1375 Ci) of {sup 137}Cs was dismantled. This serious radiological accident resulted in four fatalities, injuries to many people, and the widespread contamination of the central part of Goiania. This TECDOC describes the dosimetric and medical aspects of the Goiania accident, including the experience of some of the scientists and physicians who were involved in the management, monitoring and treatment of the victims. Many scientific papers have been published on the subject in different journals. This publication compiles up to data conclusions on the 10 year follow-up of the Goiania accident victims, and summarizes the experience that was acquired Refs, figs, tabs

  18. Dosimetric and medical aspects of the radiological accident in Goiania in 1987

    International Nuclear Information System (INIS)

    1998-06-01

    In September 1987, in Goiania, a city of one million inhabitants and capital of the Brazilian State of Goias, a rotating assembly of the shielding head of a teletherapy unit was removed and the capsule containing 50.9 TBq (1375 Ci) of 137 Cs was dismantled. This serious radiological accident resulted in four fatalities, injuries to many people, and the widespread contamination of the central part of Goiania. This TECDOC describes the dosimetric and medical aspects of the Goiania accident, including the experience of some of the scientists and physicians who were involved in the management, monitoring and treatment of the victims. Many scientific papers have been published on the subject in different journals. This publication compiles up to data conclusions on the 10 year follow-up of the Goiania accident victims, and summarizes the experience that was acquired

  19. Radiological protection aspects regarding to assistance of the cesium-137 radiation accident victims in Goiania

    International Nuclear Information System (INIS)

    Hunt, John Graham; Oliveira Filho, Denizart Silveira de; Rabelo, Paulo Ney Pamplona

    1997-01-01

    The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due to the accident involving Cesium-137 are described, as well as the work of the IRD personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author)

  20. Aspects of radiation protection to attend the victims of radiological accident with cesium 137 in Goiania

    International Nuclear Information System (INIS)

    Hunt, J.G.; Oliveira Filho, D.S. de; Rabello, P.N.P.

    1988-01-01

    The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due do the accident involving cesium 137 are described, as well the work of the NUCLEI personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author) [pt

  1. The radiological accident of Goiania and its legislative implications

    International Nuclear Information System (INIS)

    Costa, Ieda Rubens

    2001-01-01

    Starting from a reflective view of the historical relationships existing between mankind and nature, this work seeks to pinpoint the today crises and ecological awareness in order to better understand the sparse use of various forms of assault relating to the environment, emphasising the caesium 137 accident as an object of this research. The destructive crisis of capitalism and its ethics, has the ecological crisis as only one of its aspects, however, the caesium 137 accident in Goiania was never left to be treated without pertaining to that crisis. In this way, tackling the issue of the caesium 137 and its unfolding disclosures became impossible not to mention the dimensions of cultural, philosophy, politics, economics and legal issues of the accident. Therefore, within the scope of this research, the Caesium 137 accident was treated as to avoid a fragmented analysis. It was also been transformed into a interdisciplinary work, as it shows the configuration of many concepts, but not legal matters in itself, because the Law itself, as a science, does not have an object through excellency. (author)

  2. Radiation protection in necropsy of the victims of the radiological accident in Goiania

    International Nuclear Information System (INIS)

    Maryins, Nadia S.F.; Silva, Lucia Helena C.; Rosa, Roosevelt

    1997-01-01

    Four of some victims of the radiological accident in Goiania, died in October and the necropsies were carried out at Marcilio Dias Naval Hospital (Rio de Janeiro, Brazil). Due to external and internal contamination presented by these victims, specific radiation protection procedures were adopted to support the medical team. The procedures established and applied by the Radiation Protection Staff during the arrangement of necropsy's room and for personal control since the necropsy's work until confining the bodies and the transportation back to Goiania are reported

  3. Evaluation to a long term remediation actions after Goiania radiological accident

    International Nuclear Information System (INIS)

    Rochedo, Elaine R.R.; Rio, Monica A. Pires do; Coutinho, Celia M.C.; Acar, Maria E.D.; Romeiro, Carlos H.

    2000-01-01

    Ten years after the Goiania radiological accident, the results obtained by the IRD Environmental Monitoring Program are compared to the values adopted for establishing the intervention levels at the time of the accident occurrence (1987), and to the values of the parameters obtained by European countries, after the Chernobyl accident. Significant differences were observed in parameter values, particularly, those related to a long term prediction of the contamination behaviour in an urban area. This paper shows the importance of the survey for the environmental behaviour of pollutants in tropical climate conditions. (author)

  4. Report of the activities carried out by the Psychological Support Group in the Goiania radiological accident in Brazil

    International Nuclear Information System (INIS)

    1988-01-01

    The report analyzes the characteristics and attitudes of the population directly involved in the Goiania radiological accident. The inhabitants of the affected area were interviewed in their residence. Factual information about the accidents were given and specific psychological support were received whenever necessary

  5. The influence of Goiania radiological accident on Brazilian public opinion concerning new nuclear electric plants

    International Nuclear Information System (INIS)

    Meldonian, Nelson Leon; Mattos, Luis Antonio Terribile de

    1997-01-01

    The Brazilian society is against applications of nuclear energy, mainly respecting to construction of new nuclear power plants, believing that they are harmful to population's welfare and the environment. By this reason, Brazilian nuclear sector would promote a more intensive program of public discussion, not limited to technical and scientific community. Intending to contribute to a better judgment by society about the differences between diverse employment of nuclear energy, arguments concerned to its benefits are presented, pointing out that adverse accounts to nuclear electricity based on Goiania radiological accident, are not justified

  6. Radiation protection in necropsy of the victims of the radiological accident in Goiania; Atuacao da radioprotecao nas necropsias dos radioacidentados de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Maryins, Nadia S.F.; Silva, Lucia Helena C.; Rosa, Roosevelt [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Four of some victims of the radiological accident in Goiania, died in October and the necropsies were carried out at Marcilio Dias Naval Hospital (Rio de Janeiro, Brazil). Due to external and internal contamination presented by these victims, specific radiation protection procedures were adopted to support the medical team. The procedures established and applied by the Radiation Protection Staff during the arrangement of necropsy`s room and for personal control since the necropsy`s work until confining the bodies and the transportation back to Goiania are reported 6 refs., 1 tab.

  7. The radiological accident in Goiania 10 years later: an evaluation; 10 anos do acidente radiologico de Goiania: uma reflexao

    Energy Technology Data Exchange (ETDEWEB)

    Nouailhetas, Yannick; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle. Diretoria de Radioprotecao e Seguranca Nuclear

    1997-12-31

    This article presents a reflection on the impact on the population of the actions taken in the city of Goiania, following the 137-Cs accident and the biological fundamental on which this actions should be based upon. (author) 16 refs.; yannick at cnen.gov.br; axavier at cnen.gov.br

  8. Biological effects of ionizing radiations. Radiological accident from Goiania, GO, Brazil; Efeitos biologicos das radiacoes ionizantes. Acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Okuno, Emico, E-mail: emico.okuno@if.usp.br [Instituto de Fisica da Universidade de Sao Paulo (IF-USP), SP (Brazil)

    2013-01-15

    This article presents the fundaments of radiation physics, the natural and artificial sources, biological effects, radiation protection. We also examine the sequence of events that resulted in Goiania accident with a source of caesium-137 from abandoned radiotherapy equipment and its terrible consequences. (author)

  9. Psychological evaluation of the patients contaminated in the Goiania radiological accident in Brazil

    International Nuclear Information System (INIS)

    1989-08-01

    The psychological evaluation of 68 patients contaminated in the Goiania accident as well as of the personnel (about 27) working at the organizations responsible for the assistance given to the victims of the accident is presented

  10. The radiological accident of Goiania and its consequences for the development of law

    International Nuclear Information System (INIS)

    Franco, N.M.F.L.

    1998-01-01

    The radiological accident of Goiania and its repercussions caused intense debate in Brazilian society, which extended to the legislative sphere. One of the principal outcomes of this debate was the inclusion in the new Brazilian Constitutional Charter of legal provisions covering the control of nuclear energy and of radiation sources. Internationally, the 1986 Vienna Convention on Early Notification of a Nuclear Accident and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency were invoked following the accident and proved to be effective in facilitating international co-operation and solidarity to deal with the aftermath of the accident. A number of international treaties on assistance in the event of nuclear accidents, the management of radioactive waste and the management of spent fuel are currently in force. The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste, adopted in 1997, is the most recent treaty promoting the sustainability of nuclear activities. Looking ahead, an international legal framework is needed to build upon and improve the principles of a culture of radiation safety. (author)

  11. Report of the psychological support given to victims of the Goiania radiological accident in Brazil

    International Nuclear Information System (INIS)

    Nunes, Lenice Cruvinel; Pereira, Maria Emilia Pontes

    1988-02-01

    The psychological support given to the victims of the Goiania accident are described. The assistance lasted two months on the average and was given while the victims were in the hospital and later on in the recuperation center

  12. Evaluation to a long term remediation actions after Goiania radiological accident; Avaliacao a longo prazo das acoes de remediacao apos o acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Rochedo, Elaine R.R.; Rio, Monica A. Pires do; Coutinho, Celia M.C.; Acar, Maria E.D.; Romeiro, Carlos H. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    2000-07-01

    Ten years after the Goiania radiological accident, the results obtained by the IRD Environmental Monitoring Program are compared to the values adopted for establishing the intervention levels at the time of the accident occurrence (1987), and to the values of the parameters obtained by European countries, after the Chernobyl accident. Significant differences were observed in parameter values, particularly, those related to a long term prediction of the contamination behaviour in an urban area. This paper shows the importance of the survey for the environmental behaviour of pollutants in tropical climate conditions. (author)

  13. Medical follow up of ten patients victims of the radiological accident occurred in Goiania, Goias State, Brazil 1988/1992

    International Nuclear Information System (INIS)

    Curado, M.P.; Morais, M.S.A.; Silva, J.F.; Assis, P.R.; Oliveira, A.R.; Santos, E.A.

    1992-01-01

    The author makes an update of the medical aspects of ten victims of the radiological accident occurred in Goiania in September 1987. These patients received specialized treatment during the critical phase at Marcilio Dias Naval Hospital in Rio de Janeiro. Actually these patients are under medical follow-up at Leide das Neves Ferreira Foundation since march 1988. The clinical, haematological and laboratorial results are presented and discussed. The importance of a close medical follow-up direct victims of a radiological accident is stressed. (author)

  14. Nursering assistance to the radiological accident patients in Goiania-an experience report

    International Nuclear Information System (INIS)

    Graciotti, M.E.

    1989-06-01

    In september, 1987, a caesium-137 source was disrupted and caused a serious radiological acident. The victims were hospitalized in the General Hospital in city of Goiania, Goias state, Brazil. This is a report of a personal experience, during the two months of nursering care. (author) [pt

  15. Biological effects of ionizing radiations. Radiological accident from Goiania, GO, Brazil

    International Nuclear Information System (INIS)

    Okuno, Emico

    2013-01-01

    This article presents the fundaments of radiation physics, the natural and artificial sources, biological effects, radiation protection. We also examine the sequence of events that resulted in Goiania accident with a source of caesium-137 from abandoned radiotherapy equipment and its terrible consequences. (author)

  16. The radiological accident of Goiania and its legislative implications; O acidente radiologico de Goiania e suas implicacoes legistativas

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Ieda Rubens

    2001-07-01

    Starting from a reflective view of the historical relationships existing between mankind and nature, this work seeks to pinpoint the today crises and ecological awareness in order to better understand the sparse use of various forms of assault relating to the environment, emphasising the caesium 137 accident as an object of this research. The destructive crisis of capitalism and its ethics, has the ecological crisis as only one of its aspects, however, the caesium 137 accident in Goiania was never left to be treated without pertaining to that crisis. In this way, tackling the issue of the caesium 137 and its unfolding disclosures became impossible not to mention the dimensions of cultural, philosophy, politics, economics and legal issues of the accident. Therefore, within the scope of this research, the Caesium 137 accident was treated as to avoid a fragmented analysis. It was also been transformed into a interdisciplinary work, as it shows the configuration of many concepts, but not legal matters in itself, because the Law itself, as a science, does not have an object through excellency. (author)

  17. The radiological accident of Goiania and the acceptance by the public of new nuclear power plants

    International Nuclear Information System (INIS)

    Meldonian, N.L.; Mattos, L.A.T.

    1998-01-01

    Misunderstandings on the peaceful uses and the safety of nuclear energy have been a leading cause of apprehension in Brazilian public opinion. A lack of knowledge of the characteristics and destination of radioactive wastes and negative media coverage of the use of nuclear energy have aggravated this situation. Believing that applications of nuclear energy are harmful to the population's welfare and the environment, Brazilian public opinion is opposed to the utilization of nuclear energy, and in particular to the construction of new nuclear power plants. For this reason, the Brazilian nuclear sector should promote a more intensive programme of public discussion, directed not solely at the technical and scientific communities, but also at the Brazilian public at large. Such a campaign would contribute towards a better understanding by Brazilian society of the different uses of nuclear energy and would present arguments in support of the benefits of this form of energy. Moreover, a campaign of this kind would show that negative associations about the use of electricity derived from nuclear power, which are based on the Goiania radiological accident, are not justified. (author)

  18. Post-traumatic stress disorders: Aftereffects of the Goiania radiological accident

    International Nuclear Information System (INIS)

    Bandeira de Carvalho, A.

    2000-01-01

    In September of 1987, a 137 Cs medical source was violated in the city of Goiania, Brazil and, as a result, four people died, 249 were internally and/or externally contaminated and 20 people were hospitalised at the Goiania General Hospital. The most serious cases were transferred to the Marcello Dias Naval Hospital in Rio de Janeiro. The objective of this paper is to describe the emotional and social impacts caused by this accident on the hospitalised victims. As these people belonged to a low social-economic level and did not understand the meaning of radioactivity, panic only started to be felt with the first deaths. The origin of their stress was, primarily, the radiation syndrome, but mostly the rejection suffered by them in the Goiania General Hospital, caused by fear of radioactivity; the difficulty in understanding the safety regulations; the always covered staffs; and the isolation due to immune-suppression. They feared having a limb amputated, were worried about their families, ambivalent about death: wishing and afraid of it. They felt guilty about the accident but at the same time they were seeking compensation from the State. Aggressive, due to the long confinement, they rioted inside the hospital. The need for psychological support was felt by the staff but few psychologists volunteered because of fear. Human beings present a number of psychological disorders after the trauma suffered in a catastrophe. These have a pattern, called post-traumatic stress disorders, which was noticed in this accident. It is a lesson learned in Goiania that psychological support is of vital importance to help the patient fight the consequences of the suffering. Psychologists should be trained to work without fear, during emergencies of this kind. (author)

  19. The Goiania accident - environmental survey

    International Nuclear Information System (INIS)

    Godoy, J.M.; Moreira, M.C.F.; Fonseca, E.S. da

    1997-01-01

    The survey methods applied during the Goiania accident could be considered complementary one to the other, and were able to give a clear picture about the contamination in the city to guide the further decontamination works. (author)

  20. Cytogenetic follow-up of patients exposed, 7.5 years after radiological accident in Goiania, Brazil

    International Nuclear Information System (INIS)

    Ramalho, Adriana T.

    1996-01-01

    Ten persons exposed to 137 Cs during the radiological accident in Goiania (Brazil) were reexamined for the frequency of unstable chromosomal aberrations (dicentric chromosomes, centric rings and acentric fragments) 7.5 years the first examination. It was found that the frequencies fell to about 5% of the initial values, for those individuals who had been exposed to moderate to high doses. For the subjects exposed to low doses, of the order of 0.2 Gy or less., the observed frequencies of chromosomal aberrations fell much more slowly. (author)

  1. Radiological protection aspects regarding to assistance of the cesium-137 radiation accident victims in Goiania; Aspectos de protecao radiologica no atendimento as vitimas do acidente radiologico com cesio-137 em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, John Graham; Oliveira Filho, Denizart Silveira de; Rabelo, Paulo Ney Pamplona [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due to the accident involving Cesium-137 are described, as well as the work of the IRD personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author) 4 refs., 11 figs.; e-mail: marcos at omega.lncc.br

  2. The communication of radiological risk to populations exposed to a radiological accident: considerations concerning the accident in Goiania

    International Nuclear Information System (INIS)

    Curado, M.P.

    1996-01-01

    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. (author)

  3. Study of 137 Cs contamination in Rochedo Reservoir, Meia Ponte river (Goias State) from the radiologic accident in Goiania

    International Nuclear Information System (INIS)

    De Luca, Marcia Emilia M.

    1997-01-01

    Through 137 Cs concentration profiles in sediments from Rochedo Reservoir, it was possible to estimate the amount of this radionuclide (94 GBq) which has reached the Meia Ponte River system, as a consequence of the Goiania radiological accident in 1987. Based on in-situ measurements as well as on laboratory studies, the influence of N H 4 + concentration on the K d value was also investigated. The results have shown that for high N H 4 + concentrations there is a clear correlation between both parameters. It was also observed the influence on the aging effect on the 137 Cs release from the sediment, as well as of the illite content in it. (author)

  4. Subsidies to cytogenetic dosimetry technique generated from analysis of results of Goiania radiological accident

    International Nuclear Information System (INIS)

    Ramalho, Adriana Teixeira

    1993-06-01

    Following the Goiania radiation accident, which occurred in September of 1987, peripheral lymphocytes from 129 exposed or potentially exposed individuals were analyzed for the frequency of unstable chromosomal aberrations (dicentrics and centric rings) to estimate absorbed radiation dose. During the emergency period, the doses were assessed to help immediate medical treatment. After this initial estimation, doses were reassessed using in vitro calibration curves produced after the accident, more suitable for the conditions prevailing in Goiania. Dose estimates for 24 subjects exceeded 0,5 Gy. Among those, 15 individuals exceeded 1,0 Gy and 5 exceeded 3,0 Gy. None of the estimates exceeded 6,0 Gy. Four of the subjects died. During the emergency period, a cytogenetic follow-up of 14 of the exposed patients was started, aiming to observe the mean lifetime of lymphocytes containing dicentric and ring aberrations. The results suggest that for the highly exposed individuals the disappearance rate of unstable aberrations follows a two- term exponential function. Up to 470 days after the exposure, there is a rapid fall in the aberration frequency. After 470 days, the disappearance rate is very slow, almost constant. The estimated average half-time of elimination of dicentrics and rings among the highly exposed group (> 1 Gy) was 140 days for the initial period after the exposure (up to 470 days). This value is significantly shorter than the usually accepted value of 3 years reported in the literature. Mean disappearance functions of unstable chromosome aberrations were inferred, to be applied in accident situations in which there is a blood sampling delay. Statistical analysis of possible correlations between the individual half-times and biological parameters, such as sex, age, leukopenia level shown during the critical period, absorbed dose (initial frequency of chromosomal aberrations) and the administration of the bone marrow stimulating factor (rHuGM-CSF) was

  5. Medical follow up of ten patients victims of the radiological accident occurred in Goiania, Goias State, Brazil 1988/1992; Acompanhamento clinico de dez pacientes vitimas do acidente radiologico de Goiania - 1988/1992

    Energy Technology Data Exchange (ETDEWEB)

    Curado, M.P.; Morais, M.S.A.; Silva, J.F.; Assis, P.R.; Oliveira, A.R.; Santos, E.A

    1992-12-31

    The author makes an update of the medical aspects of ten victims of the radiological accident occurred in Goiania in September 1987. These patients received specialized treatment during the critical phase at Marcilio Dias Naval Hospital in Rio de Janeiro. Actually these patients are under medical follow-up at Leide das Neves Ferreira Foundation since march 1988. The clinical, haematological and laboratorial results are presented and discussed. The importance of a close medical follow-up direct victims of a radiological accident is stressed. (author) 13 refs., 5 tabs., 2 graphs.

  6. Report of the radiological protection procedures adapted in the Goiania General Hospital for assistance to the victims of the radiological accident with Cesium 137

    International Nuclear Information System (INIS)

    1989-08-01

    A caesium-137 capsule, illegal removed from a desactivated health center of the Instituto Goiano de Radioterapia, was disrupted causing a serious radiological accident. The dimensions of the accident were worsened due to some facts such as: the caesium-137 was in the chloride from, which is a very soluble compound the accident was notify to the competent authorities only several days after the capsule was removal and during this period of time some people handled the souce directly, without knowing its potential danger. This paper descibes the measures adopted in the Goiania General Hospital to restrict the exposure of workers and members of the public and to minimize the consequences of unavoidable exposures in such a way to assure that the annual dose limits were not exceeded. An efficiency evaluation of the methods adopted for the decontamination of the victims was made and its described in the report. (author) [pt

  7. Dermatological consequences of the Cs-137 radiological accident in Goiania, Goias State, Brazil

    International Nuclear Information System (INIS)

    Castro, Lia Candida Miranda de

    1996-01-01

    The objective of the present study was to analyse the occurrence of dermatosis in individuals that had been exposed to cesium 137 during the radioactive accident in Goiania, in 1987 and detect pre-cancerous dermatosis or those predictive of low immunity. The groups were evaluated according to the intensity of radiation they had been exposed to and then compared to a control group of people not exposed to radiation. The population exposed to the cesium 137 was comprised of 109 people, who were divided into Groups I and II, according to the CNEN norms. In group I, 54 people with ≤ 20 rads exposure and/or radio lesion were included; in group II, 55 people with > 20 rads exposure were included, along with the children of group I individuals. This was a historic cohort study, that is, a retrospective study that lasted 9 years, extending from September of 1987 to August, 1996. The presence of the oncoprotein p-53 was studied in the radio lesions of 10 patients. There is no evidence of an increase in the incidence of dermatosis in the exposed groups, excepts for pyoderma in patients with radio lesions. The most frequent dermatosis were: pyoderma, pityriasis versicolor, scabies, dermatophytosis and seborrhoeic dermatitis. The results obtained were not statistically significant for the evaluation of dermatosis predictive of low immunity or precancerous lesions. The oncoprotein p-53 in individuals with radio lesion showed a 80% positivity rate and risk factor estimated in 8 times, for the test. It has proved to be useful because it represents one more option in terms of propaedeutic evaluation and suggests that one should pay close and continuous attention in order to better control the evolution of these individuals. (author)

  8. Early measurements after the Goiania accident

    International Nuclear Information System (INIS)

    Godoy, J.M.; Moreira, M.C.F.; Fonseca, E.S. da

    2000-01-01

    During the early, intermediate late phase of the Goiania radiological accident different survey methods were applied involving aerial and terrestrial (using a car and directly in the field) inspections. The present work aims to show how and when they were and the obtained results. Furthermore, the 137 Cs concentration in soils were determined using a NaI(Tl) spectrometer during the accident, and also in Rio de Janeiro in a high resolution gamma spectrometry system. The concordance among those results and the validity of the 137 Cs measurements in soil with NaI(TI) are demonstrated. (author)

  9. The influence of Goiania radiological accident on Brazilian public opinion concerning new nuclear electric plants; A influencia do acidente radiologico de Goiania na aceitacao publica de novas usinas nucleoeletricas

    Energy Technology Data Exchange (ETDEWEB)

    Meldonian, Nelson Leon; Mattos, Luis Antonio Terribile de [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Grupo de Energia e Ambiente

    1997-12-31

    The Brazilian society is against applications of nuclear energy, mainly respecting to construction of new nuclear power plants, believing that they are harmful to population`s welfare and the environment. By this reason, Brazilian nuclear sector would promote a more intensive program of public discussion, not limited to technical and scientific community. Intending to contribute to a better judgment by society about the differences between diverse employment of nuclear energy, arguments concerned to its benefits are presented, pointing out that adverse accounts to nuclear electricity based on Goiania radiological accident, are not justified 10 refs., 5 tabs.; e-mail: meldonia at net.ipen.br

  10. Cytogenetic follow-up of patients exposed, 7.5 years after radiological accident in Goiania, Brazil; Sete anos e meio de acompanhamento citogenetico de pacientes expostos no acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Ramalho, Adriana T. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1996-07-01

    Ten persons exposed to {sup 137} Cs during the radiological accident in Goiania (Brazil) were reexamined for the frequency of unstable chromosomal aberrations (dicentric chromosomes, centric rings and acentric fragments) 7.5 years the first examination. It was found that the frequencies fell to about 5% of the initial values, for those individuals who had been exposed to moderate to high doses. For the subjects exposed to low doses, of the order of 0.2 Gy or less., the observed frequencies of chromosomal aberrations fell much more slowly. (author)

  11. Report of the activities carried out by the Psychological Support Group in the Goiania radiological accident in Brazil; Relatorio de atividades desenvolvidas pelo Nucleo de Apoio Psicologico da Rua 57

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The report analyzes the characteristics and attitudes of the population directly involved in the Goiania radiological accident. The inhabitants of the affected area were interviewed in their residence. Factual information about the accidents were given and specific psychological support were received whenever necessary 11 tabs.

  12. Report of the psychological support given to victims of the Goiania radiological accident in Brazil; Relatorio das atividades desenvolvidas pela Psicologia no Hospital Geral de Goiania (HGC) e CRF (FEBEM) com as vitimas diretas do Cesio-137

    Energy Technology Data Exchange (ETDEWEB)

    Nunes, Lenice Cruvinel; Pereira, Maria Emilia Pontes

    1988-02-01

    The psychological support given to the victims of the Goiania accident are described. The assistance lasted two months on the average and was given while the victims were in the hospital and later on in the recuperation center 1 tab.

  13. Psychosocial aspects of the victims of the accident with caesium-137 in Goiania (1987-1994)

    Energy Technology Data Exchange (ETDEWEB)

    Curado, M P [Fundacao Leide das Neves Ferreira, Goias (Brazil); Costa Neto, S B [Universidade de Brasilia, Instituto de Psicologia, Rio de Janeiro (Brazil)

    2000-05-01

    In September of 1987 two men took possession of and violated a source containing Caesium-137, which caused the Radiological Accident of Goiania. Besides the direct victims, a significant part of the community of Goiania was directly involved with this accident. The psychosocial impact in the social groups involved in this radiological accident - the population as a whole, immediate neighbours of contaminated sites, professionals and the victims themselves - gave rise to specific behaviour and attitudes which will be discussed in this paper. (author)

  14. Psychosocial aspects of the victims of the accident with caesium-137 in Goiania (1987-1994)

    International Nuclear Information System (INIS)

    Curado, M.P.; Costa Neto, S.B.

    2000-01-01

    In September of 1987 two men took possession of and violated a source containing Caesium-137, which caused the Radiological Accident of Goiania. Besides the direct victims, a significant part of the community of Goiania was directly involved with this accident. The psychosocial impact in the social groups involved in this radiological accident - the population as a whole, immediate neighbours of contaminated sites, professionals and the victims themselves - gave rise to specific behaviour and attitudes which will be discussed in this paper. (author)

  15. Dermatological consequences of the Cs-137 radiological accident in Goiania, Goias State, Brazil; Repercussoes dermatologicas no acidente radioativo com o Cesio 137 em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Castro, Lia Candida Miranda de

    1996-07-01

    The objective of the present study was to analyse the occurrence of dermatosis in individuals that had been exposed to cesium{sup 137} during the radioactive accident in Goiania, in 1987 and detect pre-cancerous dermatosis or those predictive of low immunity. The groups were evaluated according to the intensity of radiation they had been exposed to and then compared to a control group of people not exposed to radiation. The population exposed to the cesium{sup 137} was comprised of 109 people, who were divided into Groups I and II, according to the CNEN norms. In group I, 54 people with {<=} 20 rads exposure and/or radio lesion were included; in group II, 55 people with > 20 rads exposure were included, along with the children of group I individuals. This was a historic cohort study, that is, a retrospective study that lasted 9 years, extending from September of 1987 to August, 1996. The presence of the oncoprotein p-53 was studied in the radio lesions of 10 patients. There is no evidence of an increase in the incidence of dermatosis in the exposed groups, excepts for pyoderma in patients with radio lesions. The most frequent dermatosis were: pyoderma, pityriasis versicolor, scabies, dermatophytosis and seborrhoeic dermatitis. The results obtained were not statistically significant for the evaluation of dermatosis predictive of low immunity or precancerous lesions. The oncoprotein p-53 in individuals with radio lesion showed a 80% positivity rate and risk factor estimated in 8 times, for the test. It has proved to be useful because it represents one more option in terms of propaedeutic evaluation and suggests that one should pay close and continuous attention in order to better control the evolution of these individuals. (author)

  16. 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)

  17. Cesium-137 accident lessons in Goiania, Goias State, Brazil

    International Nuclear Information System (INIS)

    1990-11-01

    This document relates the experience obtained by several professionals which had an important role in the cesium-137 accident occurred in Goiania, Goias State, Brazil in September, 1987. It's divided into chapters, according to the action area - medical, nursing, social assistance, odontological and psychological. At first, some notions of radioprotection are explained, followed by the accident history and by the doctors and nurses action during the emergency phase and the medical, odontological, social and psychological assistance to the victims. The social assistance report shows some statistical data about the economic, occupational and social conditions of the accident victims. It is shown some information about the health institutions and the sanitary care in the ionizing radiation and about the occupational radiological protection in Goiania

  18. The early medical response to the Goiania accident

    International Nuclear Information System (INIS)

    Valverde, N.J.; Oliveira, A.R.

    2000-01-01

    The Goiania accident was the most severe radiological one that ever happened in the western hemisphere. The response to its human, social, environmental, economical and psychological burdens represented a huge challenge. Thanks to a multi-institutional intervention the consequences of the accident were greatly minimised. The medical response followed the same pattern and was based on a three-level system of progressive assistance. The early medical response encompassed medical and 'radiological' triage, admission to a specially prepared ward of a local hospital and treatment at a reference center in Rio de Janeiro. (author)

  19. The radiological accident of Goiania and the acceptance by the public of new nuclear power plants; El accidente radiologico de Goiania y la aceptacion publica de nuevas centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Meldonian, N L; Mattos, L A.T. [Grupo de Energia e Ambiente, Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil)

    1998-12-01

    Misunderstandings on the peaceful uses and the safety of nuclear energy have been a leading cause of apprehension in Brazilian public opinion. A lack of knowledge of the characteristics and destination of radioactive wastes and negative media coverage of the use of nuclear energy have aggravated this situation. Believing that applications of nuclear energy are harmful to the population`s welfare and the environment, Brazilian public opinion is opposed to the utilization of nuclear energy, and in particular to the construction of new nuclear power plants. For this reason, the Brazilian nuclear sector should promote a more intensive programme of public discussion, directed not solely at the technical and scientific communities, but also at the Brazilian public at large. Such a campaign would contribute towards a better understanding by Brazilian society of the different uses of nuclear energy and would present arguments in support of the benefits of this form of energy. Moreover, a campaign of this kind would show that negative associations about the use of electricity derived from nuclear power, which are based on the Goiania radiological accident, are not justified. (author) 10 refs, 5 tabs

  20. Consequences of radiological emergencies at Goiania and Mayapuri

    International Nuclear Information System (INIS)

    Sharma, Ranjit; Pradeepkumar, K.S.; Singh, Rajvir

    2012-01-01

    Radiological accidents due to orphan sources can lead to emergencies in the public domain, as reported worldwide. Inadequate regulatory control, lack of accountability and improper disposal of radioactive materials in scrap have resulted in radiological emergencies. Apart from few fatalities, they lead to environmental contamination, economic loss and social and psychological impact on the society. The 137 Cs and 60 Co sources of strength TBq to PBq activity level may pose high radiation exposure risk if shielding integrity is affected in any accident. There had been few radiological accidents reported world over which resulted in radiation injuries, environmental contamination and out of proportion panic in the society. The response actions for both these radiological emergencies included search, recovery of sources, decontamination and waste removal for reducing the radiation/contamination levels at the affected site. In both cases, encapsulated sources were damaged by the persons unknowingly. Response operations were carried out for longer period at Goiania compared to Mayapuri because of large scale contamination. 60 Co source being metallic in nature, even after the breaking of sources at Mayapuri the spread of contamination was confined to a small area. In Goiania, the granules of Cesium Chloride were distributed to many people because of its glowing nature in dark which caused spread of contamination to a large area and the accident was detected early as more persons reported with radiation injuries. The detection of Mayapuri accident was delayed as affected personnel reported to the hospital after three weeks of exposure to radiation. The lack of expertise in identifying radiation injuries by medical professionals contributed to further delay in reporting and detection of this emergency. The fatalities in both accidents resulted from acute radiation exposures and delay in getting medical support. The experience gained at radiological emergencies of Goiania

  1. Cesium-137: psychological and social consequences of the Goiania's accident

    International Nuclear Information System (INIS)

    Helou, Suzana; Costa Neto, Sebastiao Benicio da

    1995-01-01

    The book care for radioactive accident occurred in 1987 in Goiania - brazilian city. The accident had origin by the hospitable equipment incorrect handling which contained a stainless steel capsule, in which interior there was cesium-137 chloride. The main boarded aspects are: psychological and social aspects verified after the accident; psychological and social analysis of population of Goiania three years after the accident; essay on the pertinence of Luscher's abbreviate test in psychological evaluation of the radioactive accident victims of Goiania; and psychological and mobile evaluation of intra-uterus children exposed to the radiation with cesium-137

  2. Psychological and social aspects verified after the Goiania's radioactive accident

    International Nuclear Information System (INIS)

    Helou, Suzana

    1995-01-01

    Psychological and social aspects verified after the radioactive accident occurred in 1987 in Goiania - brazilian city - are discussed. With this goal was going presented a public opinion research in order to retract the Goiania's radioactive accident residual psychological effects. They were going consolidated data obtained in 1.126 interviews. Four involvement different levels groups with the accident are compared with regard to the event. The research allowed to conclude that the accident affected psychologically somehow all Goiania's population. Besides, the research allowed to analyze the professionals performance quality standard in terms of the accident

  3. Cesium-137 accident lessons in Goiania, Goias State, Brazil; Licoes do acidente com cesio-137 em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-11-01

    This document relates the experience obtained by several professionals which had an important role in the cesium-137 accident occurred in Goiania, Goias State, Brazil in September, 1987. It`s divided into chapters, according to the action area - medical, nursing, social assistance, odontological and psychological. At first, some notions of radioprotection are explained, followed by the accident history and by the doctors and nurses action during the emergency phase and the medical, odontological, social and psychological assistance to the victims. The social assistance report shows some statistical data about the economic, occupational and social conditions of the accident victims. It is shown some information about the health institutions and the sanitary care in the ionizing radiation and about the occupational radiological protection in Goiania. 38 refs., 8 tabs.

  4. CETESB's actions in Goiania in what concerns cesium-137 accident

    International Nuclear Information System (INIS)

    Penteado Filho, Azor Camargo; Derisio, Jose Carlos; Albuquerque, Antonio Martins de

    1991-01-01

    This work presents several actions performed by CETESB, the sanitary engineering agency of Sao Paulo State - Southeast Brazil, in what concerns the accident involving cesium-137 in Goiania, Goias State - Center Brazil. The adopted procedures are described in details

  5. Radiological survey of Goiania by a mobile monitoring unit

    International Nuclear Information System (INIS)

    Moreira, M.C.F.

    1989-01-01

    After the initial response to the radiological accident in Goiania, a radiological survey throughout the city was performed using a mobile unit. This unit was equipped with two Geiger Muller detectors outsise the vehicle and one 4' x 4' NaI(Tl) detector connected to a dual recorder. All three detectors were placed 1 m above the ground. The survey system covers a wide range of exposure rate, since environmental levels up to 10 R h -1 . Eighty percent of the Goiania urban area was covered by this survey and except for some specific locations the contamination was restricted to the main foci surroundings ocurring in a non homogenous pattern. The highest value observed in the city after the main foci decontamination was of 0.7 mR h -1 in the 57 th street - where the source was opened. Results of the main foci and some other locations are apresented in the paper. The system designed to perform the survey in the city played a fundamental role during the decontamination process (author) [pt

  6. Localized lesions induced by 137Cs during the Goiania accident

    International Nuclear Information System (INIS)

    Oliveira, A.R.; Brandao-Mello, C.E.; Valverde, N.J.; Farina, R.; Curado, M.P.

    1991-01-01

    A description is given of initial symptoms and clinical observations regarding acute localized radiation lesions in 28 persons exposed to 137Cs during the Goiania radiological accident. Specialized procedures to estimate the extent and gravity of the lesions and establish a therapeutic strategy, as well as to anticipate the prognosis in each case, are briefly discussed. Measures taken for reduction of pain and inflammation are noted, and an explanation is given for difficulties encountered due to adverse working conditions and the serious clinical manifestations presented by various patients concomitantly with their lesions. Also noted is the difficulty in obtaining credible information regarding exposure, such as source-to-object distance, duration of exposure, and source activity, which precluded dosimetry studies in most cases

  7. Subsidies to cytogenetic dosimetry technique generated from analysis of results of Goiania radiological accident; Subsidios a tecnica de dosimetria citogenetica gerados a partir da analise de resultados obtidos com o acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Ramalho, Adriana Teixeira

    1993-06-15

    Following the Goiania radiation accident, which occurred in September of 1987, peripheral lymphocytes from 129 exposed or potentially exposed individuals were analyzed for the frequency of unstable chromosomal aberrations (dicentrics and centric rings) to estimate absorbed radiation dose. During the emergency period, the doses were assessed to help immediate medical treatment. After this initial estimation, doses were reassessed using in vitro calibration curves produced after the accident, more suitable for the conditions prevailing in Goiania. Dose estimates for 24 subjects exceeded 0,5 Gy. Among those, 15 individuals exceeded 1,0 Gy and 5 exceeded 3,0 Gy. None of the estimates exceeded 6,0 Gy. Four of the subjects died. During the emergency period, a cytogenetic follow-up of 14 of the exposed patients was started, aiming to observe the mean lifetime of lymphocytes containing dicentric and ring aberrations. The results suggest that for the highly exposed individuals the disappearance rate of unstable aberrations follows a two- term exponential function. Up to 470 days after the exposure, there is a rapid fall in the aberration frequency. After 470 days, the disappearance rate is very slow, almost constant. The estimated average half-time of elimination of dicentrics and rings among the highly exposed group (> 1 Gy) was 140 days for the initial period after the exposure (up to 470 days). This value is significantly shorter than the usually accepted value of 3 years reported in the literature. Mean disappearance functions of unstable chromosome aberrations were inferred, to be applied in accident situations in which there is a blood sampling delay. Statistical analysis of possible correlations between the individual half-times and biological parameters, such as sex, age, leukopenia level shown during the critical period, absorbed dose (initial frequency of chromosomal aberrations) and the administration of the bone marrow stimulating factor (rHuGM-CSF) was

  8. A psychological analysis of the rehabilitation of the Goiania accident victims

    International Nuclear Information System (INIS)

    Costa Neto, S.B. da

    1992-01-01

    This paper brings out a psycho social analysis of the consequences of the radiologic accident of Goiania-Brazil, verified especially among its direct victims. It makes clear the psychological aspects shown by the isolated victims (hospitalized and sheltered) and the psycho therapeutic processes used by the Psychology Department. After all that study, it is clear the need of specific training for health professionals necessary for the regards and multi professional and interdisciplinary attendance to the victims Goiania. It is also important a unity of institutional objectives such as essential conditions for the rehabilitation of the patients in its largest bio psycho social aspect. (author)

  9. Goiania's radioactive accident - Evolutive description two years after

    International Nuclear Information System (INIS)

    Lamarck, P. de; Almeida Lignelli, O.J. de; Sobrinho, A.B.

    1990-01-01

    The authors lead a brief review of three patients that undergone lesions caused by ionizing radiations at the Goiania's radioactive accident, two years after. They describe the actual conditions of the skin lesions, hematologic values, sequels, diagnostic and therapeutics procedures on the follow up of this patients. They still make a comparative study between nuclear weapon's victims at Hiroshima and Nagasaki events (2 sup(nd) World War) and Goiania accident s victims. In their conclusions, the authors point out the importance in detecting early lesions, diseases or late sequels, due to radioactive expositions. (author)

  10. The Goiania accident: release from hospital criterion

    International Nuclear Information System (INIS)

    Falcao, R.C.; Hunt, J.

    1990-01-01

    On the thirteenth of September 1987, a 1357 Ci Cesium source was removed from the 'Instituto de Radiologia de Goiania' - probably two or three days later the source was opened, causing the internal and external contamination of 247 people, and part of the city of Goiania. This paper describes the release from hospital criterion of the contaminated patients, based on radiation protection principles which were developed for this case. The estimate of the biological half-life for cesium is also described. (author) [pt

  11. Study of {sup 137} Cs contamination in Rochedo Reservoir, Meia Ponte river (Goias State) from the radiologic accident in Goiania; Estudo da contaminacao por {sup 137} Cs na Represa do Rochedo, Rio Meia Ponte (GO), proveniente do acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    De Luca, Marcia Emilia M. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Inst. de Biofisica; Godoy, Jose Marcos O. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Through {sup 137} Cs concentration profiles in sediments from Rochedo Reservoir, it was possible to estimate the amount of this radionuclide (94 GBq) which has reached the Meia Ponte River system, as a consequence of the Goiania radiological accident in 1987. Based on in-situ measurements as well as on laboratory studies, the influence of N H{sub 4}{sup +} concentration on the K{sub d} value was also investigated. The results have shown that for high N H{sub 4}{sup +} concentrations there is a clear correlation between both parameters. It was also observed the influence on the aging effect on the {sup 137} Cs release from the sediment, as well as of the illite content in it. (author) 9 refs., 6 figs.

  12. Radiation protection during the medical assistance to the victims of the accident in Goiania

    International Nuclear Information System (INIS)

    Silva, L.H.C.; Fajardo, P.W.; Rosa, R.

    1989-01-01

    Some of the casualities of the radiological accident occured in Goiania (Brazil), consequence of the violation of a Cs-137 source were assisted at Marcillo Dias Naval Hospital. The risks associated to the contact with the patients were radioactive contamination and external exposure. To deal with this problem, a Radiation Protection Group was formed and a Radiation Protection Program was developed and implemented in order to assure that risks would be maintained as low as reasonably achievable. The objective of this paper is to present the acquired experience on the radiation protection support in case of emergency medical assistance in radiological accidents. (author). 1 ref.; 2 tabs

  13. 30 years of the Goiania Accident: a comparative study with other radioactivity dispersion events

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Ricardo Bastos; Vicente, Roberto, E-mail: rbsmith@ipen.br, E-mail: rvicente@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The year 2017 marks 30 years since the radioactive accident that occurred in the city of Goiania, capital of the state of Goias. It was the largest radiological accident in Brazil, and one of the largest in the world occurring outside nuclear facilities. Regarding the accidents at nuclear power plants, two of the biggest were Chernobyl in Ukraine, a year and a half before Goiania, and the Fukushima accident in Japan, in 2011. Different amounts of radioactive material were dispersed in the environment in each of these events. However, each one’s main pathway of dispersion was different: the accident of Goiania was terrestrial, Chernobyl was at the atmosphere, and Fukushima was mainly in the ocean. This work aims to study these different amounts, comparing such activities. In addition, it proposes to compare the sea dispersion of Fukushima with the amount of radioactive waste dumped in the oceans, when the release of radioactive waste at sea was permitted. It also proposes to compare the Chernobyl aerial dispersion with the radioactive material dissipated in the atmosphere, resulting from the more than 500 atmospheric nuclear tests conducted between 1945 and 1962 by the United States, the former Soviet Union, England, France and China. (author)

  14. 30 years of the Goiania Accident: a comparative study with other radioactivity dispersion events

    International Nuclear Information System (INIS)

    Smith, Ricardo Bastos; Vicente, Roberto

    2017-01-01

    The year 2017 marks 30 years since the radioactive accident that occurred in the city of Goiania, capital of the state of Goias. It was the largest radiological accident in Brazil, and one of the largest in the world occurring outside nuclear facilities. Regarding the accidents at nuclear power plants, two of the biggest were Chernobyl in Ukraine, a year and a half before Goiania, and the Fukushima accident in Japan, in 2011. Different amounts of radioactive material were dispersed in the environment in each of these events. However, each one’s main pathway of dispersion was different: the accident of Goiania was terrestrial, Chernobyl was at the atmosphere, and Fukushima was mainly in the ocean. This work aims to study these different amounts, comparing such activities. In addition, it proposes to compare the sea dispersion of Fukushima with the amount of radioactive waste dumped in the oceans, when the release of radioactive waste at sea was permitted. It also proposes to compare the Chernobyl aerial dispersion with the radioactive material dissipated in the atmosphere, resulting from the more than 500 atmospheric nuclear tests conducted between 1945 and 1962 by the United States, the former Soviet Union, England, France and China. (author)

  15. Novel biodosimetry methods applied to victims of the Goiania accident

    International Nuclear Information System (INIS)

    Straume, T.; Langlois, R.G.; Lucas, J.; Jensen, R.H.; Bigbee, W.L.; Ramalho, A.T.; Brandao-Mello, C.E.

    1991-01-01

    Two biodosimetric methods under development at the Lawrence Livermore National Laboratory were applied to five persons accidentally exposed to a 137Cs source in Goiania, Brazil. The methods used were somatic null mutations at the glycophorin A locus detected as missing proteins on the surface of blood erythrocytes and chromosome translocations in blood lymphocytes detected using fluorescence in-situ hybridization. Biodosimetric results obtained approximately 1 y after the accident using these new and largely unvalidated methods are in general agreement with results obtained immediately after the accident using dicentric chromosome aberrations. Additional follow-up of Goiania accident victims will (1) help provide the information needed to validate these new methods for use in biodosimetry and (2) provide independent estimates of dose

  16. Nuclear law and radiological accidents

    International Nuclear Information System (INIS)

    Frois, F.

    1998-01-01

    Nuclear activities in Brazil, and particularly the radiological accident of Goiania, are examined in the light of the environmental and nuclear laws of Brazil and the issue of responsibility. The absence of legislation covering radioactive wastes as well as the restrictions on Brazilian States to issue regulations covering nuclear activities are reviewed. The radiological accident and its consequences, including the protection and compensation of the victims, the responsibility of the shareholders of the Instituto Goiano de Radioterapia, operator of the radioactive source, the provisional storage and the final disposal at Abadia de Goias of the radioactive waste generated by the accident are reviewed. Finally, nuclear responsibility, the inapplicability of the Law 6453/77 which deals with nuclear damages, and the state liability regime are analysed in accordance with the principles of the Brazilian Federal Constitution. (author)

  17. The 1987 radiation accident in Goiania: medical and organizational experiences

    International Nuclear Information System (INIS)

    Oliveira, A.R. de; Souza, P.C. de

    1989-12-01

    The present works describes the circumstances of the accident occurred on 13 September 1987, in Goiania (Brazil), when two scavengers removed a teletherapy device a 50.9 TB q (1375Ci) cesium source, from a clinic. They took the apparatus home and tried to dismantled it. The authors describe the circumstances of the event, the first aid measures taken on the site, and the medical structure organized to triage and treat the casualties. Aspects relating to hospital contamination control, the environment, and radioprotection and decontamination procedures are also discussed. (L.M.J.) [pt

  18. General medical and related aspects of the Goiania accident, Brazil

    International Nuclear Information System (INIS)

    Oliveira, A.R. de; Brandao-Melo, C.E.; Hunt, J.G.

    1988-01-01

    In a recent radiation accident occurred in the city of Goiania, central area of Brazil, approximately 250 people were exposed to a 137Cs source from a radiotherapy unit abandoned in a amedical clinic in that city. At least twelve patients showed some degree of bone marrow depression, from which eight developed the classical signs and symptoms of Acute radiation Syndrome (ARS). 28 people presented local radiation burns ranging from first to third degree. Around 100 people showed evidences of internal contamination due to the dissemination of the source powder. The authors describe the circumstances of the event, the first-aid measures taken at place, the criteria adopted during the triage of victims and the radiation protection procedures used during the management and treatment of the irradiated individuals. (author) [pt

  19. Nuclear laws and radiologic accidents

    International Nuclear Information System (INIS)

    Frois, Fernanda

    1997-01-01

    Some aspects of the nuclear activities in Brazil, specially concerning the Goiania s accident are demonstrated using concepts from environmental and nuclear law. Nuclear and environmental competence, the impossibility of the states of making regional laws, as the lack of regulation about the nuclear waste, are discussed. The situation of Goiania when the accident happened, the present situation of the victims and the nuclear waste provisionally stored in Abadia de Goias is reported

  20. Radiation protection measures applied during the autopsies on the casualties of the Goiania accident

    International Nuclear Information System (INIS)

    Martins, N.S.F.; Silva, L.H.C.; Rosa, R.

    1998-01-01

    The most seriously affected casualties of the radiological accident caused by the opening of a 137 Cs source capsule in Goiania were treated at the Marcilio Dias Naval Hospital (HNMD) in Rio de Janeiro in the period from October to December 1987. Four of the injured died in October. The autopsies were performed at this institution. Due to the external and internal contamination presented by these victims, specific radiation protection procedures were adopted to enable the medical team to perform their duties. The radiation protection staff, under the co-ordination of technicians of the Brazilian Nuclear Energy Commission (CNEN), were responsible for the preparation of the autopsy room and for advising the professionals on duty during these events. The radiation protection staff took specific measures to prevent the spread of contamination throughout the hospital, the contamination of persons attending the autopsies and to minimize any radiation dose to the medical and professional team. The measures aimed at personal control and the preparation of the autopsy room are described as well as the radiation protection steps applied in connection with the performance of the autopsies, the emplacement of the bodies into the coffins and their transport back to Goiania. (author)

  1. Recent evaluation of gamma radiation levels due to 137 Cs accident in Goiania

    International Nuclear Information System (INIS)

    Umisedo, Nancy K.; Okuno, Emico; Yoshimura, Elisabeth M.; Guimaraes, Carla C.; Facure, Alessandro; Anjos, Roberto Meigikos dos

    2001-01-01

    This paper presents recent results of thermoluminescence dosimetry (TLD) in two lots of Goiania, the city of central region of Brazil that was the local of one of the worst radiological accidents of the world, in 1987. The dosimeters used in this work are similar to those used in the Dosimetry Laboratory of Physics Institute of S. Paulo University in routine dosimetry. Fifteen environmental monitors were placed in air, one meter above the ground, at chosen locations of both lots during 56 days. Three persons that live and work at one of the lots were also monitored with personnel dosimeters. The highest value obtained for personal dose equivalent rate was 3.56 mSv/year and the values of ambient dose equivalent rate ranged from 2.31 to 12.47 mSv/year. (author)

  2. Radiometric evaluation of graves of victims of the accident with Cesium 137 in Goiania, GO, Brazil: 25 years after

    International Nuclear Information System (INIS)

    Lage, Leonardo B.; Correa, Rosangela da S.; Santos, Eliane E. dos; Freitas-Junior, Ruffo

    2013-01-01

    Twenty-five years after the radiation accident in Goiania, this study aims to evaluate the radiological situation in the area demarcated by the graves of the victims of the accident with cesium-137. Radiometric survey was carried out on the surface that encompasses the four graves and vicinity, from a pre-established mesh. Dose rate measurements were carried out, using the IdentFINDER equipment, positioned at 1 m height from the ground. The values of dose rates at the points measured ranged from 0.03 to 0.07 μSv/h. This variation of dose rate is less than those obtained in the local graveyard and are in the range of background radiation observed in Goiania. Considering the results obtained 25 years after the accident, it was concluded that engineering barriers adopted at that time are effective, stating the place absolutely safe from a radiological point of view, both for the individual from the public as to the environment

  3. Proceedings of the 2. International symposium on the radioactive accident in Goiania. Program

    International Nuclear Information System (INIS)

    1993-01-01

    This 2. International symposium on the radioactive accident with cesium-137 brings together in Goiania renowned international and Brazilian specialists. These are recognized professionals of Medicine, Physics, Biology and Psychology who, gathered around a strictly scientific event, will discuss the complex problems originated by a serious accident, exchanging experiences and searching for definite solutions for the issues. The main topics are: the environmental and social impacts; technical and medical procedures; victims contamination and biological radiation effects in the body of the victims

  4. The follow-up of in vivo measurements on the patients of the Goiania accident

    International Nuclear Information System (INIS)

    Oliveira, C.A.N.; Melo, D.R.; Dantas, B.M.; Nani, G.J.; Lipsztein, J.L.; Laurer, G.R.

    2000-01-01

    A radiological accident occurred in September 1987 in the city of Goiania, Brazil, due to violation of a 50.9 TBq 137 Cs source used for medical therapy. This accident resulted internal and external contamination as well as irradiation of members of the public. Some people had radiation bums after rubbing the fragments of the source on their skin. Successive skin decontamination were carried on until there was no external detection of $ radiation. In August 1990, with the objective of verifying the long term retention of Cs in the scares, a detection system to perform in vivo measurements in specific regions of the body, with enough sensitivity to discriminate surface and deep contamination, based on the ratio K α /K β ( 137m Ba characteristic X-rays) was set up in Goiania. This system was also used to obtain information of the distribution of residual activities of 137 Cs in the body, 3 years after the intake. The detector applied in this set of measurements system consisted of a HPGe type N, collimated with a 20 cm x 0.5 mm layer of cooper. Ten people were selected for this study based on their remaining 137 Cs body burden, which was obtained using a 8''x4'' NaI(Tl) detector, and on the presence of radiation bum scares. The selected individuals laid down on a thin matrix under the detection system. The HPGe was positioned over and close to the region of interest, which was different for each patient. Two of the subjects showed evidence of significant caesium activity still remaining in wound sites. These results were obtained through the detection of the 137m Ba characteristic X-rays from the decay of 137 Cs. Four of the 10 individuals measured exhibited high levels of X-ray activity in the surface area above the liver. The measurement of these low energy X-rays (30 keV) from an organ as deep in the body as the liver indicates a significant amount of activity in that organ and also that caesium is probably not homogeneously distributed. (author)

  5. Aerial radiometric surveying of Goiania city, Brazil, after the accident with Cs-137

    International Nuclear Information System (INIS)

    Barreto, P.M.C.; Fonseca, E.S. da

    1988-01-01

    A low altitude (40 m) aeroradiometric survey with an helicopter was carried out over Goiania city few days after the Cs-137 radiological accident was communicated to CNEN. The objective was to evaluate the extension of the contamination. All the urban area plus dwellings centers in the outskirts of the city as well as drainage systems were surveyed in two days of operation. A total of 67 million m 2 were evaluated. This survey found out only one contamination point (1.1 R/h) which was not yet identified by the ground crews. No contamination was found in the Capin Puba Creek and Meia Ponte river. Detection tests at differen heights over the main contamination points showed that Cs-137 radiation could be detected at more than 350m above them. The results demonstrated that the contamination was restricted to points in the neighbourhood of the junkyard where the source was violated. Such points were under the control of CNEN personnel. The advantages of the airbone technique was to cover a large area in short time. The non-existence of a regional contamination was an important fact to calm the population and the Government. (author) [pt

  6. Psychological and social analysis of population of Goiania three years after the accident with the cesium-137

    International Nuclear Information System (INIS)

    Helou, Suzana; Costa Neto, Sebastiao Benicio da; Curado, Maria Paula

    1995-01-01

    Psychological and social analysis of population of Goiania - Brazilian city - three years after the accident with the cesium-137 occurred in 1987 are discussed. With this goal it is presented a public opinion research in order to retract the Goiania's radioactive accident residual psychological effects. The public opinion research was analyzed in sum individual answers terms, considering the factors multiplicity to what the individuals are exposed in the society. It was adopted Cabral's and Nick's concepts

  7. Radiological accident of cesium-137 in brazil activities of surveillance and decontamination

    International Nuclear Information System (INIS)

    Nakajima, Toshiyuki

    1989-01-01

    In 1987, a serious radiological accident occurred in Goiania, Brazil. Four inhabitants died and about 250 persons were internally or externally contaminated with 137 Cs released from a removed and then broken source vessel. In this report, outline of the accident and, activities on surveillance of contamination and works for decontamination are described. (author)

  8. Radiological attacks and accidents. Medical consequences

    International Nuclear Information System (INIS)

    Sakuta, Hidenari

    2007-01-01

    Probability of the occurrence of radiological attacks appears to be elevated after the terrorist attacks against the United States on September 11 in 2001. There are a lot of scenarios of radiological attack: simple radiological device, radiological disperse device (RDD or dirty bomb), attacks against nuclear reactor, improvised nuclear device, and nuclear weapons. Of these, RDD attack is the most probable scenario, because it can be easily made and can generate enormous psychological and economic damages. Radiological incidents are occurring to and fro in the world, including several cases of theft to nuclear facilities and unsuccessful terrorist attacks against them. Recently, a former Russian spy has allegedly been killed using polonium-210. In addition, serious radiological accidents have occurred in Chernobyl, Goiania, and Tokai-mura. Planning, preparation, education, and training exercise appear to be essential factors to cope with radiological attacks and accidents effectively without feeling much anxiety. Triage and psychological first aid are prerequisite to manage and provide effective medial care for mass casualties without inducing panic. (author)

  9. Radiometric evaluation of graves of victims of the accident with Cesium 137 in Goiania, GO, Brazil: 25 years after; Avaliacao radiometrica das sepulturas das vitimas do acidente com o Cesio 137 em Goiania: 25 anos apos

    Energy Technology Data Exchange (ETDEWEB)

    Lage, Leonardo B.; Correa, Rosangela da S.; Santos, Eliane E. dos, E-mail: leonardobl@cnen.gov.br, E-mail: rcorrea@cnen.gov.br, E-mail: esantos@cnen.gov.br [Centro Regional de Ciencias Nucleares do Centro-Oeste (CRCN-CO/CNEN-GO), Abadia de Goias, GO (Brazil); Freitas-Junior, Ruffo, E-mail: uffojr@terra.com.br [Universidade Federal de Goias (UFG), Goiania, GO (Brazil). Faculdade de Medicina. Programa de Mastologia

    2013-07-01

    Twenty-five years after the radiation accident in Goiania, this study aims to evaluate the radiological situation in the area demarcated by the graves of the victims of the accident with cesium-137. Radiometric survey was carried out on the surface that encompasses the four graves and vicinity, from a pre-established mesh. Dose rate measurements were carried out, using the IdentFINDER equipment, positioned at 1 m height from the ground. The values of dose rates at the points measured ranged from 0.03 to 0.07 μSv/h. This variation of dose rate is less than those obtained in the local graveyard and are in the range of background radiation observed in Goiania. Considering the results obtained 25 years after the accident, it was concluded that engineering barriers adopted at that time are effective, stating the place absolutely safe from a radiological point of view, both for the individual from the public as to the environment.

  10. Lessons from Goiania

    International Nuclear Information System (INIS)

    Nazari Alves, R.

    2000-01-01

    The lessons learned from the radiological accident of Goiania in 1987 derived from the observations from the Regulatory Agency which was in charge of the decontamination tasks may be consolidated into four classes: Preventive Actions, characterised as those that aim to minimise the probability of occurrence of a radiological accident; Minimisation of time between the moment of the accident occurrence and the beginning of intervention, in case a radiological accident does occur, despite all preventive measures; Intervention, which is correlated to the type of installation, its geographical location, the social classes involved and their contamination vectors; and Follow up, for which well established rules to allow continuing monitoring of the victims and rebuilding of homes are necessary. The greatest lesson of all was the need for integration of the professionals involved, from all organizations. (author)

  11. Planning the medical response to radiological accidents

    International Nuclear Information System (INIS)

    1998-01-01

    Radioactive substances and other sources of ionizing radiation are used to assist in diagnosing and treating diseases, improving agricultural yields, producing electricity and expanding scientific knowledge. The application of sources of radiation is growing daily, and consequently the need to plan for radiological accidents is growing. While the risk of such accidents cannot be entirely eliminated, experience shows that most of the rare cases that have occurred could have been prevented, as they are often caused by human error. Recent radiological accidents such as those at Chernobyl (Ukraine 1986), Goiania (Brazil 1987), San Salvador (El Salvador 1989), Sor-Van (Israel 1990), Hanoi (Viet Nam 1992) and Tammiku (Estonia 1994) have demonstrated the importance of adequate preparation for dealing with such emergencies. Medical preparedness for radiological accidents must be considered an integral part of general emergency planning and preparedness and established within the national framework for radiation protection and safety. An IAEA Technical Committee meeting held in Istanbul in 1988 produced some initial guidance on the subject, which was subsequently developed, reviewed and updated by groups of consultants in 1989, 1992 and 1996. Special comments were provided by WHO, as co-sponsor of this publication, in 1997. This Safety Report outlines the roles and tasks of health authorities and hospital administrators in emergency preparedness for radiological accidents. Health authorities may use this document as the basis for their medical management in a radiological emergency, bearing in mind that adaptations will almost certainly be necessary to take into account the local conditions. This publication also provides information relevant to the integration of medical preparedness into emergency plans

  12. Whole body monitoring - Goiania

    International Nuclear Information System (INIS)

    Oliveira, C.A.N. de; Lourenco, M.C.; Bertelli Neto, L.; Lucena, E.A. de; Becker, P.H.B.

    1988-01-01

    Due to the radiological Cs accident in Goiania, Goias in September 1987, it became necessary to evaluate internal contamination levels of: - Individual from the general public that for any reason had direct or indirect involvement with the radioactive source (group 1). - Occupationally involved persons (group 2). For each of these groups, procedures of whole body monitoring were developped. In order to attend group 1 individuals, the IRD/CNEN installed a whole body unit in the INAMPS General Hospital of Goiania in 11.08.87, which was later transferred to 121,57 street, Central Sector in Goiania in 2.06.88. In this unit 547 people were monitored, 356 from group 1 and 241 from group 2, until 04.13.88. In the IRD whole body counter installation, 194 individuals were counted, 185 from group 2 and 9 from group 1. The frequency of monitoring of each individual was established according to the Cs activity present in the body or to the job to be assigned. In this paper we will present some burden activity curves for Cs 137 as a function of the time elapsed from the first measurement. There people from group 1 were measured in both counters, the IRD and the Goiania ones. The values obtained in both installations are compatible with the body activity x time curve. (author) [pt

  13. Radiological accidents in medical practice

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan

    2012-01-01

    Different radiological accidents that may occur in medical practice are shown. The following topics are focused: accident statistics for medical exposure, accidental medical exposures, radiotherapy accidents and potential accidental scenarios [es

  14. Mortal radiological accident

    International Nuclear Information System (INIS)

    Gimenez, J.C.

    1987-01-01

    After defining the concept of 'Radiological accident', statistical data from Radiation Emergency Assistance Center of ORNL (United States of America) are given about the deaths caused by acute irradiation between 1944 and April 24, 1986 -ie, the day before Chernobyl nuclear accident- as well as on the number of deaths caused by the latter. Next the different clinical stages of the Acute Irradiation Syndrome (AIS) as well as its possible treatment are described, and finally the different physical, clinical and biological characteristics linked to the AIS and to its diagnosis and prognosis are discussed. (M.E.L.) [es

  15. The fate of chromosomal aberrations in 137Cs-exposed individuals in the Goiania radiation accident

    International Nuclear Information System (INIS)

    Ramalho, A.T.; Nascimento, A.C.

    1991-01-01

    Following the Goiania radiation accident, lymphocytes from 110 exposed or potentially exposed individuals were analyzed for the frequencies of chromosomal aberrations (dicentrics and centric rings) to estimate absorbed radiation dose. Dose estimates for 21 subjects exceeded 1.0 Gy, and for eight subjects they exceeded 4.0 Gy. Four of the subjects died. After the emergency period, a cytogenetic follow-up of 10 of the highest exposed patients was started. The results suggest that the average disappearance half-time of lymphocytes containing dicentric and centric rings was 130 d, which is shorter than the usually accepted value of 3 y reported in the literature

  16. Evaluation of Sao Paulo population knowledge about nuclear energia and radioactive wastes. Did the Goiania accident rise any interest ?

    International Nuclear Information System (INIS)

    Rzyski, Barbara M.; Sartori, Carla E.

    1997-01-01

    The results of the inquire collected in 1996, about 10 years after Goiania accident, regarding to the knowledge of nuclear energy and rad wastes are presented. The survey was performed among university students and the population of the Sao Paulo city, of all social levels and different ages. The results show that people between 45 and 55 years are more receptive to the matter. It was observed that the major part of the information absorbed by the public arise form news divulged by newspapers and some spread facts, in cases of incidents or accidents as was Goiania

  17. Essay on the pertinence of Luscher's abbreviate test in psychological evaluation of the radioactive accident victims of Goiania

    International Nuclear Information System (INIS)

    Costa Neto, Sebastiao Benicio da

    1995-01-01

    The essay on the pertinence of Luscher's abbreviate test in psychological evaluation of the radioactive accident victims of Goiania - Brazilian city - occurred in 1987 is consequence of confront of data obtained in two distinct situations having for criterion: time, efficiency and pertinence. Besides of this, they are introduced palografic and the house-tree-person - HTP - tests. These tests aimed at the common psychological characteristics verification to radioactive accident victims' personality of Goiania and to the data existential moment for those people. Among the three tests, the one of Luscher was what obtained the best interviewees acceptance index

  18. Revisiting the Goiania Accident: Medical and Dosimetric Experiences

    International Nuclear Information System (INIS)

    Oliveira, A.R.; Valverde, C.E.; Brandao Mello, N.J.L.; Almeida, C.E.V.

    1998-01-01

    Retrospective dosimetry can be accomplished by means of a physical reconstruction using mathematical or anthropomorphic phantoms or biological or clinical indicators. Biological dosimetry, based on biochemical, cytological and cytogenetic indicators, reduces the uncertainties in dose estimation. Micronuclei, PCC and FISH are techniques now available to radiobiologists and radiation specialists, which will complement the role played by conventional cytogenetics. After the Chernobyl accident, reliance was on various bioclinical dosemeters, such as the onset of vomiting, lymphocytes and neutrophils and biochemical indicators. The onset of prodromal manifestations, haematological behaviour and other indicators presented by eight caesium patients were analysed and correlated with the biological dosimetry performed immediately after the accident. Clinical and haematological indicators matched to a good extent with the cytogenetic dosimetry performed in Brazil and the USA. It was concluded that in an accident involving the public, retrospective dosimetry could be helpful in aiding dose estimation and also in validating dosimetry established by conventional physical and biological techniques. (author)

  19. Comparative evaluations of surface contamination detectors calibration with radioactive sources - used in the Goiania accident, and standard sources

    International Nuclear Information System (INIS)

    Becker, P.H.B.; Marecha, M.H.H.

    1997-01-01

    The construction of Cs-137 standard flat sources for calibration of surface contamination detectors, used in the Goiania accident in 1987, is described and the procedures adopted are reported. At that time, standard sources were not available. Nowadays the Instituto de Radioprotecao e Dosimetria has standard sources acquired from Amersham which are used as calibration standards for surface contamination detectors. Comparative evaluations between the standard flat sources constructed for the accident and the calibrated ones are presented

  20. Goiania radiation accident: activities carried out and lessons learned based on personal experience

    International Nuclear Information System (INIS)

    Silva, F.C.A. da

    2017-01-01

    Goiânia Radiological Accident, on September 13, 1987, with a radioactive source of cesium-137 with 50.9 TBq, used in radiotherapy, is one of the most important accidents in the scientific area, representing a milestone for all workers in the areas of radiation protection and radiological emergency that worked during the event. A personal view of the Goiânia Radiological Accident is presented, showing some activities carried out in contaminated areas and lessons learned based on own experience during the event

  1. Evaluation of Sao Paulo population knowledge about nuclear energia and radioactive wastes. Did the Goiania accident rise any interest ?; Avaliacao do conhecimento da populacao paulistana sobre a energia nuclear e os rejeitos radioativos. O acidente de Goiania despertou o interesse?

    Energy Technology Data Exchange (ETDEWEB)

    Rzyski, Barbara M.; Sartori, Carla E. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-12-31

    The results of the inquire collected in 1996, about 10 years after Goiania accident, regarding to the knowledge of nuclear energy and rad wastes are presented. The survey was performed among university students and the population of the Sao Paulo city, of all social levels and different ages. The results show that people between 45 and 55 years are more receptive to the matter. It was observed that the major part of the information absorbed by the public arise form news divulged by newspapers and some spread facts, in cases of incidents or accidents as was Goiania 2 refs., 11 tabs., 1 append.; e-mail: bmrzyski at net.ipen.br

  2. Goiania, ten years later. Proceedings of an international conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-01

    Following the radiological accident that happened in Goiania, Brazil, in late 1987, the Brazilian National Nuclear Energy Commission (CNEN) was able to turn to the international community for assistance under the terms of the 1986 IAEA sponsored Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency; this marked the first time the convention was invoked. Additionally, to prevent the loss of useful information, CNEN and the IAEA designated a panel of international experts to investigate the causes and consequences of the accident and draw up a comprehensive report, `The Radiological Accident in Goiania`, which the IAEA published in 1988. Under its nuclear safety programme, it is the IAEA`s intention to follow up serious radiological accidents with review and analysis, to document the causes and circumstances and to disseminate conclusions, lessons to be learned and recommendations from which all States may benefit. A decade after the Goiania accident, the CNEN convened the international conference `Goiania, Ten Years Later` in co-operation with the IAEA. The purpose of this conference was to share with the local population and the international community the knowledge gained during this tragic event and in the following years. The conference attracted some 400 participants from 17 countries (Argentina, Austria, Brazil, Canada, Cuba, El Salvador, Estonia, Germany, Israel, Italy, Mexico, Peru, Russian Federation, Spain, Uruguay, United States of America and Venezuela). The present IAEA proceedings contain some 50 papers selected for publication by the editorial committee of the conference Refs, figs, tabs

  3. Goiania, ten years later. Proceedings of an international conference

    International Nuclear Information System (INIS)

    1998-12-01

    Following the radiological accident that happened in Goiania, Brazil, in late 1987, the Brazilian National Nuclear Energy Commission (CNEN) was able to turn to the international community for assistance under the terms of the 1986 IAEA sponsored Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency; this marked the first time the convention was invoked. Additionally, to prevent the loss of useful information, CNEN and the IAEA designated a panel of international experts to investigate the causes and consequences of the accident and draw up a comprehensive report, 'The Radiological Accident in Goiania', which the IAEA published in 1988. Under its nuclear safety programme, it is the IAEA's intention to follow up serious radiological accidents with review and analysis, to document the causes and circumstances and to disseminate conclusions, lessons to be learned and recommendations from which all States may benefit. A decade after the Goiania accident, the CNEN convened the international conference 'Goiania, Ten Years Later' in co-operation with the IAEA. The purpose of this conference was to share with the local population and the international community the knowledge gained during this tragic event and in the following years. The conference attracted some 400 participants from 17 countries (Argentina, Austria, Brazil, Canada, Cuba, El Salvador, Estonia, Germany, Israel, Italy, Mexico, Peru, Russian Federation, Spain, Uruguay, United States of America and Venezuela). The present IAEA proceedings contain some 50 papers selected for publication by the editorial committee of the conference

  4. Radiological accidents balance in medicine

    International Nuclear Information System (INIS)

    Nenot, J.C.

    1995-01-01

    This work deals with the radiological accidents in medicine. In medicine, the radiation accidents on medical personnel and patients can be the result of over dosage and bad focusing of radiotherapy sealed sources. Sometimes, the accidents, if they are unknown during a time enough for the source to be spread and to expose a lot of persons (in the case of source dismantling for instance) can take considerable dimensions. Others accidents can come from bad handling of linear accelerators and from radionuclide kinetics in some therapies. Some examples of accidents are given. (O.L.). 11 refs

  5. Dose assessment in radiological accidents

    International Nuclear Information System (INIS)

    Donkor, S.

    2013-04-01

    The applications of ionizing radiation bring many benefits to humankind, ranging from power generation to uses in medicine, industry and agriculture. Facilities that use radiation source require special care in the design and operation of equipment to prevent radiation injury to workers or to the public. Despite considerable development of radiation safety, radiation accidents do happen. The purpose of this study is therefore to discuss how to assess doses to people who will be exposed to a range of internal and external radiation sources in the event of radiological accidents. This will go a long way to complement their medical assessment thereby helping to plan their treatment. Three radiological accidents were reviewed to learn about the causes of those accidents and the recommendations that were put in place to prevent recurrence of such accidents. Various types of dose assessment methods were discussed.(au)

  6. Groundwater flow modelling in the region of the repository site of the radioactive wastes from Goiania accident-Brazil

    International Nuclear Information System (INIS)

    Aquino Branco, Otavio Eurico de; Carvalho Filho, Carlos Alberto

    1996-08-01

    The radioactive wastes from Goiania's accident, with be deposited at the repository site of Abadia de Goias, located 20 km away from the city of Goiania. This paper presents a groundwater flow in confined or unconfined, heterogeneous and anisotropic porous media with variable layer thicknesses. The necessary parameters to simulate the flow were taken from technical reports and from specific studies about the region. The geological and hydrogeological studies evidence that in this area there is one aquifer type water table. The permeability coefficient evaluated for aquifer formation was 1.88x10 -4 cm/s and for the porosity 0.47. The average annual rate of recharge was evaluated in 0.22 m. The potentiometric map generated using the MODFLOW code showed a good a agreement between the hydraulic head simulated and that measured in the field. (author)

  7. Groundwater flow modelling in the region of the repository site of the radioactive wastes from Goiania accident-Brazil; Modelamento do fluxo de agua subterranea na regiao do repositorio dos rejeitos decorrentes do acidente radiologico de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Aquino Branco, Otavio Eurico de; Carvalho Filho, Carlos Alberto [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)

    1996-08-01

    The radioactive wastes from Goiania`s accident, with be deposited at the repository site of Abadia de Goias, located 20 km away from the city of Goiania. This paper presents a groundwater flow in confined or unconfined, heterogeneous and anisotropic porous media with variable layer thicknesses. The necessary parameters to simulate the flow were taken from technical reports and from specific studies about the region. The geological and hydrogeological studies evidence that in this area there is one aquifer type water table. The permeability coefficient evaluated for aquifer formation was 1.88x10{sup -4}cm/s and for the porosity 0.47. The average annual rate of recharge was evaluated in 0.22 m. The potentiometric map generated using the MODFLOW code showed a good a agreement between the hydraulic head simulated and that measured in the field. (author) 8 refs., 3 figs.

  8. Medical follow-up of the radiation accident with 137Cs in Goiania - an update (1990-1994)

    International Nuclear Information System (INIS)

    Brandao-Mello, C.E.; Farina, R.; Rodrigues de Oliveira, A.; Curado, M.P.; Filho, J.F.; Santos, Q.C.B.

    2000-01-01

    On September 13, 1987 a shielded 137 Cs source was removed by two scavengers from a teletherapy unit in abandoned clinic in Goiania, Brazil, and was later broken open. The source was handled by many people from the time it was removed (Sept 13) until it was taken to the sanitary surveillance division (Sept 28). Many of these people (approximately 250) were exposed to large external and internal doses of radiation from the radioactive source; of these, 50 showed signal and symptoms of whole-body irradiation and local acute irradiation and also showed signs of external or internal contamination from ingested or absorbed 137 Cs. Fourteen of those 50 developed moderate to severe bone marrow (BM) injury and required intensive medical care at a specialised unit in Rio de Janeiro. None were subjected to BM transplants. Ultimately, 4 of these casualties died of bleeding and sepsis despite the administration of GM-CSF (Granulocyte Macrophage Colony Stimulating Factor). Internal contamination due to ingestion or absorption of 137 Cs was successfully removed by means of administration of Prussian Blue at doses ranging from 1.5-10.0 gm/day. Radiation induced skin injuries were observed in 28 patients requiring surgical and post-operative procedures. Since March 1988 a medical follow up protocol was established by NNEC and the Leide Das Neves Ferreira Foundation of the state of Goias, in order to prospectively follow more than 150 victims. The aim of this paper is to describe the main after-effects of the 137 Cs accident in the last 4 years, giving emphasis on clinical, haematological, radiological and psychological aspects. (author)

  9. The great fear of 1987: a rereading of the accident with Cesium-137 in Goiania, Brazil

    International Nuclear Information System (INIS)

    Oliveira Junior, Euripedes Monteiro de

    2016-01-01

    The works that take as object of study the radioactive accident in Goiania, and I have found to date, have tried to give special importance to its legal, psychosocial and clinical trials of radiation patients. Here in this text, I will try to understand this event from its historical dimension of fear, emphasizing its historicity from the social and cultural practices of some people, groups and entities involved with the issue. In other words, the focus of this study will be in the memories of those social relations that have been built while unfolding the event, both past and present. In this sense, we find our main concerns contained in a number of issues that are constantly alluded to discussions in which the central concepts refer to the event, memory and narrative in this case will be worked out by building the fear contained in people's memories, in groups involved in the event as well as the narratives constructed by official agencies involved in the event along with the film and the news media. (author)

  10. A medical follow-up of 137 Cs Goiania radiation accident: un update (1990-1992)

    International Nuclear Information System (INIS)

    Brandao-Mello, Carlos Eduardo; Oliveira, Alexandre Rodrigues de; Farina, Rosana

    1995-01-01

    The aim of this paper is to describe the main aftereffects of the 137 Cs accident in the last two years, giving emphasis on clinical, hematological, radiological and psychological aspects. A medical follow-up protocol was established by CNEN and the Leide das Neves Ferreira Foundation of the State of Goias, in order to prospectively follow more than 150 victims. (author). 6 refs

  11. Goiania radiation accident: 30 years - a half-life for a whole life..

    International Nuclear Information System (INIS)

    Reis, R.G.; Lucena, E.A.; Arantes, R.R.; Silva, A.A.; Reis, A.A.

    2017-01-01

    The radiological accident in Goiânia, Brazil, considered the largest urban radiological accident in the world, generated several publications in the technical area that are widely disseminated in the scientific literature, given the importance of the lessons learned. However, in a simple conversation with people who worked on that accident, it is noted that many reports have not been recorded. In this year in which 30 years of the event is completed, it will be of great value to record personal testimonies that are not in technical or scientific books. And what can we tell after a half-life that lasted for a lifetime? The lived stories, the situations, the improvisations, the way to solve, the overcoming, the human side, the emotions, happy or sad, short or long, funny or not. The objective of this work is to preserve, maintain and divulge reports and situations experienced by people who worked on the radiological accident with Cs-137 in Goiânia. Audio or video recordings about experiences lived in Goiânia by people who worked in that emergency situation were carried out. The reports are free and the form of registration is always at the discretion of the narrator. Storing records allows to preserve, maintain, and disclose the accident to other generations

  12. Radiological accidents: education for prevention and confrontation

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

    2008-01-01

    The purpose of this work is to train and inform on radiological accidents as a preventive measure to improve the people life quality. Radiological accidents are part of the events of technological origin which are composed of nuclear and radiological accidents. As a notable figure is determined that there have been 423 radiological accidents from 1944 to 2005 and among the causes prevail industrial accidents, by irradiations, medical accidents and of laboratories, among others. Latin American countries such as Argentina, Brazil, Mexico and Peru are some where most accidents have occurred by radioactivity. The radiological accidents can have sociological, environmental, economic, social and political consequences. In addition, there are scenarios of potential nuclear accidents and in them the potential human consequences. Also, the importance of the organization and planning in a nuclear emergency is highlighted. Finally, the experience that Cuba has lived on the subject of radiological accidents is described [es

  13. Radiation protection in the Marcilio Dias Naval Hospital during the arrived of the victims of the accident in Goiania

    International Nuclear Information System (INIS)

    Fajardo, P.W.

    1988-05-01

    The procedure carried out for Nuclear Medicine Sector of the Marcilio Dias Hospital in the arrived of the victims more graves of the accident in Goiania are presented. The datas obtained with the services of monitoring realized with the detector DSM-3 of the Nardeaux and the radiometric raising of the patients and of their bedroom, making with a ionization chamber 'baby-line' are shown. The services of radiation protection in the ward and the decontamination of the patients are described. The procedures to the necropsy of the contamineted bodies are presented. (V.R.B.)

  14. The radiological accident in Yanango

    International Nuclear Information System (INIS)

    2000-01-01

    The use of nuclear technologies has fostered new, more effective and efficient medical procedures and has substantially improved diagnostic and therapeutic capabilities. However, in order that the benefits of the use of ionizing radiation outweigh the potential hazards posed by this medium, it is important that radiation protection and safety standards be established to govern every aspect of the application of ionizing radiation. Adherence to these standards needs to be maintained through effective regulatory control, safe operational procedures and a safety culture that is shared by all. Occasionally, established safety procedures are violated and serious radiological consequences ensue. The radiological accident described in this report, which took place in Lilo, Georgia, was a result of such an infraction. Sealed radiation sources had been abandoned by a previous owner at a site without following established regulatory safety procedures, for example by transferring the sources to the new owner or treating them as spent material and conditioning them as waste. As a consequence, 11 individuals at the site were exposed for a long period of time to high doses of radiation which resulted inter alia in severe radiation induced skin injuries. Although at the time of the accident Georgia was not an IAEA Member State and was not a signatory of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the IAEA still provided assistance to the Government of Georgia in assessing the radiological situation, while the World Health Organization (WHO) assisted in alleviating the medical consequences of the accident. The two organizations co-operated closely from the beginning, following the request for assistance by the Georgian Government. The IAEA conducted the radiological assessment and was responsible for preparing the report. The WHO and its collaborating centres within the Radiation Emergency Medical Preparedness and Assistance Network

  15. Goiania incident case study

    International Nuclear Information System (INIS)

    Petterson, J.S.

    1988-06-01

    The reasons for wanting to document this case study and present the findings are simple. According to USDOE technical risk assessments (and our own initial work on the Hanford socioeconomic study), the likelihood of a major accident involving exposure to radioactive materials in the process of site characterization, construction, operation, and closure of a high-level waste repository is extremely remote. Most would agree, however, that there is a relatively high probability that a minor accident involving radiological contamination will occur sometime during the lifetime of the repository -- for example, during transport, at an MRS site or at the permanent site itself during repacking and deposition. Thus, one of the major concerns of the Yucca Mountain Socioeconomic Study is the potential impact of a relatively minor radiation-related accident. A large number of potential impact of a relatively minor radiation-related accident. A large number of potential accident scenarios have been under consideration (such as a transportation or other surface accident which results in a significant decline in tourism, the number of conventions, or the selection of Nevada as a retirement residence). The results of the work in Goiania make it clear, however, that such a significant shift in established social patterns and trends is not likely to occur as a direct outcome of a single nuclear-related accident (even, perhaps, a relatively major one), but rather, are likely to occur as a result of the enduring social interpretations of such an accident -- that is, as a result of the process of understanding, communicating, and socially sustaining a particular set of associations with respect to the initial incident

  16. The radiological accident in Cochabamba

    International Nuclear Information System (INIS)

    2004-07-01

    In April 2002 an accident involving an industrial radiography source containing 192 Ir occurred in Cochabamba, Bolivia, some 400 km from the capital, La Paz. A faulty radiography source container had been sent back to the headquarters of the company concerned in La Paz together with other equipment as cargo on a passenger bus. This gave rise to a potential for serious exposure for the bus passengers as well as for the company employees who were using and transporting the source. The Government of Bolivia requested the assistance of the IAEA under the terms of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency. The IAEA in response assembled and sent to Bolivia a team composed of senior radiation safety experts and radiation pathology experts from Brazil, the United Kingdom and the IAEA to investigate the accident. The IAEA is grateful to the Government of Bolivia for the opportunity to report on this accident in order to disseminate the valuable lessons learned and help prevent similar accidents in the future

  17. Whole-body monitoring: Goiania case, Brazil

    International Nuclear Information System (INIS)

    Oliveira, C.A.N. de; Lourenco, M.C.; Dantas, B.M.; Lucena, E.A. de; Becker, P.H.B.

    1988-01-01

    Due to the radiological Cs accident in Goiania, Goias in September 1987, it became necessary to evaluate internal contamination levels of: individuals from the general public that for any reason had direct or indirect involvement with the radioactive source (group 1); occupationally involved persons (group 2). For each of these groups, procedures of whole body monitoring were developped. In order to attend group 1 individuals, the IRD/CNEN installed a whole body unit in the INAMPS General Hospital of Goiania in 11.08.87, which was later transferred to 121, 57 street, Central Sector in Goiania in 2.06.88. In this unit 547 people were monitored, 356 from group 1 and 241 from group 2, until 04.13.88. In the IRD whole body counter installation, 194 individuals were counted, 185 from group 2 and 9 from group 1. The frequency of monitoring of each individual was stablished according to the Cs activity present in the body or to the job that will be done. Some body burden activity curves for Cs 137 as a function of the time elapsed from the first measurement, are presented. There people from group 1 were measured in both counters, the IRD and the Goiania ones. The values obtained in both installations are compatible with the body activity X time curve. (author) [pt

  18. induced chromosome aberrations analyzed by fluorescence in situ hybridization. Eight years follow up of the Goiania radiation accident victims

    International Nuclear Information System (INIS)

    Natarajan, A.T.; Santos, S.J.; Darroudi, F.; Hadjidikova, V.; Vermeulen, S.; Chatterjee, S.; Van de Berg, M.; Grigorova, M.; Sakamoto-Hojo, E.T.; Granath, F.; Ramalho, A.T.; Curado, M.P.

    1998-01-01

    The radiation accident in focus here occurred in a section of Goiania (Brazil) where more than a hundred individuals were contaminated with on September 1987. In order to estimate the absorbed radiation doses, initial frequencies of dicentrics and rings were determined in 129 victims [A.T. Ramalho, PhD Thesis, Subsidios a tecnica de dosimetria citogenetica gerados a partir da analise de resultados obtidos com o acidente radiologico de Goiania, Universidade Federal do Rio de Janeiro, Rio de Janeiro, Brazil, 1992]. We have followed some of these victims cytogenetically over the years seeking for parameters that could be used as basis for retrospective radiation dosimetry. Our data on translocation frequencies obtained by fluorescence in situ hybridization (FISH) could be directly compared to the baseline frequencies of dicentrics available for those same victims. Our results provided valuable information on how precise these estimates are. The frequencies of translocations observed years after the radiation exposure were two to three times lower than the initial dicentrics frequencies, the differences being larger at higher doses (>1 Gy). The accuracy of such dose estimates might be increased by scoring sufficient amount of cells. However, factors such as the persistence of translocation carrying lymphocytes, translocation levels not proportional to chromosome size, and inter-individual variation reduce the precision of these estimates

  19. Induced chromosome aberrations analyzed by fluorescence in situ hybridization. Eight years follow up of the Goiania radiation accident victims

    Energy Technology Data Exchange (ETDEWEB)

    Natarajan, A.T.; Santos, S.J.; Darroudi, F.; Hadjidikova, V.; Vermeulen, S.; Chatterjee, S.; Van de Berg, M.; Grigorova, M. [Leiden University Medical Centrum LUMC, Department of Radiation Genetics and Chemical Mutagenesis, Wassenaarseweg 72, 2333 AL Leiden (Netherlands); Sakamoto-Hojo, E.T. [Department of Biology, Faculty of Philosophy, Sciences and Letters of Ribeirao Preto, University of Sao Paulo, Ribeirao Preto (Brazil); Granath, F. [Department of Mathematical Statistics, Stockholm University, Stockholm (Sweden); Ramalho, A.T. [Institute of Radioprotection and Dosimetry, National Commission of Nuclear Energy, Rio de Janeiro (Brazil); Curado, M.P. [Foundation Leide das Neves Ferreira, Goiania (Brazil)

    1998-05-25

    The radiation accident in focus here occurred in a section of Goiania (Brazil) where more than a hundred individuals were contaminated with on September 1987. In order to estimate the absorbed radiation doses, initial frequencies of dicentrics and rings were determined in 129 victims [A.T. Ramalho, PhD Thesis, Subsidios a tecnica de dosimetria citogenetica gerados a partir da analise de resultados obtidos com o acidente radiologico de Goiania, Universidade Federal do Rio de Janeiro, Rio de Janeiro, Brazil, 1992]. We have followed some of these victims cytogenetically over the years seeking for parameters that could be used as basis for retrospective radiation dosimetry. Our data on translocation frequencies obtained by fluorescence in situ hybridization (FISH) could be directly compared to the baseline frequencies of dicentrics available for those same victims. Our results provided valuable information on how precise these estimates are. The frequencies of translocations observed years after the radiation exposure were two to three times lower than the initial dicentrics frequencies, the differences being larger at higher doses (>1 Gy). The accuracy of such dose estimates might be increased by scoring sufficient amount of cells. However, factors such as the persistence of translocation carrying lymphocytes, translocation levels not proportional to chromosome size, and inter-individual variation reduce the precision of these estimates

  20. The resuspension and redeposition of 137Cs in an urban area: the experience after the Goiania accident

    International Nuclear Information System (INIS)

    Pires Do Rio, M.A.; Amaral, E.C.S.; Paretzke, H.G.

    1994-01-01

    In Goiania, Brazil, the accidental opening of a 137 Cs teletherapy source led to the contamination of an urban area of approximately 1 km 2 . The restricted, local contamination patterns without any significant influence from previous contaminations (Chernobyl reactor accident and atmospheric atomic bomb test fall-out) provided a unique opportunity to study the resuspension and redeposition mechanisms in an urban area under tropical climate characteristics. Air, total deposition, rainwater, surface soil and street dust were sampled over 2 years at a garden of a house and the surroundings and analysed for 137 Cs. The local meteorological conditions were recorded. In addition, some size fractionation measurements were performed. The data show a significant seasonality and a very slow long-term decrease with time for the activity concentration in air and deposition rate. The data as a whole suggest that in Goiania, resuspension and deposition are mainly local phenomena and no evidence was found for a significant spreading of 137 Cs from the place of primary contamination. (author)

  1. The radiological accident in Istanbul

    International Nuclear Information System (INIS)

    2000-01-01

    The use of radioactive materials offers a wide range of benefits throughout the world in medicine, research and industry. Precautions are, however, necessary in order to limit the exposure of persons to the radiation that is emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy sources or industrial radiography sources, extreme care is necessary to prevent accidents which may have severe consequences. Nevertheless, in spite of the precautions taken, accidents with radiation sources continue to occur, albeit infrequently. As part of its subprogramme on the safety of radiation sources, the IAEA conducts follow-up reviews of such serious accidents to give an account of their circumstances and of the medical aspects, from which organizations with responsibilities for radiation protection and the safety of sources may learn. A serious radiological accident occurred in Istanbul, Turkey, in December 1998 and January 1999 when two packages used to transport 60 Co teletherapy sources were sold as scrap metal. The persons who purchased the two packages opened them and broke open the shielded containers, thereby unknowingly exposing themselves and several others to radiation from at least one unshielded 60 Co source. The persons who dismantled the containers suffered from acute radiation syndrome. The accident came to the attention of the relevant national authority when a doctor who had examined the victims reported that he suspected the possibility of radiation exposure. The national authorities identified other individuals who might have undergone acute radiation exposures, and a total of 18 persons (including seven children) were admitted to hospital. Of these, ten adults exhibited clinical signs and symptoms of acute radiation exposure. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the Turkish authorities requested assistance from the IAEA in terms of advice on the medical

  2. Reminiscences of Goiania ten years later: the psychological effects

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, A B [Rio de Janeiro (Brazil)

    1998-12-01

    The author recalls her experiences during the follow-up of the radiological accident in Goiania, Brazil, in 1987, when a {sup 137}Cs capsule was removed from an abandoned radiotherapy clinic. At the time of the accident she was employed by the Brazilian Nuclear Energy Commission`s (CNEN) Department of Human Resources Management as a psychologist. She describes the emotional impact suffered by the victims, the population, the medical care team and the staff of emergency responders of CNEN as they decontaminated the city and cared for the victims. The author puts forward proposals for psychological preparedness for radiological emergencies and nuclear accidents. (author)

  3. Reminiscences of Goiania ten years later: the psychological effects

    International Nuclear Information System (INIS)

    Carvalho, A.B.

    1998-01-01

    The author recalls her experiences during the follow-up of the radiological accident in Goiania, Brazil, in 1987, when a 137 Cs capsule was removed from an abandoned radiotherapy clinic. At the time of the accident she was employed by the Brazilian Nuclear Energy Commission's (CNEN) Department of Human Resources Management as a psychologist. She describes the emotional impact suffered by the victims, the population, the medical care team and the staff of emergency responders of CNEN as they decontaminated the city and cared for the victims. The author puts forward proposals for psychological preparedness for radiological emergencies and nuclear accidents. (author)

  4. The radiological accident in Lilo

    International Nuclear Information System (INIS)

    2000-01-01

    The use of radioactive materials offers a wide range of benefits throughout the world in medicine, research and industry. Precautions are, however, necessary in order to limit the exposure of persons to the radiation that is emitted. Where the amount of radioactive material is substantial, such as with sources used in radiotherapy or industrial radiography, extreme care is necessary to prevent accidents that may result in severe consequences for the affected individuals. Nevertheless, in spite of the precautions taken, accidents with radiation sources continue to occur, albeit infrequently. As part of its activities dealing with the safety of radiation sources, the IAEA follows up severe accidents with a view to providing an account of their circumstances and the medical aspects from which those organizations with responsibilities for radiation protection and the safety of sources may learn. A serious radiological accident occurred in Peru in February 1999 when a welder picked up an 192 Ir industrial radiography source and put it in his pocket for several hours. This resulted in his receiving a high radiation dose that necessitated the amputation of one leg. His wife and children were also exposed, but to a much lesser extent. The Peruvian authorities requested assistance from the IAEA in obtaining advice on medical treatment. They also agreed to assist the IAEA with the subsequent review of the circumstances surrounding the accident. The IAEA is grateful to the Instituto Peruano de Energia Nuclear for its willingness to assist in the reparation of this report and, thereby, share its experience with other Member States

  5. Radionuclide metrology: traceability and response to a radiological accident

    Energy Technology Data Exchange (ETDEWEB)

    Tauhata, L.; Cruz, P.A.L. da; Silva, C.J. da; Delgado, J.U.; Oliveira, A.E. de; Oliveira, E.M. de; Poledna, R.; Loureiro, J. dos S.; Ferreira Filho, A.L.; Silva, R.L. da; Filho, O. L.T.; Santos, A.R.L. dos; Veras, E.V. de; Rangel, J. de A.; Quadros, A.L.L.; Araújo, M.T.F. de; Souza, P.S. de; Ruzzarim, A.; Conceição, D.A. da; Iwahara, A., E-mail: palcruz@ird.gov.br [Instituto de Radioproteção e Dosimetria (LNMRI/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Metrologia das Radiações Ionizantes

    2017-07-01

    In the case of a radiological accident, there are characteristic phases: discovery and initial assistance with first aid; the triage and monitoring of the affected population; the release of the affected people; forward the victims to medical care; as well as the preparation of the report on the accident. In addition, studies and associated researches performed in the later period. Monitors, dosimeters and measuring systems should be calibrated by contaminating radionuclide standards. The radioactive sources used must be metrologically reliable. In Brazil, this function is performed by LNMRI/IRD/CNEN, designated by INMETRO, which Radionuclide Metrology Laboratory is responsible for the standardization and supply of radioactive sources in diverse geometries and matrices. This laboratory has a stock of radionuclide solutions with controlled environmental variables for the preparation of sources, which are calibrated and standardized by mean of primary and secondary systems. It is also responsible for the dissemination of standards and, in order to establish the metrological traceability of national standards, participates in international key-comparisons promoted by BIPM and regional metrology organizations. Internally, it promotes the National Comparison Programs for laboratories for the analysis of environmental samples and the traceability for producing centers of radiopharmaceuticals and Nuclear Medicine Services in the country. The paper presents the demand for {sup 137}Cs related to the radioactive accident in Goiania/Brazil and the significant results for the main radionuclides standardized by the Radionuclide Metrology Laboratory for international key-comparisons and national comparisons to provide metrological traceability. With the obtained results, the LNMRI of Brazil integrates the international metrology BIPM network and fulfills its function of supplying, with about a hundred of radioactive standards, the country's needs in different applications

  6. Radionuclide metrology: traceability and response to a radiological accident

    International Nuclear Information System (INIS)

    Tauhata, L.; Cruz, P.A.L. da; Silva, C.J. da; Delgado, J.U.; Oliveira, A.E. de; Oliveira, E.M. de; Poledna, R.; Loureiro, J. dos S.; Ferreira Filho, A.L.; Silva, R.L. da; Filho, O. L.T.; Santos, A.R.L. dos; Veras, E.V. de; Rangel, J. de A.; Quadros, A.L.L.; Araújo, M.T.F. de; Souza, P.S. de; Ruzzarim, A.; Conceição, D.A. da; Iwahara, A.

    2017-01-01

    In the case of a radiological accident, there are characteristic phases: discovery and initial assistance with first aid; the triage and monitoring of the affected population; the release of the affected people; forward the victims to medical care; as well as the preparation of the report on the accident. In addition, studies and associated researches performed in the later period. Monitors, dosimeters and measuring systems should be calibrated by contaminating radionuclide standards. The radioactive sources used must be metrologically reliable. In Brazil, this function is performed by LNMRI/IRD/CNEN, designated by INMETRO, which Radionuclide Metrology Laboratory is responsible for the standardization and supply of radioactive sources in diverse geometries and matrices. This laboratory has a stock of radionuclide solutions with controlled environmental variables for the preparation of sources, which are calibrated and standardized by mean of primary and secondary systems. It is also responsible for the dissemination of standards and, in order to establish the metrological traceability of national standards, participates in international key-comparisons promoted by BIPM and regional metrology organizations. Internally, it promotes the National Comparison Programs for laboratories for the analysis of environmental samples and the traceability for producing centers of radiopharmaceuticals and Nuclear Medicine Services in the country. The paper presents the demand for 137 Cs related to the radioactive accident in Goiania/Brazil and the significant results for the main radionuclides standardized by the Radionuclide Metrology Laboratory for international key-comparisons and national comparisons to provide metrological traceability. With the obtained results, the LNMRI of Brazil integrates the international metrology BIPM network and fulfills its function of supplying, with about a hundred of radioactive standards, the country's needs in different applications

  7. Overview of the radiological accidents in the world, updated December 1989

    Energy Technology Data Exchange (ETDEWEB)

    Nenot, J.C. (CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Protection Sanitaire)

    1990-06-01

    This outline historical review discusses radiological accidents of two categories: those involving large groups of the population with relatively low doses, or a few individuals with high doses resulting in acute health effects. Comments on the following accidents are made: (a) the Marshallese population and the Japanese Fisherman, Pacific Ocean 1954 (b) South East Urals USSR 1957 (c) Juarez, Mexico 1983/84 (d) Chernobyl 1986 (e) Goiania, Brazil 1987. Registration of accidents resulting in high doses to few individuals is also discussed:-criticality accidents, those resulting in high whole-body doses from sealed sources, nuclear power reactor incidents leading to acute doses among workers, those resulting in localized radiation injury and those resulting in severe internal exposure. (UK).

  8. Mental health effects from radiological accidents and their social management

    International Nuclear Information System (INIS)

    Brenot, J.; Charron, S.; Verger, P.

    2000-01-01

    Mental health effects resulting from exposure to radiation have been identified principally in the context of large radiological accidents. They cover an extended scope of manifestations in relation with the notion of stress: increase of some hormones, modifications in mental concentration, symptoms of anxiety and depression, psycho-somatic diseases, deviation behaviours, and, on the long term, a possible post-traumatic stress disorder (PTSD). The main results come from the Three Mile Island, Goiania, and Chernobyl accidents and several modifying factors have been identified. Considering those facts, diverse social responses can be brought to reduce the detriment to affected individuals and communities. Medical treatments are necessary for persons who suffer from pathological diseases. In most cases, a structured public health follow-up is required to establish the seriousness of the health problems, to forecast the extent of medical and psychological assistance, and to inform people who express fears and worries. Social assistance is always valuable under various forms: financial compensations, preferential medical care, and particular advantages concerning working and living conditions. If this social assistance is necessary and helpful, it also induces a loss in personal adjustment capability and initiative capacity. To overcome those negative impacts, some guidelines to authorities' action can be set up. But the best approach, not excluding the previous ones, remains problem solving at the local level through community responsibilization; some instructive examples come from the Chernobyl experience. (author)

  9. Mental health effects from radiological accidents and their social management

    Energy Technology Data Exchange (ETDEWEB)

    Brenot, J.; Charron, S.; Verger, P. [Institute for Protection and Nuclear Safety, Fontenay-aux-Roses Cedex (France)

    2000-05-01

    Mental health effects resulting from exposure to radiation have been identified principally in the context of large radiological accidents. They cover an extended scope of manifestations in relation with the notion of stress: increase of some hormones, modifications in mental concentration, symptoms of anxiety and depression, psycho-somatic diseases, deviation behaviours, and, on the long term, a possible post-traumatic stress disorder (PTSD). The main results come from the Three Mile Island, Goiania, and Chernobyl accidents and several modifying factors have been identified. Considering those facts, diverse social responses can be brought to reduce the detriment to affected individuals and communities. Medical treatments are necessary for persons who suffer from pathological diseases. In most cases, a structured public health follow-up is required to establish the seriousness of the health problems, to forecast the extent of medical and psychological assistance, and to inform people who express fears and worries. Social assistance is always valuable under various forms: financial compensations, preferential medical care, and particular advantages concerning working and living conditions. If this social assistance is necessary and helpful, it also induces a loss in personal adjustment capability and initiative capacity. To overcome those negative impacts, some guidelines to authorities' action can be set up. But the best approach, not excluding the previous ones, remains problem solving at the local level through community responsibilization; some instructive examples come from the Chernobyl experience. (author)

  10. Radiation protection at Centro Medico Naval Marcilio Dias during the assistance to the victims of the accident in Goiania

    International Nuclear Information System (INIS)

    Silva, L.H.C.; Rosa, R.; Fajardo, P.W.

    1988-01-01

    The objective of this paper is to present the acquired experience in developing a radiation protection program to be implemented in case of an emergency medical assistance in radiological accidents. (author) [pt

  11. The role of FUNLEIDE in the follow-up or assistance to the victims of the Goiania accident

    International Nuclear Information System (INIS)

    Santos, Q.C.B.

    2000-01-01

    The FUNLEIDE (Fundacao Leide Da Neves Ferreira) was created by the Government with the objectives of planning, organising, supervising and giving assistance to the persons involved in the radiation accident with 137 Cs in Goiania. The medical service of the FUNLEIDE is responsible for searching early signals for possible alterations caused by ionising radiation, such as cancer, cataract, genetic changes, etc., following a specific protocol for routine exams of the patients assigned Group I (with radiodermatitis and/or whole body dosimetry above or equal to 20 rads), Group II (no dermatitis, dosimetry below to 20 rads) and Group III (professionals who worked in the emergency phase of the accident as well as relatives and other persons who got in contact with patients from Group I and II). The FUNLEIDE is formed by the following departments: Medical Department, Nursing Department, Laboratories, Department of Odonthology, Department of Psychology and Department of Social Service. Besides the routine exams, the Medical Department provides any kind of medical assistance for the population involved in the accident. (author)

  12. Reminiscences of Goiania - 10 years later - the psychological effects

    International Nuclear Information System (INIS)

    Carvalho, Ana Bandeira de

    1997-01-01

    The author, at that time working at the Brazilian Nuclear Energy Commission's Human Resources Management Department as psychologist, remembers her experience during the follow-up of the radiological accident which happened in Goiania, Brazil, in 1987, when a 137 Cs capsule was stolen from an abandoned radiotherapy clinic. She emphasizes the emotional impact suffered by the victims, the population, the health team and the Brazilian Nuclear Energy Commission's staff of emergency responders during the city clean-up and victim's aid and gives some proposals for psychological preparedness to attend radiological emergencies and nuclear accidents. (author)

  13. Legal aspects of nuclear and radiological accidents

    International Nuclear Information System (INIS)

    El-baroudy, M.M.

    2005-01-01

    Aiming at preventing nuclear and radiological accidents and maintaining safety and security, the State extends its jurisdiction over nuclear and radiological activities through the promulgation of regulatory legislations and providing criminal protection to these activities. The State, in its legislation, defines an authority responsible for the planning of preparedness for emergency situations. That Authority cooperates with other competent authorities in the State as well as with other relevant international organizations and other States in a coordinated way aiming at dealing effectively with and mitigating the consequences of nuclear and radiological accidents through promulgating relevant international conventions and plans for reinforcement of international cooperation in accidents situations. Moreover, the International Atomic Energy Authority (IAEA) can provide specialized consultations and offer assistance in case of accidents. The present study is divided into an introduction and two chapters. In the introduction, the nature of nuclear or radiological accidents is defined. The first chapter deals with the national legal system for preventing the occurrence of nuclear and radiological accidents and mitigating their consequences. The second chapter deals with the international cooperation for facing nuclear or radiological accidents and mitigating their consequences

  14. Radiological accidents, scenarios, planning and answers

    International Nuclear Information System (INIS)

    Solis Delgado, Alexander.

    2008-01-01

    Radiological accidents, scenarios and the importance of a good planning to prevent and control these types of accidents are presented. The radiation can be only one of the risks in an accident, most of dominant radiological risks are not radiological (fire, toxic gases, etc.). The common causes of radiological accidents, potential risks such as external irradiation, internal contamination and the environment pollution are highlighted. In addition, why accidents happen and how they evolve is explained. It describes some incidents with the radiation occurred in Costa Rica from 1993 to 2007. The coordination of emergency management in Costa Rica in relation to a radiological accident, and some mechanisms of action that have practiced in other places are focuses. Among the final considerations are the need to finalize the national plan for radiological emergencies as a tool of empowerment for the teams of emergency care and the availability of information. Likewise the processes of communication, coordination and cooperation to avoid chaos, confusion and crisis are also highlighted [es

  15. Management of radioactive wastes from HNMD (Hospital Naval Marcilio Dias) and from IRD (Instituto de Radioprotecao e Dosimetria) due to the accident in Goiania

    International Nuclear Information System (INIS)

    Peres, S.S.; Silva, J.J.G.

    1988-01-01

    A description of the methods and procedures for the management of the radwastes from HNMD (Hospital Naval Marcilio Dias) and from IRD (Instituto de Radioprotecao e Dosimetria) due to the radioactive accident at Goiania City, is presented. Basically the radwastes are consituted by excreta of persons involved in the accident and materials used for medicals care of patients. The method employed for treatment of faeces was its aggregation in lime and cement and for the case of urine, ion exchange resing, was used. Others type of radwastes were compacted or simply conditionned. Many releases to the environment, were possible. (author) [pt

  16. Radiological accidents: analysis of the information disseminated by media and public acceptance of nuclear technology

    International Nuclear Information System (INIS)

    Delgado, Jose Ubiratan; Tauhata, Luiz; Garcia, Marcia Maria

    1995-01-01

    A methodology to treat quantitatively information by Media concerning a nuclear or a radiological accident is presented. It allows us to classify information according to the amount, importance and way of showing, into one indicator, named Information Equivalent. This establishes a procedure for analysis of released information and includes: number of head-lines, illustrations, printed lines, editorials, authorities quoted and so on. Interpretation becomes easier when the evolution and statistical trend of this indicator is observed. The application to evaluate the dissemination of the accident which took place in 1987 in Goiania, Brazil, was satisfactory and allowed us to purpose a model. This will aid the planning, the decision making process and it will improve relationships between technical staff and media during the emergency. (author). 5 refs., 4 figs., 3 tabs

  17. Brazilian bentonite study: use in Goiania; Estudo das bentonitas nacionais: utilizacao em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Tello, Cledola Cassia Oliveira de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)

    1997-12-31

    The evaluation of the bentonite effect in the waste cementation process and in the final solidified product properties is presented. The research showed that bentonite amounts until 15% in the product improves the caesium retention without jeopardizing the other product properties. These results were very useful in the treatment of the wastes from the radiological accident occurred in Goiania in 1987, when a caesium sources was broken. Paste, mortar and grout with bentonite were used to solidify and immobilize these wastes. (author) 20 refs., 1 fig., 6 tabs.; e-mail: tellocc at urano.cdtn.br

  18. Review of specific radiological accident considerations

    International Nuclear Information System (INIS)

    Elder, J.

    1984-01-01

    Specific points of guidance provided in the forthcoming document A Guide to Radiological Accident Considerations for Siting and Design of Nonreactor Nuclear Facilities are discussed. Of these, the following are considered of particular interest to analysts of hypothetical accidents: onsite dose limits; population dose, public health effects, and environmental contamination as accident consequences which should be addressed; risk analysis; natural phenomena as accident initiators; recommended dose models; multiple organ equivalent dose; and recommended methods and parameters for source terms and release amount calculations. Comments are being invited on this document, which is undergoing rewrite after the first stage of peer review

  19. A major technological accident: the dispersion of a radioactive cesium - 137 pellet in Goiania, Brazil (1987)

    International Nuclear Information System (INIS)

    Guertzon, C.

    1994-01-01

    This study concerns the accidental dispersion of cesium 137 chloride via an abandoned radiotherapy device in Brazil, in september 1987. Since the accident occurred recently in a confined area and concerned a single radiochemical agent, it was possible to delimit the study parameters in each discipline: post-accident management, physics, medicine, environment, law, psychology, socio-economics and communication. Costs are difficult to evaluate but obviously very important. It is difficult to analyze all consequences. No official has been accused, there were no sentence. The results demonstrate the critical importance of the human factor in technological accidents. (A.L.B.)

  20. What constitutes a radiology radiation accident

    International Nuclear Information System (INIS)

    Wallace, A.; Edmonds, K.; Hayton, A.; Tingey, D.

    2010-01-01

    Full text: A review of the literature indicates a very small number of articles on radiology radiation accidents. This may be due to there being no agreed definition of the term 'accident' when applied to radiology incidents. As the intensity of X-ray beams and the functionality of various modalities increase there is a consequent development in procedures to which 'high dose' applications are required. We may therefore expect to see more incidents in future. How are we to manage them? Radiology radiation accidents are usually exemplified by deterministic skin burns which may take many weeks or months to become apparent and any procedure leading to a radiation induced fatality is difficult to prove. (author)

  1. The use of uranium exploitation techniques in the selection of a candidate site for Cs-137 radioactive wastes from the Goiania accident

    International Nuclear Information System (INIS)

    Saad, S.

    1997-01-01

    The selection of a candidate site for the disposal of wastes containing Cesium-137 originated by the Goiania accident followed a sequence of studies where specific exploratory techniques in the field of geoscience were applied through geophysical, geochemical, hydrological, hydrogeological and pedological investigations and subsurface drillings. This programme has been aimed at characterizing in detail the selected site, in order to obtain parameters for the conceptual engineering design and also to elaborate the Environmental Impact Report. Among the different options encountered, the site which presented the best characteristics to store those wastes is located about 300 m west of the provisional repository. (author)

  2. Radiological accident 'The Citadel' medical aspects

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan; Fernandez, Isis M.; Lopez, Gladys; Garcia, Omar; Lamadrid, Ana I.; Ramos, Enma O.; Villa, Rosario; Giron, Carmen M.; Escobar, Myrian; Zerpa, Miguel; Romero, Argenis H.; Medina, Julio; Laurenti, Zenia; Oliva, Maria T.; Sierra, Nitza; Lorenzo, Alexis

    2008-01-01

    The work exposes the medical actions carried out in the mitigation of the consequences of the accident and its main results. In a facility of storage of radioactive waste in Caracas, Venezuela, it was happened a radiological accident. This event caused radioactive contamination of the environment, as well as the irradiation and radioactive contamination of at least 10 people involved in the fact, in its majority children. Cuban institutions participated in response to the accident. Among the decisions adopted by the team of combined work Cuban-Venezuelan, we find the one of transferring affected people to Cuba, for their dosimetric and medical evaluation. Being designed a work strategy to develop the investigations to people affected by the radiological accident, in correspondence with the circumstances, magnitude and consequences of the accident. The obtained main results are: 100% presented affectations in its health, not associate directly to the accident, although the accident influenced in its psychological state. In 3 of studied people they were detected radioactive contamination with Cesium -137 with dose among 2.01 X 10-4 Sv up to 2.78 X 10-4 Sv. This accident demonstrated the necessity to have technical capacities to face these events and the importance of the international solidarity. (author)

  3. Strategy implemented for a safe management of the waste arising from the Goiania accident

    Energy Technology Data Exchange (ETDEWEB)

    Miaw, Sophia T.W. [International Atomic Energy Agency, Vienna (Austria). Safety Co-ordination Section; Mezhari, Arnaldo; Shu, Jane; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle

    1997-12-31

    The management of radioactive waste after the accident is discussed. Several aspects such as properties of the waste, the available infrastructure for its collection, the decontamination logistics, the motivation and commitment of works and the politically sensitive definition of handling different waste as well as the administrative procedure to set up reliable records on the collected waste are studied. Four years after the accident, corrosion was detected in some packages. Waste reconditioning, development and implementation of waste data base and development of a national safety evaluation procedure for the final disposal facility are presented 11 refs., 5 tabs.

  4. Strategy implemented for a safe management of the waste arising from the Goiania accident

    International Nuclear Information System (INIS)

    Miaw, Sophia T.W.; Mezhari, Arnaldo; Shu, Jane; Xavier, Ana Maria

    1997-01-01

    The management of radioactive waste after the accident is discussed. Several aspects such as properties of the waste, the available infrastructure for its collection, the decontamination logistics, the motivation and commitment of works and the politically sensitive definition of handling different waste as well as the administrative procedure to set up reliable records on the collected waste are studied. Four years after the accident, corrosion was detected in some packages. Waste reconditioning, development and implementation of waste data base and development of a national safety evaluation procedure for the final disposal facility are presented

  5. Preventing radiological accidents and emergencies by legislative and regulatory means

    International Nuclear Information System (INIS)

    Pelzer, N.

    1998-01-01

    The Goiania radiation accident triggered a reassessment of radiation safety systems. From a legal point of view, the course of events indicates that there were deficiencies either in the existing legal framework or in the implementation of that framework. Proposals to avoid similar accidents in the future are discussed, stressing the need for a sound legal regime and a close co-operation between state authorities and users of radioactive sources. In particular, the importance is underscored of the human factor in achieving a high level of radiation safety. (author)

  6. The Radiological Accident in Lia, Georgia

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-12-15

    The use of radioactive material offers a wide range of benefits to medicine, research and industry throughout the world. Precautions are necessary, however, to limit the exposure of people to the radiation emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy or industrial radiography sources, great care is required to prevent accidents which could have severe consequences. Nevertheless, in spite of the precautions taken, serious accidents involving radiation sources continue to occur, albeit infrequently. The IAEA conducts follow-up reviews of such serious accidents to provide an account of their circumstances and consequences, from which organizations with responsibilities for radiation protection, safety of sources and emergency preparedness and response may learn. A serious radiological accident occurred in Georgia on 2 December 2001, when three inhabitants of the village of Lia found two metal objects in the forest while collecting firewood. These objects were {sup 90}Sr sources with an activity of 1295 TBq. The three inhabitants used the objects as heaters when spending the night in the forest. The major cause of the accident was the improper and unauthorized abandonment of radiation sources in Georgia and the absence of clear labels or radiation signs on the sources warning of the potential radiation hazard. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), the Georgian authorities requested assistance from the IAEA to advise on the dose assessment, source recovery and medical management of those involved in the accident. This publication describes the circumstances and events surrounding the accident, its management and the medical treatment of the people exposed. It also describes the dose reconstruction calculations and biodosimetry assessments conducted. A number of uncertainties remain relating to some details of the accident. However

  7. The Radiological Accident in Lia, Georgia

    International Nuclear Information System (INIS)

    2014-12-01

    The use of radioactive material offers a wide range of benefits to medicine, research and industry throughout the world. Precautions are necessary, however, to limit the exposure of people to the radiation emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy or industrial radiography sources, great care is required to prevent accidents which could have severe consequences. Nevertheless, in spite of the precautions taken, serious accidents involving radiation sources continue to occur, albeit infrequently. The IAEA conducts follow-up reviews of such serious accidents to provide an account of their circumstances and consequences, from which organizations with responsibilities for radiation protection, safety of sources and emergency preparedness and response may learn. A serious radiological accident occurred in Georgia on 2 December 2001, when three inhabitants of the village of Lia found two metal objects in the forest while collecting firewood. These objects were 90 Sr sources with an activity of 1295 TBq. The three inhabitants used the objects as heaters when spending the night in the forest. The major cause of the accident was the improper and unauthorized abandonment of radiation sources in Georgia and the absence of clear labels or radiation signs on the sources warning of the potential radiation hazard. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), the Georgian authorities requested assistance from the IAEA to advise on the dose assessment, source recovery and medical management of those involved in the accident. This publication describes the circumstances and events surrounding the accident, its management and the medical treatment of the people exposed. It also describes the dose reconstruction calculations and biodosimetry assessments conducted. A number of uncertainties remain relating to some details of the accident. However, sufficient

  8. The radiological accident in Tammiku

    International Nuclear Information System (INIS)

    1998-01-01

    On 21 October 1994, three brothers entered a waste repository at Tammiku, Estonia, without authorization and removed a metal container enclosing a caesium-137 source. During the removal the source was dislodged and fell to the ground. One of the men picked up the source, placed it in his pocket and took it to his home in the nearby village of Kiisa. Very soon after entry into the repository he began to feel ill, and few hours later he began to vomit. The man was subsequently admitted to hospital with severe injuries to his leg and hip and died on 2 November 1994. The injury and subsequent death were not attributed to radiation exposure, and the source remained in the man's house with his wife and stepson and the boy's great-grandmother. The boy was hospitalized on 17 November with severe burns on his hands, and these were identified by a doctor as radiation induced. The authorities were alerted, and the Estonian Rescue Board recovered the source from the house. The source was returned to the Tammiku repository on 18 November. The occupants of the house and one of the two surviving brothers were hospitalized and diagnosed as suffering from radiation induced injuries of varying severity. All were subsequently released from hospital, but, at the time of writing this report the treatment to the most exposed individuals is still continuing. The objective of this report is to provide information to national authorities and regulatory organizations so that they can take steps to minimize the risks of similar accidents in the future, and also put in place arrangements to deal with such accidents if they do occur. It is hoped that this report will be of general interest in the radiation protection community, although it si aimed primarily at managers of waste disposal facilities, and legislators and regulators, both in developing countries and in all countries reviewing their radiation protection legislation. This report describes the events leading up to the accident, the

  9. The radiological accident in Tbilisi

    International Nuclear Information System (INIS)

    Abramidze, S.; Katamadze, N.; Lomtadze, Z.; Crus Suarez, R.; Bilbao Alfonso, A.V.

    1998-01-01

    On 9 October 1997 a facsimile message was received by the IAEA from the Minister of Health of Georgia stating that servicemen of the Lilo Training Detachment of Frontier Troops had developed local radiation induced skin diseases on various parts of their bodies. Details were sent of the medical diagnoses of the nine victims together with information on the radiation sources and dose rates that had caused the exposures. The Georgian minister of Health requested the IAEA to assist in the examination and treatment of the patients. An investigation had revealed that several Cs-137, Co-60 radiation sources and some beta emitters had been found and that in some places high dose rates had been detected. The Government of Georgia requested the IAEA to send an emergency team to evaluate the radiological situation at the Lilo Training Center. The present paper is a summary of the finding and lessons to be learned from this situation. (author)

  10. Radiological consequences of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.

    2003-01-01

    The reactor accident at unit 4 of the Chernobyl nuclear power plant in Ukraine has deeply affected the living conditions of millions of people. Especially the health consequences have been of public concern up to the present and also been the subject of sometimes absurd claims. The current knowledge on the radiological consequences of the accident is reviewed. Though an increased hazard for some risk groups with high radiation exposure, e.g., liquidators, still cannot be totally excluded for the future, the majority of the population shows no statistically significant indication of radiation-induced illnesses. The contribution of the Research Center Juelich to the assessment of the post-accidental situation and psychological relief of the population is reported. The population groups still requiring special attention include, in particular, children growing up in highly contaminated regions and the liquidators of the years 1986 and 1987 deployed immediately after the accident. (author)

  11. The great fear of 1987: a rereading of the accident with Cesium-137 in Goiania, Brazil; O grande medo de 1987: uma releitura do acidente com o Cesio-137 em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira Junior, Euripedes Monteiro de

    2016-11-01

    The works that take as object of study the radioactive accident in Goiania, and I have found to date, have tried to give special importance to its legal, psychosocial and clinical trials of radiation patients. Here in this text, I will try to understand this event from its historical dimension of fear, emphasizing its historicity from the social and cultural practices of some people, groups and entities involved with the issue. In other words, the focus of this study will be in the memories of those social relations that have been built while unfolding the event, both past and present. In this sense, we find our main concerns contained in a number of issues that are constantly alluded to discussions in which the central concepts refer to the event, memory and narrative in this case will be worked out by building the fear contained in people's memories, in groups involved in the event as well as the narratives constructed by official agencies involved in the event along with the film and the news media. (author)

  12. Management and transport of radioactive wastes in Goiania, Brazil

    International Nuclear Information System (INIS)

    Xavier, A.M.; Mezrahi, A.

    1988-01-01

    The radiological accident occured in Goiania, which has led to the liberation to the environment of c.l.350 Ci of Cs-137, demanded the formulation of special procedures related to waste management and transport of radioactive materials to a provisory storage facility. The main objectives of the present article are to describe the work performed in the above mentioned fields and to point out the basic needs for Brazilian research and development in the areas of waste treatment and design and testing of packages. (author) [pt

  13. Nuclear laws and radiologic accidents; Direito nuclear e os acidentes radiologicos

    Energy Technology Data Exchange (ETDEWEB)

    Frois, Fernanda [Pontificia Univ. Catolica de Sao Paulo, SP (Brazil)

    1997-12-31

    Some aspects of the nuclear activities in Brazil, specially concerning the Goiania s accident are demonstrated using concepts from environmental and nuclear law. Nuclear and environmental competence, the impossibility of the states of making regional laws, as the lack of regulation about the nuclear waste, are discussed. The situation of Goiania when the accident happened, the present situation of the victims and the nuclear waste provisionally stored in Abadia de Goias is reported 7 refs.; e-mail: froes at sti.com.br

  14. Considerations regarding iodine prophylaxis in radiological accidents

    International Nuclear Information System (INIS)

    Perez, M.R.; Gisone, P.; Rojo, A.M.; Dubner, D.; Bruno, H.

    1995-01-01

    The indication for the blockade of thyroid gland by the administration of stable iodide is the main countermeasure for diminishing the thyroid uptake of radioiodine following radiological accidents with potential release of radioiodine into the environment in order to avoid deterministic effects and to decrease the probability of stochastic effects. Iodine prophylaxis should be considered along with other countermeasures like sheltering indoors, evacuation and control on contaminated foods. In this communication different factors related to accidental situations regarding iodine prophylaxis are evaluated. A therapeutical scheme is proposed in order to be applied in countries of this region. (author). 4 refs

  15. Brazilian emergency planning for radiological accidents

    International Nuclear Information System (INIS)

    Mendonca, A.H.

    1986-01-01

    Brazilian emergency planning for radiological accidents is organized to respond promptly to any emergency at nuclear power plants or other installations utilizing nuclear fuel. It consists of several committees: a general coordination committee with representatives from several federal departments, with final decision with the Brazilian Nuclear Energy Commission (CNEN), and the Federal Environmental Protection Agency (SEMA). Some committees conduct support activities. For example, the Operational Coordination Committee supervises the tasks undertaken by the Army, Navy, and Air Force in response to the needs and decisions of the general coordination committee

  16. Reminiscences of Goiania - 10 years later - the psychological effects

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Ana Bandeira de

    1997-12-31

    The author, at that time working at the Brazilian Nuclear Energy Commission`s Human Resources Management Department as psychologist, remembers her experience during the follow-up of the radiological accident which happened in Goiania, Brazil, in 1987, when a {sup 137} Cs capsule was stolen from an abandoned radiotherapy clinic. She emphasizes the emotional impact suffered by the victims, the population, the health team and the Brazilian Nuclear Energy Commission`s staff of emergency responders during the city clean-up and victim`s aid and gives some proposals for psychological preparedness to attend radiological emergencies and nuclear accidents. (author) 8 refs.; e-mail: anita at openlink.com.br

  17. Comparative evaluations of surface contamination detectors calibration with radioactive sources - used in the Goiania accident, and standard sources; Estudo comparativo da calibracao dos monitores de contaminacao superficial com as fontes radiativas utilizadas durante o acidente de Goiania e com fontes padrao

    Energy Technology Data Exchange (ETDEWEB)

    Becker, P.H.B.; Marecha, M.H.H. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    The construction of Cs-137 standard flat sources for calibration of surface contamination detectors, used in the Goiania accident in 1987, is described and the procedures adopted are reported. At that time, standard sources were not available. Nowadays the Instituto de Radioprotecao e Dosimetria has standard sources acquired from Amersham which are used as calibration standards for surface contamination detectors. Comparative evaluations between the standard flat sources constructed for the accident and the calibrated ones are presented 6 refs., 1 fig., 4 tabs.; e-mail: pbecker at ird.gov.br; mhelena at ird. gov.br

  18. TIARA: treatment initiatives after radiological accidents

    International Nuclear Information System (INIS)

    Menetrier, F.; Berard, Ph.; Joussineau, S.; Stradling, N.; Hodgson, A.; List, V.; Morcillo, M.A.; Paile, W.; Holt, D.C.B.; Eriksson, T.

    2007-01-01

    This paper describes the objectives, and reviews the progress, of the European project 'Treatment Initiatives After Radiological Accidents' (TIARA). TIARA forms part of the 'Preparatory Action for Security Research' (PASR) launched by the European Commission in 2004. The Preparatory Action is intended to reach preliminary conclusions on the needs for the security of EU citizens. It prepared a comprehensive Security Research Programme as part of the Commission's Seventh Framework Programme proposal, which was adopted in 2006 and launched in 2007. The principal purpose of TIARA is to constitute a European network that will participate in facilitating the management of a crisis in the event of the malevolent dispersal of radionuclides into the public environment. (authors)

  19. Radiologic accidents in industrial gamma radiography - Brazilian cases

    International Nuclear Information System (INIS)

    Silva, Francisco Cesar Augusto da

    1997-01-01

    Three severe radiological accidents in industrial gamma radiography happened in Brazil during the period of 1985 to 1988. Five operators and nineteen public people were involved. These accidents caused some injuries in parts of the body, mainly hands and fingers. The main causes were faults in source monitoring, inadequate routine procedures and unknowing of radiation warning symbol by public people. The present paper shows the Brazilian cases of radiological accidents and makes some analysis of them. (author)

  20. Report about decontamination and follow-up of Cesium-137 radiation victims at the FEBEM unit in Goiania

    International Nuclear Information System (INIS)

    Cambises, P.B.S.; Sanchez, A.S.; Almeida, C.C.

    1997-01-01

    The acquired experience and the facts related to treatment and external decontamination of contaminated people of the primary group of the Goiania accident are reported. This group was sent to Unidade FEBEM from October 10 to December 20, 1987. The external decontamination methods and the observed results obtained by daily monitoring reports are presented. Furthermore, the applied methodology to release people or to ask them for further periodical check ups at the radiological control units is also presented. (author)

  1. Radiological consequences of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.

    2002-01-01

    Fifty years of peaceful utilization of nuclear power were interrupted by the reactor accident in unit 4 of the Chernobyl nuclear power station in Ukraine in 1986, a disruptive event whose consequences profoundly affected the way of life of millions of people, and which has moved the public to this day. Releases of radioactive materials contaminated large areas of Belarus, the Russian Federation, and Ukraine. Early damage in the form of radiation syndrome was suffered by a group of rescue workers and members of the reactor operating crew, in some cases with fatal consequences, while the population does not, until now, show a statistically significant increase in the rate of late damage due to ionizing radiation expect for thyroid diseases in children. In particular, no increases in the rates of solid tumors, leukaemia, genetic defects, and congenital defects were detected. For some risk groups exposed to high radiation doses (such as liquidators) the hazard may still be greater, but the large majority of the population need not live in fear of serious impacts on health. Nevertheless, the accident shows major negative social and psychological consequences reinforced by the breakdown of the Soviet Union. This may be one reason for the observed higher incidence of other diseases whose association with the effects of radiation as a cause has not so far been proven. The measurement campaign conducted by the federal government in 1991-1993 addressed these very concerns of the public in an effort to provide unbiased information about exposures detected, on the one hand, in order to alleviate the fears of the public and reduce stress and, on the other hand, to contribute to the scientific evaluation of the radiological situation in the regions most highly exposed. The groups of the population requiring special attention in the future include especially children growing up in highly contaminated regions, and the liquidators of 1986 and 1987 employed in the period immediately

  2. Profiles determination of Cesium-137 concentration in the main areas of Goiania radiological accident

    International Nuclear Information System (INIS)

    Rocca, H.C.C.; Aoki, P.E.; Enokihara, C.T.; Rostelato, M.; Lepki, V.; Bambalas, E.

    1988-07-01

    This paper describes the profiles determination of cesium-137 concentration measured in function of depth and applied in seven areas considered as the main contamination focus. Since november 14th to december 17th 1987, 125 soil drillings were made and a total of 740 soil samples were prepared. Obtained data allowed to calculate the soil volume to be removed from contaminate areas. It was verified that after remotions the remaining activity was approximately 0,89Ci. (author) [pt

  3. Goiania 1987: searching for radiation

    International Nuclear Information System (INIS)

    Clarke Binns, D.A.

    1998-01-01

    The founding of the Searching for Radiation Group following the radiation accident in Goiania, Brazil, in 1987, is described. Particulars on the equipment and detector used, the number of people monitored, the techniques used to gather information on the probable date of the accident, about possibly contaminated places and people are provided and communicating with the general public is addressed. The discussion is divided into three main parts: 1) how the Searching for Radiation Group was formed; 2) the participation of the state Health Secretariat and the street children in the Group and 3) the lessons learned. (author)

  4. Radioactive waste management Goiania - São Paulo: 30 years later

    International Nuclear Information System (INIS)

    Souza, D.C.B. de; Geraldo, B.; Tessaro, A.P.X.; Rostelato, M.E.C.M.; Marumo, J.T.; Carvalho, V.S.; Barbosa, N.K.O.; Vicente, R.

    2017-01-01

    Considered the largest urban radiological accident in the world, the accident in Goiânia with Cesium-137 resulted in the death of four people and injuries in another 49, besides measurable levels of internal or external contamination in 129. The accident generated also environmental contamination and thousands of tons of radioactive waste that resulted from the response activities. The accident occurred as a result of the dismantling of an equipment of radiotherapy by employees of a junkyard. Before the accident was identified, contaminated materials were sent to recycling companies in the state of São Paulo. The objective of this work was to report the existence of waste from Goiania accident in the state of São Paulo and to check the estimated activities at the time of the waste conditioning by measuring the current dose rates in waste packages, allowing a refinement of previously applied calculations. (author)

  5. Radioactive waste management Goiania - São Paulo: 30 years later

    Energy Technology Data Exchange (ETDEWEB)

    Souza, D.C.B. de; Geraldo, B.; Tessaro, A.P.X.; Rostelato, M.E.C.M.; Marumo, J.T.; Carvalho, V.S.; Barbosa, N.K.O.; Vicente, R., E-mail: dcsouza@usp.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    Considered the largest urban radiological accident in the world, the accident in Goiânia with Cesium-137 resulted in the death of four people and injuries in another 49, besides measurable levels of internal or external contamination in 129. The accident generated also environmental contamination and thousands of tons of radioactive waste that resulted from the response activities. The accident occurred as a result of the dismantling of an equipment of radiotherapy by employees of a junkyard. Before the accident was identified, contaminated materials were sent to recycling companies in the state of São Paulo. The objective of this work was to report the existence of waste from Goiania accident in the state of São Paulo and to check the estimated activities at the time of the waste conditioning by measuring the current dose rates in waste packages, allowing a refinement of previously applied calculations. (author)

  6. Source term and radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Mourad, R.

    1987-09-01

    This report presents the results of a study of the source term and radiological consequences of the Chernobyl accident. The results two parts. The first part was performed during the first 2 months following the accident and dealt with the evaluation of the source term and an estimate of individual doses in the European countries outside the Soviet Union. The second part was performed after August 25-29, 1986 when the Soviets presented in a IAEA Conference in Vienna detailed information about the accident, including source term and radiological consequences in the Soviet Union. The second part of the study reconfirms the source term evaluated in the first part and in addition deals with the radiological consequences in the Soviet Union. Source term and individual doses are calculated from measured post-accident data, reported by the Soviet Union and European countries, microcomputer program PEAR (Public Exposure from Accident Releases). 22 refs

  7. A virtual environment for simulation of radiological accidents

    International Nuclear Information System (INIS)

    Silva, Tadeu Augusto de Almeida; Farias, Oscar Luiz Monteiro de

    2013-01-01

    A virtual environment is a computer environment, representative of a subset of the real world, and where models of the real world entities, process and events are included in a virtual (three-dimensional) space. Virtual environments are ideal tools for simulation of certain critical processes, such as radiological accidents, where human beings or properties can suffer irreversible or long term damages. Radiological accidents are characterized by the significant exposure to radiation of specialized workers and general public. The early detection of a radiological accident and the determination of its possible extension are essential factors for the planning of prompt answers and emergency actions. This paper proposes the integration of georeferenced representation of the three-dimensional space and agent-based models, with the objective to construct virtual environments that have the capacity to simulate radiological accidents. The three-dimensional georeferenced representations of space candidates are: 1) the spatial representation of traditional geographical information systems (GIS); 2) the representation adopted by Google Maps®. Adding agents to these spatial representations allow us to simulate radiological accidents, quantify the doses received by members of the public, obtain a possible spatial distribution of people contaminated, estimate the number of contaminated individuals, estimate the impact on the health-network, estimate environmental impacts, generate exclusion zones, build alternative scenarios and train staff to deal with radiological accidents. (author)

  8. A virtual environment for simulation of radiological accidents

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Tadeu Augusto de Almeida, E-mail: tedsilva@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Farias, Oscar Luiz Monteiro de, E-mail: fariasol@eng.uerj.br [Universidade do Estado do Rio de Janeiro (UERJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    A virtual environment is a computer environment, representative of a subset of the real world, and where models of the real world entities, process and events are included in a virtual (three-dimensional) space. Virtual environments are ideal tools for simulation of certain critical processes, such as radiological accidents, where human beings or properties can suffer irreversible or long term damages. Radiological accidents are characterized by the significant exposure to radiation of specialized workers and general public. The early detection of a radiological accident and the determination of its possible extension are essential factors for the planning of prompt answers and emergency actions. This paper proposes the integration of georeferenced representation of the three-dimensional space and agent-based models, with the objective to construct virtual environments that have the capacity to simulate radiological accidents. The three-dimensional georeferenced representations of space candidates are: 1) the spatial representation of traditional geographical information systems (GIS); 2) the representation adopted by Google Maps®. Adding agents to these spatial representations allow us to simulate radiological accidents, quantify the doses received by members of the public, obtain a possible spatial distribution of people contaminated, estimate the number of contaminated individuals, estimate the impact on the health-network, estimate environmental impacts, generate exclusion zones, build alternative scenarios and train staff to deal with radiological accidents. (author)

  9. Improvements in the nuclear accident response system in Brazil

    International Nuclear Information System (INIS)

    Estrada, J.J.S.; Azevedo, E.M.; Knofel, T.M.J.; Recio, J.C.A.; Alves, R.N.

    1998-01-01

    The National Commission on Nuclear Energy has been making outstanding effort to improve its nuclear and radiological accident response systems since the tragic accident in Goiania. Most of this effort is related to nuclear area although the radiological accident has been also considered. This paper describes the improvements in the CNEN response system structure, discusses several topics involving those related to emergency planning and preparedness, and points out some deficiencies that need to be corrected also. The situation during the Goiania accident was more disadvantageous than nowadays, so it is believed that none of the actual deficiencies are sufficient to guess that the population and the environment will not be protected in case of a nuclear or radiological accident

  10. A model national emergency plan for radiological accidents

    International Nuclear Information System (INIS)

    2000-07-01

    The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a result, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request

  11. A model national emergency response plan for radiological accidents

    International Nuclear Information System (INIS)

    1993-09-01

    The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a results, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request. 2 tabs

  12. Radiometric mapping of Goiania urban area: natural and artificial radiation dose

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Nivaldo C.; Dias, Danila C.S.; Guerrero, Eder T. Z.; Alberti, Heber L.C., E-mail: ncsilva@cnen.gov.br, E-mail: danilacdias@gmail.com, E-mail: edertzg@cnen.gov.br, E-mail: heber@cnen.gov.br [Comissao Nacional de Energia Nuclear (LAPOC/CNEN), Pocos de Caldas, MG (Brazil). Laboratorio de Pocos de Caldas; Santos, Eliane E.; Pimenta, Lucinei R.; Costa, Heliana F., E-mail: esantos@cnen.gov.br, E-mail: lucinei@cnen.gov.br, E-mail: heliana@cnen.gov.br [Centro Regional de Ciencias Nucleares do Centro Oeste (CRCN-CO/CNEN-GO), Abadia de Goias, GO (Brazil)

    2013-07-01

    In the city of Goiania it is common to observe in some social groups, such as medical society, academy and communication (media), the association between cancer incidence and the 1987's Goiania radiological accident. Moreover, data of Population-Base Cancer Register published in 2010 by INCA (Instituto Nacional do Cancer), reveals that Goiania figures among the three cities where the major increases in cancer incidence were observed. Therefore, this project aims to provide a dose rate database over Goiania's road network aiming to: 1) assess the level radiation dose to which the population is exposed and 1) provide technical support for social communication of Brazilian Commission for Nuclear Energy. The monitoring was accomplished by using a mobile system (EBERLINE FHT 1376) which includes a 5-liter plastic scintillator detector coupled with a GPS (Global Positioning System) and a portable computer. This system allowed the recording of both the geographical coordinates and the dose rate of each single point. Using a NBR (Natural Background Rejection) the system is able to discriminate between natural and artificial radiation. After the field campaign, the raw data were then treated in a Geographical Information System (GIS) using the ArcGis software in order to produce dose maps. Therefore, this paper will present the results of the current stage of this research encompassing the monitoring of streets located on seven regions Goiania - divided in for administrative purposes. It is important to point out that more than 175175 individual data were collected with results ranging from 13 to 490 nSv/h. (author)

  13. Radiometric mapping of Goiania urban area: natural and artificial radiation dose

    International Nuclear Information System (INIS)

    Silva, Nivaldo C.; Dias, Danila C.S.; Guerrero, Eder T. Z.; Alberti, Heber L.C.

    2013-01-01

    In the city of Goiania it is common to observe in some social groups, such as medical society, academy and communication (media), the association between cancer incidence and the 1987's Goiania radiological accident. Moreover, data of Population-Base Cancer Register published in 2010 by INCA (Instituto Nacional do Cancer), reveals that Goiania figures among the three cities where the major increases in cancer incidence were observed. Therefore, this project aims to provide a dose rate database over Goiania's road network aiming to: 1) assess the level radiation dose to which the population is exposed and 1) provide technical support for social communication of Brazilian Commission for Nuclear Energy. The monitoring was accomplished by using a mobile system (EBERLINE FHT 1376) which includes a 5-liter plastic scintillator detector coupled with a GPS (Global Positioning System) and a portable computer. This system allowed the recording of both the geographical coordinates and the dose rate of each single point. Using a NBR (Natural Background Rejection) the system is able to discriminate between natural and artificial radiation. After the field campaign, the raw data were then treated in a Geographical Information System (GIS) using the ArcGis software in order to produce dose maps. Therefore, this paper will present the results of the current stage of this research encompassing the monitoring of streets located on seven regions Goiania - divided in for administrative purposes. It is important to point out that more than 175175 individual data were collected with results ranging from 13 to 490 nSv/h. (author)

  14. Lessons learned from radiological accidents at medical exposures in radiotherapy

    International Nuclear Information System (INIS)

    Fagundes, J.S.; Ferreira, A.F.; Lima, C.M.A.; Silva, F.C.A. da

    2017-01-01

    An exposure is considered accidental in radiotherapy when there is a substantial deviation in the prescription of treatment. In this work, an analysis of published radiological accidents, both in Brazil and internationally, was performed during medical exposures in radiotherapy treatments, removing the main lessons learned. Of the research carried out, we highlight Brazil with four radiological accidents and one death in the period between 2011 and 2014; the United States of America with 169 accidents with two deaths from 2000 to 2010 and France from 2001 to 2014 had 569 deaths without patients. Lessons learned have been described, for example, that maintenance personnel training should specify limitations or restrictions on the handling or adjustment of critical parts on the accelerator. It is recommended to apply the 10 main lessons learned due to radiological accidents during medical exposures in radiotherapy treatments to avoid future events

  15. A methodology for radiological accidents analysis in industrial gamma radiography

    International Nuclear Information System (INIS)

    Silva, F.C.A. da.

    1990-01-01

    A critical review of 34 published severe radiological accidents in industrial gamma radiography, that happened in 15 countries, from 1960 to 1988, was performed. The most frequent causes, consequences and dose estimation methods were analysed, aiming to stablish better procedures of radiation safety and accidents analysis. The objective of this work is to elaborate a radiological accidents analysis methodology in industrial gamma radiography. The suggested methodology will enable professionals to determine the true causes of the event and to estimate the dose with a good certainty. The technical analytical tree, recommended by International Atomic Energy Agency to perform radiation protection and nuclear safety programs, was adopted in the elaboration of the suggested methodology. The viability of the use of the Electron Gamma Shower 4 Computer Code System to calculate the absorbed dose in radiological accidents in industrial gamma radiography, mainly at sup(192)Ir radioactive source handling situations was also studied. (author)

  16. Developing a comprehensive and accountable database after a radiological accident

    International Nuclear Information System (INIS)

    Berry, H.A.; Burson, Z.G.

    1986-09-01

    After a radiological accident occurs, it is highly desirable to promptly begin developing a comprehensive and accountable environmental database both for immediate health and safety needs and for long-term documentation. The need to assess and evaluate the impact of the accident as quickly as possible is always very urgent, the technical integrity of the data must also be assured and maintained. Care must therefore be taken to log, collate, and organize the environmental data into a complete and accountable database. The key components of the database development are summarized as well as the experience gained in organizing and handling environmental data acquired during: (1) TMI (1979); (2) the St. Lucie Reactor Accident Exercise (through the Federal Radiological Measurement and Assessment Center (FRMAC), March 1984); (3) the Sequoyah Fuels Inc., uranium hexafluoride accident near Gore, Oklahoma (January 1986); and (4) Chernobyl reactor accident in Russia (April 1986)

  17. Radiological accident and incident in Thailand: Lesson to be learned

    International Nuclear Information System (INIS)

    Ya-anant, N.; Tiyapun, K.; Saiyut, K.

    2011-01-01

    Radioactive materials in Thailand have been used in medicine, research and industry for more than 50 y. Several radiological accident and incidents happened in the past 10 y. A serious one was the radiological accident that occurred in Samut Prakan (Thailand) in 2000. The serious radiological accident occurred when the 60 Co head was partially dismantled, taken from that storage to sell as scrap metal. Three victims died and 10 people received high dose from the source. The lesson learned from the radiological accident in Samut Prakan was to improve in many subjects, such as efficiency in Ministerial Regulations and Atomic Energy Act, emergency response and etc. In addition to the serious accident, there are also some small incidents that occurred, such as detection of contaminated scrap metals from the re-cycling of scrap metals from steel factories. Therefore, the radiation protection infrastructure was established after the accident. Laws and regulations of radiation safety and the relevant regulatory procedures must be revised. (authors)

  18. The spread of 137Cs by resuspension of contaminated soil in the urban area of Goiania

    International Nuclear Information System (INIS)

    Pires do Rio, M.A.; Amaral, E.C.S.; Paretzke, H.G.

    2000-01-01

    Measurements regarding the population exposure were performed in Goiania after the radiological accident as well as studies on resuspension and redeposition of 137 Cs in urban areas, on the contribution of soil splash to the 137 Cs uptake by leafy vegetables and on the transfer of 137 Cs from soil to chicken meat and eggs. Periodical street dust sampling was used to follow-up the spreading of the radionuclide in the city. The results do not indicate a measurable spreading of this radionuclide throughout the city from the contaminated areas, but resuspension can lead to significant local contamination of agricultural products, equipment, structures, etc. (author)

  19. Radiological emergency: road map for radiation accident victim transport

    International Nuclear Information System (INIS)

    Costa, V.S.G.; Alcantara, Y.P.; Lima, C.M.A.; Silva, F. C. A. da

    2017-01-01

    During a radiological or nuclear emergency, a number of necessary actions are taken, both within the radiation protection of individuals and the environment, involving many institutions and highly specialized personnel. Among them it is possible to emphasize the air transportation of radiation accident victims.The procedures and measures for the safe transport of these radiation accident victims are generally the responsibility of the armed forces, specifically the Aeronautics, with the action denominated 'Aeromedical Military Evacuation of Radiation Accident Victims'. The experience with the Radiological Accident of Goiânia demonstrated the importance of adequate preparation and response during a radiological emergency and the need for procedures and measures with regard to the transport of radiation victims are clearly defined and clearly presented for the effectiveness of the actions. This work presents the necessary actions for the transport of radiation accident victim during a radiological emergency, through the road map technique, which has been widely used in scientific technical area to facilitate understanding and show the way to be followed to reach the proposed objectives

  20. Radiological study of cerebro-vascular accidents

    International Nuclear Information System (INIS)

    Misri, H.T.; Kabawe, Bassam

    1991-01-01

    The role of computerized tomography scanner in studying the cerebro-vascular accidents has been discussed. One hundred fifty patients with cerebro-vascular accidents were studied at Aleppo University Hospital between 1989-1990. Clinical history and physical examination were recorded, as well as, computerized tomography scanning in all cases without using the contrast media mostly. Relationship between the density of the lesion (inforctionor hemorrhage) and the time has been found. This relationship can help in forensic medicine. (author). 29 refs., 5 tabs., 2 figs

  1. Evaluation of the nuclear and radiological emergency response system in Brazil; Visao critica do sistema de atendimento a emergencia radiologica e nuclear no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Estrada, Julio J.S.; Azevedo, Eduardo M.; Knoefel, Tom M.J. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Brazilian Nuclear Energy Commission (CNEN) has made outstanding efforts to improve its nuclear and radiological accident response system since the tragic accident in Goiania, Brazil. Most of these efforts are related to nuclear emergency although radiological accidents are also considered. Several topics are discussed involving those related to planning and preparedness. Some deficiencies that need to be corrected or improved are pointed out 8 refs.

  2. The Fukushima accident: radiological consequences and first lessons. Proceedings

    International Nuclear Information System (INIS)

    2012-02-01

    This document brings together the available presentations given at the conference organised by the French society of radiation protection about the Fukushima accident, its radiological consequences and the first lessons learnt. Sixteen presentations (slides) are compiled in this document and deal with: 1 - Accident progress and first actions (Thierry Charles, IRSN); 2 - Conditions and health monitoring of the Japanese intervention teams (Bernard Le Guen, EDF); 3 - The Intra Group action after the Fukushima accident (Michel Chevallier, Groupe Intra; Frederic Mariotte, CEA); 4 - Processing of effluents (Georges Pagis, Areva); 5 - Fukushima accident: impact on the terrestrial environment in Japan (Didier Champion, IRSN); 6 - Consequences of the Fukushima accident on the marine environment (Dominique Boust, IRSN); 7 - Territories decontamination perspectives (Pierre Chagvardieff, CEA); 8 - Actions undertaken by Japanese authorities (Florence Gallay, ASN); 9 - Japanese population monitoring and health stakes (Philippe Pirard, InVS); 10 - Citizen oversight actions implemented in Japan (David Boilley, ACRO); 11 - Implementation of ICRP's (International Commission on Radiological Protection) recommendations by Japanese authorities: first analysis (Jacques Lochard, CIPR); 12 - Control of Japan imported food stuff (David Brouque, DGAL); 13 - Questions asked by populations in France and in Germany (Florence-Nathalie Sentuc, GRS; Pascale Monti, IRSN); 14 - Labour law applicable to French workers working abroad (Thierry Lahaye, DGT); 15 - Protection of French workers working in Japan, Areva's experience (Patrick Devin, Areva); 16 - Fukushima accident experience feedback and post-accident nuclear doctrine (Jean-Luc Godet, ASN)

  3. Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

    During the 1960's and 70's the expanded use of nuclear materials to generate electricity, to provide medical benefits, and for research purposes continued to grow in the United States. While substantial effort went into constructing plants and facilities and providing for a number of redundant backup systems for safety purposes, little effort went into the development of emergency response plans for possible major radiological accidents. Unfortunately, adequate plans and procedures had not been developed to co-ordinate either state or federal emergency response assets and personnel should a major radiological accident occur. This situation became quite evident following the Three Mile Island Nuclear Reactor accident in 1979. An accident of that magnitude had not been adequately prepared for and Pennsylvania's limited emergency radiological resources and capabilities were quickly exhausted. Several federal agencies with statutory responsibilities for emergency response, including the U.S. Environmental Protection Agency (EPA), U.S. Department of Energy (DOE), Federal Emergency Management Agency (FEMA), Nuclear Regulatory Commission (NRC), and others provided extensive assistance and support during the accident. However, the assistance was not fully co-ordinated nor controlled. Following the Three Mile Island incident 13 federal agencies worked co-operatively to develop an agreement called the Federal Radiological Emergency Response Plan (FRERP). Signed in November 1985, this plan delineated the statutory responsibilities and authorities of each federal agency signatory to the FRERP. In the event of a major radiological accident, the FRERP would be activated to ensure that a co-ordinated federal emergency response would be available to respond to any major radiological accident scenario. The FRERP encompasses a wide variety of radiological accidents, not just those stemming from nuclear power plants. Activation of the FRERP could occur from major accidents involving

  4. Radiological accident in Panama - IAEA to send assistance team

    International Nuclear Information System (INIS)

    2001-01-01

    Full text: The International Atomic Energy Agency (IAEA) is sending a team of six international experts to assist the authorities of Panama to deal with the aftermath of a radiological accident that occurred at Panama's National Oncology Institute. The Government of Panama informed the IAEA on 22 May about the accident, reported that 28 patients have been affected, and requested IAEA's assistance under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, to which Panama is a party. The assistance to be provided by the expert mission will include: ensuring that the radiation source(s) involved in the accident is (are) in a safe and secure condition; evaluating the doses incurred by the affected patients, inter alia, by analysing the treatment records and physical measurements; undertaking a medical evaluation of the affected patients' prognosis and treatment, taking into account, inter alia, the autopsy findings for those who died; and identifying issues on which the IAEA could offer to provide and/or co-ordinate assistance to minimize the consequences of the accident. The team, which includes senior experts in radiology, radiotherapy, radiopathology, radiation dosimetry and radiation protection from France, USA and Japan, and the IAEA itself, will leave for Panama tomorrow, 26 May

  5. Chernobyl radiological data for accident consequence assessment

    International Nuclear Information System (INIS)

    Bottino, A.; Sacripanti, A.

    1989-01-01

    In this draft is presented the results of a first effort to summarize information related to the radionuclides behaviour in rural areas, in order to estimate pathway parameters to assess accident consequences. This topic encloses relevant aspects concerning contamination of rural environment, the most important being: 1) dry deposition velocities; 2) washout coefficient; 3) accumulation in lakes; 4) migration in soil; 5) winter conditions; 6) filtering effects of forests

  6. Radiological emergencies arising from accidents in Italy

    International Nuclear Information System (INIS)

    Bazzan, A.

    1986-01-01

    The Nuclear Safety and Health Protection Directorate (DISP) of ENEA has organized a structure of officers and technicians on call whenever an accident related to the activity of ENEA-DISP should occur. The most frequent events arise from natural misfortunes, crime, and deficiencies in public services. As regards technical operations such as measurements, removals, decontaminations and transport, DISP requests utilization of the different structures and equipment available to ENEA research centres and, in particular and most frequently, of the Safety and Radioprotection Division of the main ENEA centre: the Casaccia Research Centre. The technicians of this division are always available via telephone or radio, with the firm duty to be present within one hour from the call. The co-operation between these two structures enables timely and efficient intervention in many circumstances so that population and environmental risks can be avoided. Typical accidental situations are earthquakes, adverse atmospheric events, landslides, collapses, railway and road accidents, lost sources discovery, and seizure of illegally detained sources by judicial power. The paper briefly describes some of the situations which have occurred, and the actions carried out to recover sources and to re-establish safe environmental conditions. (author)

  7. The radiological accidents in Tbilisi, Georgia

    International Nuclear Information System (INIS)

    Abramidze, S.; Katamadze, N.; Cruz Suares, R.; Bilbao Alfonso, A.

    1998-01-01

    On october 1997, a facsimile message was received by the IAEA from the Georgian Minister of Health stating that servicemen of the Lilo Training Detachment of Frontier Troops had developed local radiation-induced skin diseases on various parts of their body. Details were sent of the medical diagnoses of the mine victims , as well as information on the radiation sources and dose rates that had caused the exposures. The Georgian Minister of Health requested the IAEAs assistance in the examination and treatment of the patients. An Investigation had revealed that several Cs 137, Co-60 radiation sources and some beta emitters had been found, and that in some places high dose rates had been detected. The Government of Georgia requested the IAEA to send an emergency team to evaluate the radiological conditions at the Lilo Training Centre. The present paper summarizes the findings and lessons learned

  8. Radiological Consequence Analyses Following a Hypothetical Severe Accident in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Juyub; Kim, Juyoul [FNC Technology Co., Yongin (Korea, Republic of)

    2016-10-15

    In order to reflect the lessons learned from the Fukushima Daiichi nuclear power plant accident, a simulator which is named NANAS (Northeast Asia Nuclear Accident Simulator) for overseas nuclear accident has been developed. It is composed of three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. For the source-term estimation module, the representative reactor types were selected as CPR1000, BWR5 and BWR6 for China, Japan and Taiwan, respectively. Considering the design characteristics of each reactor type, the source-term estimation module simulates the transient of design basis accident and severe accident. The atmospheric dispersion prediction module analyzes the transport and dispersion of radioactive materials and prints out the air and ground concentration. Using the concentration result, the dose assessment module calculates effective dose and thyroid dose in the Korean Peninsula region. In this study, a hypothetical severe accident in Japan was simulated to demonstrate the function of NANAS. As a result, the radiological consequence to Korea was estimated from the accident. PC-based nuclear accident simulator, NANAS, has been developed. NANAS contains three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. The source-term estimation module simulates a nuclear accident for the representative reactor types in China, Japan and Taiwan. Since the maximum calculation speed is 16 times than real time, it is possible to estimate the source-term release swiftly in case of the emergency. The atmospheric dispersion prediction module analyzes the transport and dispersion of radioactive materials in wide range including the Northeast Asia. Final results of the dose assessment module are a map projection and time chart of effective dose and thyroid dose. A hypothetical accident in Japan was simulated by NANAS. The radioactive materials were released during the first 24 hours and the source

  9. Radiological Cs-137 accidents/incidents in Estonia

    International Nuclear Information System (INIS)

    Sinisso, Mark

    1997-01-01

    Two radiological accidents/incidents in Estonia are reported. The first -21 October 1994, three brothers entered the Tammiku repository and stole a radioactive Cs-137 source and received dangerous doses of radiation. The other incident (early 1995) involved an abandoned source - a discarded metal cylinder containing Cs-137. Chronologies and factual data are considered for both events. Concise descriptions of the incidents, a medical overview of the fate of injured people and lessons learned are presented

  10. Radiological Cs-137 accidents/incidents in Estonia

    Energy Technology Data Exchange (ETDEWEB)

    Sinisso, Mark [Ministry of Foreign Affairs, Tallin (Estonia)

    1997-12-31

    Two radiological accidents/incidents in Estonia are reported. The first -21 October 1994, three brothers entered the Tammiku repository and stole a radioactive Cs-137 source and received dangerous doses of radiation. The other incident (early 1995) involved an abandoned source - a discarded metal cylinder containing Cs-137. Chronologies and factual data are considered for both events. Concise descriptions of the incidents, a medical overview of the fate of injured people and lessons learned are presented

  11. Proposed classification scale for radiological incidents and accidents

    International Nuclear Information System (INIS)

    2003-04-01

    The scale proposed in this report is intended to facilitate communication concerning the severity of incidents and accidents involving the exposure of human beings to ionising radiations. Like the INES, it comprises eight levels of severity and uses the same terms (accident, incident, anomaly, serious and major) for keeping the public and the media informed. In a radiological protection context, the severity of an event is considered as being directly proportional to the risk run by an individual (the probability of developing fatal or non-fatal health effects) following exposure to ionising radiation in an incident or accident situation. However for society, other factors have to be taken into account to determine severity. The severity scale proposed is therefore based on assessment of the individual radiological risk. A severity level corresponding to exposure of a member of the public in an incident or accident situation is determined on the basis of risk assessment concepts and methods derived from international consensus on dose/effect relationships for both stochastic and deterministic effects. The severity of all the possible exposure situations - worker exposure, collective exposure, potential exposure - is determined using a system of weighting in relation to situations involving members of the public. In the case of this scale, to indicate the severity of an event, it is proposed to make use of the most penalizing level of severity, comparing: - the severity associated with the probability of occurrence of deterministic effects and the severity associated with the probability of occurrence of stochastic effects, when the event gives rise to both types of risk; - the severity for members of the public and the severity for exposed workers, when both categories of individuals are involved; - the severity on the proposed radiological protection scale and that obtained using the INES, when radiological protection and nuclear safety aspects are associated with

  12. NIF: Impacts of chemical accidents and comparison of chemical/radiological accident approaches

    International Nuclear Information System (INIS)

    Lazaro, M.A.; Policastro, A.J.; Rhodes, M.

    1996-01-01

    The US Department of Energy (DOE) proposes to construct and operate the National Ignition Facility (NIF). The goals of the NIF are to (1) achieve fusion ignition in the laboratory for the first time by using inertial confinement fusion (ICF) technology based on an advanced-design neodymium glass solid-state laser, and (2) conduct high-energy-density experiments in support of national security and civilian applications. The primary focus of this paper is worker-public health and safety issues associated with postulated chemical accidents during the operation of NIF. The key findings from the accident analysis will be presented. Although NIF chemical accidents will be emphasized, the important differences between chemical and radiological accident analysis approaches and the metrics for reporting results will be highlighted. These differences are common EIS facility and transportation accident assessments

  13. Restoration of environments affected by residues from radiological accidents: Approaches to decision making

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    The International Atomic Energy Agency, jointly with the Instituto de Radioprotecao e Dosimetria of the Comissao Nacional de Energia Nuclear (CNEN), Brazil, the Forschungszentrum fuer Umwelt und Gesundheit, Institut fuer Strahlenschutz, Germany, and with the collaboration of the European Commission, held a workshop in Rio de Janeiro and Goiania, Brazil, in August 1994, on the scientific basis for decision-making after radioactive contamination of an urban environment. This volume presents the proceedings of the workshop. Eighty-eight participants from 18 Member States and 39 organizations attended the workshop. The main thrust of the workshop was to foster information exchange on the scientific basis for intervention in a de facto situation created by an accident affecting an urban area and resulting in long term human radiation exposure. The venue of the workshop was particularly appropriate. Some years before, in September 1987, an accident involving a lost radioactive source had occurred in the city of Goiania, causing serious contamination and serious injuries and deaths among members of the public. The IAEA, in close collaboration with the Brazilian authorities and with the help of an international group of senior experts, drew up and published a comprehensive appraisal of that accident so that Member States might benefit from the lessons to be learned. In 1994, seven years after that fateful event, it was felt that the time was ripe to draw further lessons and to facilitate an exchange of ideas among experts.

  14. Restoration of environments affected by residues from radiological accidents: Approaches to decision making

    International Nuclear Information System (INIS)

    2000-05-01

    The International Atomic Energy Agency, jointly with the Instituto de Radioprotecao e Dosimetria of the Comissao Nacional de Energia Nuclear (CNEN), Brazil, the Forschungszentrum fuer Umwelt und Gesundheit, Institut fuer Strahlenschutz, Germany, and with the collaboration of the European Commission, held a workshop in Rio de Janeiro and Goiania, Brazil, in August 1994, on the scientific basis for decision-making after radioactive contamination of an urban environment. This volume presents the proceedings of the workshop. Eighty-eight participants from 18 Member States and 39 organizations attended the workshop. The main thrust of the workshop was to foster information exchange on the scientific basis for intervention in a de facto situation created by an accident affecting an urban area and resulting in long term human radiation exposure. The venue of the workshop was particularly appropriate. Some years before, in September 1987, an accident involving a lost radioactive source had occurred in the city of Goiania, causing serious contamination and serious injuries and deaths among members of the public. The IAEA, in close collaboration with the Brazilian authorities and with the help of an international group of senior experts, drew up and published a comprehensive appraisal of that accident so that Member States might benefit from the lessons to be learned. In 1994, seven years after that fateful event, it was felt that the time was ripe to draw further lessons and to facilitate an exchange of ideas among experts

  15. Role of the Federal Radiological Monitoring and Assessment Center (FRMAC) following a radiological accident

    International Nuclear Information System (INIS)

    Doyle, J.F. III.

    1986-01-01

    The Federal Radiological Emergency Response Plan (FRERP) calls for the Department of Energy to establish a Federal Radiological Monitoring and Assessment Center (FRMAC) immediately following a major radiological accident to coordinate all federal off-site monitoring efforts in support of the State and the Cognizant Federal Agency (CFA) for the facility or material involved in the accident. Some accidents are potentailly very complex and may require hundreds of radiation specialists to ensure immediate protection of the public and workers in the area, and to identify priorities for the Environmental Protection Agency (EPA) long-term efforts once the immediate protective actions have been carried out. The FRMAC provides a working environment with today's high technology tools (i.e., communication, computers, management procedures, etc.) to assure that the State and CFA decision makers have the best possible information in a timely manner on which to act. The FRMAC planners also recognize an underlying responsibility to continuously document such operations in order to provide the State, the CFA, and the EPA the technical information they will require for long term assessments. In addition, it is fully recognized that information collected and actions taken by the FRMAC will be subjected to the same scrutiny as other parts of the accident and the overall response

  16. The radiological accident at the irradiation facility in Nesvizh

    International Nuclear Information System (INIS)

    1996-01-01

    More than 40 years of experience in radiation processing has shown that such technology is generally used safely, and steady improvement in the design of facilities and careful selection and training of operators have contributed to this good safety record. However, some cases of circumvention of safety systems have been registered and it is documented that the consequences of radiological accidents at industrial radiation facilities can be extremely serious. The causes of accidents may have some points in common, but at the same time may be highly specific. A detailed study of these common and specific features seems to be of great importance for further improvements in safety systems. One such event occurred on 26 October 1991 at an industrial sterilization facility in Nesvizh, Belarus, when the operator entered the irradiation chamber and was severely exposed to a lethal dose of radiation. The significant feature of this case was related to the medical management. It should be underlined that some circumstances of the accident only came to light during the post-accident review made by the IAEA. To document the causes and consequences of the accident and to define the lessons learned are of help to those people with responsibility for the safety of such facilities and to those medical authorities who might be involved in the management of a radiation event. 16 refs, figs, tabs, photographs

  17. Physical reconstruction of the radiological accident of Chilca (Lima - Peru)

    International Nuclear Information System (INIS)

    Lachos, A.; Marquez, J. F.

    2014-08-01

    The radiological accident happened in the Chilca District, the Canete County at 60 km to the south of Lima-Peru, during the night of January 11 to 12, 2012. The physical reconstruction of the accident was carried out in January 21, 2012, by means of the information gathering administrative and technical of the radioactive source as well as of the installation, the personnel and the involved procedures in the accidental event, information of the space geometry where the event took place. The preliminary information indicates that the source could have been locked in the guide tube of the equipment, next to the collimator in the first takes radiographic. The radiation monitors were not activated on the procedure, impeding this way, not to realize the flaw and causing that the personnel were exposed to the radiation during the whole work period. Their hands and especially their fingers would have been only to some millimeters of the source. With the obtained information and the measurements of the exposure rates of the radioactive source, was carried out the dose calculation to total body, the dose received in the hands and the dose received in the index finger of the left hand. The accident happened by operative procedure breach, by lack of training of the operators. The physical reconstruction of the accident contributes fundamental information for the decisions taking in the medical management of the accidents by radiation. (author)

  18. Review of Atomic Energy Laws Related to Radiological Accidents and Methods of Improvement

    International Nuclear Information System (INIS)

    Chang, Gun Hyun; Kim, Sang Won; Yoo, Jeong; Ahn, Hyoung Jun; Park, Young Sik; Kim, Hong Suk; Kwon, Jeong Wan; Jang, Ki Won; Kim, Sok Chul

    2009-01-01

    Atomic energy-related laws in Korea have a two pronged management system for radiological accidents. To be specific, the Atomic Energy Act is applicable to all radiological accidents, i.e. accidents pertaining to nuclear facilities and radioactive materials while the Act for Physical Protection and Radiological Emergency ('APPRE') applies to accidents related to nuclear materials and large-scale nuclear facilities. The Atomic Energy Act contains three provisions directly related with radiological accidents (Articles 89, 98 and 102). Article 89 provides for the obligations of nuclear licensees or consigned transporters to institute safety measures and file a report to the head of the Ministry of Education, Science and Technology ('MEST') in the event of any radiological accident during transport or packing of radioactive materials, etc. Article 98 stipulates obligations of nuclear licensees to implement safety procedures and submit a report to the Minister of Education, Science and Technology concerning radiation hazards arising in the event a radiological accident occurs in connection with nuclear projects, as well as the Minister's requests to implement necessary measures. Article 102 explicitly provides for obligations to file a report to the Minister in the event of theft, loss, fire or other accidents involving radioactive materials, etc. in the possession of nuclear licensees. The APPRE classifies radiological accidents according to location and scale of the accidents. Based on location, accidents are divided into accidents inside or outside nuclear facilities. Accidents inside nuclear facilities refer to accidents that occur at nuclear reactors, nuclear fuel cycling facilities, radioactive waste storage, treatment and disposal facilities, facilities using nuclear materials and facilities related to radioisotopes of not lower than 18.5PBq (Subparagraph 2, Article 2 of the APPRE) while accidents outside nuclear facilities mean accidents that take place on

  19. Recommendations guide in radiological accidents for first respondents, paramedical personnel

    International Nuclear Information System (INIS)

    Astudillo, A. J.; Ambriz, J. J.; Paredes, L. C.

    2011-10-01

    The lenders of medical services hope to provide the appropriate attention to the patients due to the great variety of scenarios that are presented. One of these involves the patient that has been exposed or contaminated with radioactive materials. Due to this situation the recommendations guide for the primary task forces are presented. Elements of medical response before the radiological accidents presence. The objective of these guides is to give the guidelines for the initial response to the emergency that fulfills the following criterions: a) to Apply with readiness all the reasonable measures to protect the victims and the public, in order to minimizing the radiological and not radiological effects to the health; b) to Save lives and to develop the procedures required in the medical emergency; c) to Treat the injuries caused by the radiation and the resulting injuries of the emergency; d) to Compile and to protect the information that can be useful to treat the effects to the health, of the victims and public in general, and to impede that emergencies seemed are repeat in the future; e) to Create and to maintain the public's trust in the response; f) to Establish a base for an action of lingering response and g) to Suggest evaluation criterions of the radiological emergency, the organization criterions, operation and surrounding of the emergency area. (Author)

  20. A radiological accident consequence assessment system for Hong Kong

    International Nuclear Information System (INIS)

    Wong, M.C.; Lam, H.K.

    1993-01-01

    An account is given of the Hong Kong Radiological Accident Consequence Assessment System which would be used to assess the potential consequences of an emergency situation involving atmospheric release of radioactive material. The system has the capability to acquire real-time meteorological information from the Observatory's network of automatic stations, synoptic stations in the nearby region as well as forecast data from numerical prediction models. The system makes use of these data to simulate the transport and dispersion of the released radioactive material. The effectiveness of protective action on the local population is also modeled. The system serves as a powerful aid in the protective action recommendation processes

  1. Radiological consequence of Chernobyl nuclear power accident in Japan

    International Nuclear Information System (INIS)

    Uchiyama, Masafumi; Nakamura, Yuji; Kankura, Takako; Iwasaki, Tamiko; Fujimoto, Kenzo; Kobayashi, Sadayoshi.

    1988-03-01

    Two years have elapsed since the accident in Chernobyl nuclear power station shocked those concerned with nuclear power generation. The effect that this accident exerted on human environment has still continued directly and indirectly, and the reports on the effect have been made in various countries and by international organizations. In Japan, about the exposure dose of Japanese people due to this accident, the Nuclear Safety Commission and Japan Atomic Energy Research Institute issued the reports. In this report, the available data concerning the envrionmental radioactivity level in Japan due to the Chernobyl accident are collected, and the evaluation of exposure dose which seems most appropriate from the present day scientific viewpoint was attempted by the detailed analysis in the National Institute of Radiological Sciences. The enormous number of the data observed in various parts of Japan were different in sampling, locality, time and measuring method, so difficulty arose frequently. The maximum concentration of I-131 in floating dust was 2.5 Bq/m 3 observed in Fukui, and the same kinds of radioactive nuclides as those in Europe were detected. (Kako, I.)

  2. Cesium-137 monitoring of aquatic and terrestrial environment in Goiania

    International Nuclear Information System (INIS)

    Godoy, J.N.O.; Guimaraes, J.R.D.; Gouvea, V.A.; Rochedo, E.R.R.

    1988-01-01

    During the Goiania radiological accident, aprox. 1200 Ci of Cs - 137 were inadvertently manipulated and an unknown fraction of this total was available for environmental dispertion during at least 6 weeks, before efficient remedial action could be undertaken. The main dispersion pathways were rainwater run-off and soil ressuspension and further deposition. Cs-137 monitoring in the local environment started in the first week of October, including to date aprox. 1300 measurements of soil, vegetable (fruits and kitchen-gardens), ground and drinking water, sediments and fish, aerosol, precipitation and external dose measurement with TL dosimeters, in the surroundings of the main contamination spots. Until the conclusion of de-contamination activities in late December, the ranges of Cs-137 in a 50m radius of evacuated areas were as follows: 10 2 -10 4 Bq/Kg for surface soils and edible vegetables, 10 0 -10 1 mBq/m 3 in air and 10 Bq/l in all water types. River sediment and fish 5-10 Km downstream the accident are ranged respectively 10 2 -10 3 and 10 2 /Kg. These data indicated the pathways and locations for intervention for further reduction of radiation exposure. This intervention consisted mainly in tree-tipping and surface soil removal. (author) [pt

  3. The information in Nuclear Energy: The Experience in Goiania

    International Nuclear Information System (INIS)

    Ferreira, W.M.; Campos, E.P.

    1998-01-01

    After the accident in Goiania the Nuclear Energy National Commission implant in this city a information system for the human population. The objective consisted on giving a technical knowledge about the nuclear energy utilization. This work represents the utilized strategy and the results reached in this program during the period 1991-1996

  4. Multidisciplinary response for a radiological accident developed in Argentina

    International Nuclear Information System (INIS)

    Di Giorgio, Marina; Tadic, Matilde; Vazquez, Marina; Cateriano, Miguel; Jordan, Osvaldo; Rojas, Carlos A.; Portas, M.; Coppola, A.; De Lellis, M. del C.; Dovasio, F.

    2010-01-01

    In January 2009 during an oil well logging task in Rincon de los Sauces, Province of Neuquen, Argentina, and, as a result of the temporary loss of control of a 137 Cs sealed source of 92,5 GBq (2,5 Ci), two workers were allegedly exposed to ionizing radiation. The Health Emergency Coordination System in Neuquen activated the Radiological Emergency Intervention System of the Nuclear Regulatory Authority (NRA). An initial assessment of the accident scenario and the involved persons was performed. Two workers were were transfer to Buenos Aires for a biodosimetry evaluation. In Buenos Aires, the Burn Hospital performed the first diagnostic and therapeutic approach of the radioinduced skin injuries. The NRA estimated the biological absorbed doses and the studies of telethermography. The Italian Hospital was in charge of the studies using ultrasonography and Eco- Doppler. As a result of the multidisciplinary evaluation performed, one of the workers was diagnosed with superficial radioinduced dermatitis. The mentioned intervention highlighted the importance of multidisciplinary and multiparametric work for the evaluation of a radiological accident, as well as for the diagnosis and early treatment of the exposed persons. (authors) [es

  5. National response plan - Major nuclear or radiological accidents

    International Nuclear Information System (INIS)

    2014-02-01

    France has been implementing stringent radiation protection and nuclear safety and security measures for many years. However, this does not mean that the country is exempt from having to be prepared to deal with an emergency. Changes in France, Europe and other parts of the globe have made it necessary for France to reconsider how it responds to nuclear and radiological emergencies. As the potential impact of a nuclear or radiological accident can affect a wide range of activities, the plan described herein is based on a cross-sector and inter-ministerial approach to emergency response. The Chernobyl and Fukushima-Daiichi disasters are proof that the consequences of a major nuclear or radiological accident can affect all levels of society. These challenges are substantial and relate to: public health: An uncontrolled nuclear accident can have immediate consequences (death, injury, irradiation) as well as long-term consequences that can lead to increased risk of developing radiation-induced diseases (such as certain types of cancer); environmental quality: Radiation contamination can last for several decades and, in some cases, can result in an area being closed off permanently to the public; economic and social continuity: Nuclear accidents bring human activity to a halt in contaminated areas, disrupting the economic and social order of the entire country. It may therefore be necessary to adapt economic and social systems and carry out clean-up operations if people and businesses have been displaced; quality of international relations: Related to fulfillment of obligations to alert and inform European and international partners. This international dimension also covers the protection of French nationals present in countries stricken by a nuclear accident. This national plan provides reference information on how to prepare for a nuclear or radiological emergency and make the appropriate decisions in the event of an emergency. It covers the emergency phase (including

  6. Continuing training in radiological protection as an effective means of avoiding radiological accidents

    International Nuclear Information System (INIS)

    Lima, C.M.A.; Pelegrineli, S.Q.; Martins, G.; Lima, A.R.; Silva, F.C.A. da

    2017-01-01

    it is notorious that one of the main causes of radiological accidents is the lack of knowledge of radiological protection of workers. In order to meet the needs of professionals in acquiring a solid base in radiological protection and safety, was created in 2013, by the Casa Branca School / SP and technically supported by the company MAXIM Cursos, the 'Post-Graduation Course Lato Sensu de Radiological Protection in Medical, Industrial and Nuclear Applications', which offers a broad improvement in radiation protection. The course of 380 hours and duration of 18 months is divided into 13 modules, including theoretical classes, in person and online using the virtual classroom and practical training in radiation protection in general. In the end students should present a monograph, guided by a course teacher and reviewed by an Examining Bank. Five classes have been formed in these four years, totaling 92 students. In all, 51 monographs have been defended on topics of technical and scientific interest. For this, the Faculty consists of 25 professors, being 9 Doctors, 13 Masters and 3 Specialists in Radiological Protection

  7. Radiological environment within an NPP after a severe nuclear accident

    Science.gov (United States)

    Andgren, Karin; Fritioff, Karin; Buhr, Anna Maria Blixt; Huutoniemi, Tommi

    2017-09-01

    The radiological environment following a severe nuclear accident can be visualised on building layouts. The direct radiation in an area (or room) can be visualized on the layout by a colouring scheme depending on the dose rate level (for example orange for high gamma dose rate level and purple for an intermediate gamma dose rate level). Following the Fukushima accident, a need for update of these layouts has been identified at the Swedish nuclear power plant of Forsmark. Shielding calculations for areas where access is desired for severe accident management have been performed. Many different sources of radiation together with different types of shielding material contribute to the dose that would be received by a person entering the area. External radiation from radioactivity within e.g. pipes and components is considered and also external radiation from radioactivity in the air (originating from diffuse leakage of the containment atmosphere). Results are presented as dose rates for relevant dose points together with a method for estimating the dose rate levels for each of the rooms of the reactor building.

  8. Radiological environment within an NPP after a severe nuclear accident

    Directory of Open Access Journals (Sweden)

    Andgren Karin

    2017-01-01

    Full Text Available The radiological environment following a severe nuclear accident can be visualised on building layouts. The direct radiation in an area (or room can be visualized on the layout by a colouring scheme depending on the dose rate level (for example orange for high gamma dose rate level and purple for an intermediate gamma dose rate level. Following the Fukushima accident, a need for update of these layouts has been identified at the Swedish nuclear power plant of Forsmark. Shielding calculations for areas where access is desired for severe accident management have been performed. Many different sources of radiation together with different types of shielding material contribute to the dose that would be received by a person entering the area. External radiation from radioactivity within e.g. pipes and components is considered and also external radiation from radioactivity in the air (originating from diffuse leakage of the containment atmosphere. Results are presented as dose rates for relevant dose points together with a method for estimating the dose rate levels for each of the rooms of the reactor building.

  9. Medical management of radiological accidents in non-specialized clinics: mistakes and lessons

    International Nuclear Information System (INIS)

    Jikia, D.

    2009-01-01

    In 1996-2002 three radiological accidents were developed in Georgia. There were some people injured in those accidents. During medical management of the injured some mistakes and errors were revealed both in diagnostics and scheme of the treatment. The goal of this article is to summarize medical management of the mentioned radiological accidents, to estimate reasons of mistakes and errors, to present the lessons drawn in result of Georgia radiological accidents. There was no clinic with specialized profile and experience. Accordingly due to having no relevant experience late diagnosis can be considered as the main error. It had direct influence on the patients' health and results of treatment. Lessons to be drawn after analyzing Georgian radiological accidents: 1. informing medical staff about radiological injuries (pathogenesis, types, symptoms, clinical course, principles of treatment and etc.); 2. organization of training and meetings in non-specialized clinics or medical institutions for medical staff; 3. preparation of informational booklets and guidelines.(author)

  10. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    International Nuclear Information System (INIS)

    Angelov, V.; Semova, T.; Bonchev, Ts.

    1995-01-01

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs

  11. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    Energy Technology Data Exchange (ETDEWEB)

    Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Semova, T; Bonchev, Ts [Sofia Univ. (Bulgaria). Fizicheski Fakultet

    1996-12-31

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs.

  12. Determination of cesium-137 soil-to-plant concentration ratios for vegetables in Goiania City, Brazil

    International Nuclear Information System (INIS)

    Lauria, D.C.; Sachett, I.A.; Pereira, J.C.; Zenaro, R.

    1994-01-01

    The radiological accident that occurred in Goiania City, Brazil, in September 1987, led to the spreading of 137 Cs in the urban area. Even after the decontamination procedure, there was a reminiscence of 137 Cs activity in the soil of residential gardens. This activity was enough to conduct preliminary experiments for determination of soil to vegetable concentration ratios. Experiments were conducted for carrots, lettuce and radishes. Two types of experimental patterns were used to determine the concentration ratios: lysimeters cultivation under greenhouse condition and soil cultivation in open field plot. The concentration ratios measured for cultivation under greenhouse and field plot conditions are considerably higher than those mentioned in the International Union of Radioecologist (IUR) data bank for the same vegetables and cultivation condition. (author) 5 refs.; 2 figs.; 3 tabs

  13. Study of application of protective measures for the public and remediation of contaminated areas in case of nuclear and / or radiological accidents in Brazil

    International Nuclear Information System (INIS)

    Silva, Diogo Neves Gomes da

    2011-01-01

    Since the radiological accident in Goiania in 1987, the IRD (Institute of Radiological Protection and Dosimetry - IRD / CNEN) has been developing tools to support decision-making processes after a nuclear or radiological accident which leads to an environmental contamination and to an exposure of individuals the public These processes include the establishment of a supporting multicriteria model, which involves the application of protective and remediation measures of contaminated areas in tropical environments. In this study, it was performed an evaluation of the efficiency of these measures in order to determine the consequences of their implementation, based on results obtained from the code SIEM (Emergency Integrated System), which constitutes an environmental mode1 developed at IRD to simulate this type of accident. In order to perform this evaluation, it was first developed a database containing descriptions of various protection/remediation measures, which could be applied nationwide. Afterwards, some basic scenarios were established, considering the environmental, housing and food characteristics of the population of the vicinity of the nuclear power plants in Angra dos Reis (state of Rio de Janeiro). Thus, the accident simulations were carried out separately containing releases of 137 Cs, 90 Sr and 131 I. The results showed that the dose reduction varies according to the extent and the timing of the remediation measure applied. Although it is possible to establish some basic guidelines, generic solutions are not recommended, since the resulting doses are highly dependent on the actual situation. Any decision-making process should be made case by case, according to the actual conditions of the affected area and to the occupation characteristics and use of the affected areas, considering the characteristics of the source term of contamination, the time of the year in which the accident occurs, the local agricultural practices and food habits of real people

  14. Report about decontamination and follow-up of Cesium-137 radiation victims at the FEBEM unit in Goiania; Relato de participacao e a experiencia adquirida no tratamento de descontaminacao e acompanhamento de radioacidentados com Cesio-137 na Unidade FEBEM de Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Cambises, P.B.S.; Sanchez, A.S.; Almeida, C.C. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    1997-12-31

    The acquired experience and the facts related to treatment and external decontamination of contaminated people of the primary group of the Goiania accident are reported. This group was sent to Unidade FEBEM from October 10 to December 20, 1987. The external decontamination methods and the observed results obtained by daily monitoring reports are presented. Furthermore, the applied methodology to release people or to ask them for further periodical check ups at the radiological control units is also presented. (author) 2 refs., 7 figs., 2 tabs.

  15. Goiania radiation accident: 30 years - a half-life for a whole life..; Acidente radiológico em Goiânia: 30 - anos - uma meia-vida para uma vida inteira...

    Energy Technology Data Exchange (ETDEWEB)

    Reis, R.G.; Lucena, E.A.; Arantes, R.R.; Silva, A.A.; Reis, A.A., E-mail: rocio@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Serviço de Ensino

    2017-07-01

    The radiological accident in Goiânia, Brazil, considered the largest urban radiological accident in the world, generated several publications in the technical area that are widely disseminated in the scientific literature, given the importance of the lessons learned. However, in a simple conversation with people who worked on that accident, it is noted that many reports have not been recorded. In this year in which 30 years of the event is completed, it will be of great value to record personal testimonies that are not in technical or scientific books. And what can we tell after a half-life that lasted for a lifetime? The lived stories, the situations, the improvisations, the way to solve, the overcoming, the human side, the emotions, happy or sad, short or long, funny or not. The objective of this work is to preserve, maintain and divulge reports and situations experienced by people who worked on the radiological accident with Cs-137 in Goiânia. Audio or video recordings about experiences lived in Goiânia by people who worked in that emergency situation were carried out. The reports are free and the form of registration is always at the discretion of the narrator. Storing records allows to preserve, maintain, and disclose the accident to other generations.

  16. Treatment initiatives after radiological accidents: TIARA first step

    International Nuclear Information System (INIS)

    Menetrier, F.; Berard, P.; Joussineau, S.; Stradling, N.; Hodgson, V.; List, MA.; Morcillo, W.; Paile, D.; Holt, T.; Eriksson

    2006-01-01

    Full text of publication follows: T.I.A.R.A. [Treatment Initiatives After Radiological Accidents] project is a consortium of 8 European partners. This project is part of the Preparatory Action on Security Research recently launched by the European Commission. The Preparatory Action is intended to reach preliminary conclusions on the needs for the security of European Union citizens before the launch of the Security Research Programme in 2007. The principal purpose of T.I.A.R.A. is to constitute a European network which will participate in enhancing the management of a crisis in the hypothesis of a malevolent dispersal of radionuclides in a public place. The main concern is to identify and define effective medical treatments for internal radioactive contamination. A preview of the state of treatment of contamination by radionuclides (especially actinides) in Europe highlights the following points: a decrease in the number of physicians with experience of treatment, a need for generalised agreement on treatment decisions and protocols, unanticipated operational issues and research into new treatments. If treatment is to be effective then several factors must be addressed and these include: firstly, the availability of effective specific treatment for the radionuclides involved, their rapid transport to and distribution of the drugs at the place of the malevolent dispersal and the easy administration of the drug even if numerous people are contaminated. The objectives of T.I.A.R.A. are threefold. First to provide straightforward guidance on dose assessment and efficacy of treatment which is readily understood by health physicists and physicians who do not have detailed knowledge and experience in radiological protection matters. Second, to foresee the operational needs for treating persons when there are mass casualties. Third, to monitor scientific and technological development on research into new treatments. Progress in all these aspects of the project will be

  17. Review of Atomic Energy Laws Related to Radiological Accidents and Methods of Improvement

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Gun Hyun; Kim, Sang Won; Yoo, Jeong; Ahn, Hyoung Jun; Park, Young Sik; Kim, Hong Suk; Kwon, Jeong Wan; Jang, Ki Won; Kim, Sok Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2009-05-15

    Atomic energy-related laws in Korea have a two pronged management system for radiological accidents. To be specific, the Atomic Energy Act is applicable to all radiological accidents, i.e. accidents pertaining to nuclear facilities and radioactive materials while the Act for Physical Protection and Radiological Emergency ('APPRE') applies to accidents related to nuclear materials and large-scale nuclear facilities. The Atomic Energy Act contains three provisions directly related with radiological accidents (Articles 89, 98 and 102). Article 89 provides for the obligations of nuclear licensees or consigned transporters to institute safety measures and file a report to the head of the Ministry of Education, Science and Technology ('MEST') in the event of any radiological accident during transport or packing of radioactive materials, etc. Article 98 stipulates obligations of nuclear licensees to implement safety procedures and submit a report to the Minister of Education, Science and Technology concerning radiation hazards arising in the event a radiological accident occurs in connection with nuclear projects, as well as the Minister's requests to implement necessary measures. Article 102 explicitly provides for obligations to file a report to the Minister in the event of theft, loss, fire or other accidents involving radioactive materials, etc. in the possession of nuclear licensees. The APPRE classifies radiological accidents according to location and scale of the accidents. Based on location, accidents are divided into accidents inside or outside nuclear facilities. Accidents inside nuclear facilities refer to accidents that occur at nuclear reactors, nuclear fuel cycling facilities, radioactive waste storage, treatment and disposal facilities, facilities using nuclear materials and facilities related to radioisotopes of not lower than 18.5PBq (Subparagraph 2, Article 2 of the APPRE) while accidents outside nuclear facilities mean accidents

  18. Audit of litigation against the accident and emergency radiology department.

    Science.gov (United States)

    Cantoni, S; De Stefano, F; Mari, A; Savaia, F; Rosso, R; Derchi, L

    2009-09-01

    The aims of this study were to reduce and monitor litigation due to failure to diagnose a fracture, to evaluate whether the cases were due to radiological error or other problems in the diagnostic and therapeutic management of patients and to identify organisational, technical or functional changes or guidelines to improve the management of patients with suspected fracture and their expectations. We analysed the litigation database for the period 2004-2006 and extracted all episodes indicating failure to diagnose a fracture at the accident and emergency radiology department of our centre. The radiographs underwent blinded review by two experts, and each case was jointly analysed by a radiologist and a forensic physician to see what led to the compensation claim. We identified 22 events (2004 seven cases; 2005 eight cases; 2006 seven cases). Six cases were unrelated to radiological error. Six were due to imperceptible fractures at the time of the examination. These were accounted for by the presence of a major lesion distracting the examiner's attention from a less important associated lesion in one case, a false negative result in a patient examined on a incompletely radiolucent spinal board and underexposure of the coccyx region in an obese patient. Six cases were related to an interpretation error by the radiologist. In the remaining cases, the lesion being referred to in the compensation claim could either not be established or the case was closed by the insurance company without compensation. Corrective measures were adopted. These included planning the purchase of a higher performance device, drawing up a protocol for imaging patients on spinal boards, reminding radiologists of the need to carefully scrutinise the entire radiogram even after having identified a lesion, and producing an information sheet explaining to patients the possibility of false negative results in cases of imperceptible lesions and inviting them to return to the department if symptoms

  19. ANS [American Nuclear Society] topical meeting on radiological accidents: Perspectives and emergency planning: Proceedings

    International Nuclear Information System (INIS)

    1987-03-01

    The increasing use of radioactive materials and the increasing public concern about possible accidents involving these materials has led to greater emphasis on preparing for such emergencies. The ANS Topical Meeting on Radiological Accidents - Perspectives and Emergency Planning provided a review of experiences with radiological accidents. The meeting covered some of the most important aspects of radiological accidents. Papers were presented which dealt with radiological accident experience. Technical response to accidents is of primary interest to many in the nuclear community; most of the papers submitted fell into this area. So many of these papers dealt with the use of computers in response that a session on that topic was arranged. A very significant impact of most radiological accidents is the cost, especially the cost of cleanup. There were papers on what is known about costs and associated current topics, such as modification and extension of the Price-Anderson Act. At least as important as the technical response to accidents is how society attempts to deal with them. A session on institutional issues was included to discuss how governments and other organizations respond to and deal with accidents. Medical effects of accidents are of great concern to the public. Invited papers to review the effects of high doses of radiation as well as very low doses were included in that session. Although the nuclear industry has an excellent safety record, this fact often does not agree with the public perception of the industry. The final session explored the public response to and perception of radiological emergencies and accidents. This subject will ultimately determine the future use of radioactive materials in this country

  20. Assessment of ionizing radiation as a risk factor for breast cancer incidence in Goiania

    International Nuclear Information System (INIS)

    Lage, Leonardo Bastos

    2016-01-01

    annual averages of crude rates of incidence. The spatial correlation of groups (clusters) of new cases has been verified, through the Moran index, and from geographically referenced radiometric measurements obtained in the previous step, the correlation between the incidence of breast cancer and ionizing radiation levels was assessed by unconditional linear regression. The results were presented in two papers. In the first, radiometric surveys were conducted in 1.405 of the 1.636 (85,9%) census tracts sectors that make up the seven Sanitary Districts in the city of Goiania. In total 197.811 geographically referenced measures of the absorbed dose rate in the air were made, with a average of 29,85 ± 7,47 and amplitude from 9,17 to 629,88 nGy/h. From these values were estimated the average of annual effective dose and collective effective dose for outdoor environments, with values of 0,036 ± 0,003 mSv/year and 28,51 ± 11,68 man.mSv/year, respectively. The levels of exposure to external gamma radiation, found in the city of Goiania 28 years after the radiological accident with Cesium-137, are compatible with the values estimated by UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation). And the value of the annual average of effective dose in Goiania, is lower than in other places in Brazil, which have only 'background' of natural radiation outdoors. The results obtained in this study indicate that the dosimetric situation in Goiania does not present undue risk to people and the environment. In the second article, were identified 4.105 new cases of breast cancer, 2.233 in the study area and 1.286 (57,59%) of these geographically referenced. The annual average values of crude rates of incidence, considering the total numbers of cases and geographically referenced presented in the study area are, respectively, 102,91 and 71,86 new cases per 100.000 women. The crude rate of incidence in Goiania was 66,59 cases per 100.000, while in the

  1. Convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1986-11-01

    The full text of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency adopted by the General Conference at its special session from 24-26 September 1986 is presented. It is stipulated that the States Parties shall cooperate between themselves and with the Agency to facilitate prompt assistance in the event of a nuclear accident or radiological emergency to minimize its consequences and to protect life, the property and the environment from the effects of radioactive releases

  2. Investigation of evaluation method for marine radiological impact during an accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    In 2012, JNES carried out to investigate the measurement information of radionuclide released to the ocean at Fukushima Daiichi NPP accident, the foreign regulation for marine radiological impact, and the evaluation method for release and diffusion to the ocean at the accident inside and outside Japan. (author)

  3. Radiological protection and the Fukushima Daiichi accident. Responses of the key international organisations

    Energy Technology Data Exchange (ETDEWEB)

    Clement, Christopher

    2017-10-01

    The Fukushima Daiichi nuclear power plant accident in March 2011 shook the radiological protection world. All major organisations in the radiological protection field turned their eyes to Japan. Their actions, driven by their mandates, are reflected in their respective landmark reports on the accident. Reports of the International Commission on Radiological Protection, World Health Organisation, United Nations Scientific Committee on the Effects of Atomic Radiation, and International Atomic Energy Agency are summarised. Collaboration between key international organisations is strong, based in part on informal interactions which need to be backed up with formal relations to ensure solid long-term collaboration.

  4. Radiologic accidents in industrial gamma radiography - Brazilian cases; Acidentes radiologicos em gamagrafia industrial - casos brasileiros

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Francisco Cesar Augusto da [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Three severe radiological accidents in industrial gamma radiography happened in Brazil during the period of 1985 to 1988. Five operators and nineteen public people were involved. These accidents caused some injuries in parts of the body, mainly hands and fingers. The main causes were faults in source monitoring, inadequate routine procedures and unknowing of radiation warning symbol by public people. The present paper shows the Brazilian cases of radiological accidents and makes some analysis of them. (author) 1 ref., 1 tab.; e-mail: dasilva at ird.gov.br

  5. Guidelines for calculation of atmospheric dispersion and radiological consequences of design basis reactor accidents - Severe accident calculation guidelines, EPR

    International Nuclear Information System (INIS)

    Martens, R.; Schmitz, B.M.; Horn, M.

    1999-01-01

    The activities carried out within the (reduced) project period (1. Sept. until 31. Dec. 1998) for coordinated harmonization between France and Germany, of guidelines for calculation of the radiological consequences of a severe reactor accident, are summarized. (orig./CB) [de

  6. Relocation tabletop exercise: federal radiological response in the post-accident phase

    International Nuclear Information System (INIS)

    Grant, K.; Adler, M.V.; Wolff, W.F.

    1986-01-01

    The federal Radiological Emergency Response Plan (FRERP) was developed to provide the framework for coordinating federal radiological assistance to states and to local authorities faced with a large radiological accident. The Relocation Tabletop Exercise was conducted on December 9-11, 1985 at the Beaver Valley Power Station, the site of the simulated accident. The exercise scenario had postulated a substantial release of radioactive materials from a fuel handling accident at the Beaver Valley Power Station in Shippingport, Pennsylvania, leaving radioactive materisls deposited over part of the surrounding area. The exercise was structured as a sequential series of nice mini-scenarios, each of which focused on one problems. The exercise was intended to identify issues and problems which needed consideration or procedures which might need to be developed for this post-accident phase. It was a ''no-fault'' excercise

  7. Individual monitoring and dosimetry: The Goiania experience

    International Nuclear Information System (INIS)

    Lipsztein, J.L.; Melo, D.R.; Oliveira, C.A.N.; Bertelli, L.

    2000-01-01

    Several people were contaminated with 137 Cs in an accident involving the stealing and breaching of a radiotherapy source in Goiania, Brazil. A drug known as Prussian Blue was administered to some contaminated individuals to enhance Cs elimination from the body. Individuals internally contaminated were monitored for the two first months, exclusively by in vitro bioassay, i.e., urine and faeces analysis. After that period of time a field whole-body counter was set up in Goiania and individuals started to be monitored in vivo, on a regular basis. The total internal committed doses and the effect of Prussian blue treatment have been evaluated. For adults, the biological half-time (T 2 ) under PB treatment was reduced to an average value around to 31% of the half-time after finished treatment. For adolescents (T 2 ) was reduced to an average value around to 54% and for children was reduced to an average value around to 57%. A weight dependent biokinetic study of 137 Cs retention in humans was conducted. Data from 10 girls and 7 boys, aged 1 to 10 y old, as well as from 10 adolescents: 4 females and 6 males, and from 30 adults: 15 females and 15 males, contaminated in the accident, were used in this study. A planned experiment with beagle dogs were carried out to furnish some further data for our study. Based on these data, a three terms exponential equation is suggested to describe the 137 Cs retention in the body, the first-term associated with a very short half-time, the second with a longer half-time and the third term with a very long half-time, of the order of 400 to 570 days and relating to a retention fraction of only 0.1%. A table of weight, age and sex specific half-times for the second term is suggested. (author)

  8. RASCAL [Radiological Assessment System for Consequence AnaLysis]: A screening model for estimating doses from radiological accidents

    International Nuclear Information System (INIS)

    Sjoreen, A.L.; Athey, G.F.; Sakenas, C.A.; McKenna, T.J.

    1988-01-01

    The Radiological Assessment System for Consequence AnaLysis (RASCAL) is a new MS-DOS-based dose assessment model which has been written for the US Nuclear Regulatory Commission for use during response to radiological emergencies. RASCAL is designed to provide crude estimates of the effects of an accident while the accident is in progress and only limited information is available. It has been designed to be very simple to use and to run quickly. RASCAL is unique in that it estimates the source term based on fundamental plant conditions and does not rely solely on release rate estimation (e.g., Ci/sec of I-131). Therefore, it can estimate consequences of accidents involving unmonitored pathways or projected failures. RASCAL will replace the older model, IRDAM. 6 refs

  9. Radiological accident reconstruction with numerical tools: towards a more realistic representation of the victim

    International Nuclear Information System (INIS)

    Courageot, E.; Sayah, R.; Huet, Ch.

    2010-01-01

    The authors describe the evolutions brought to the SESAME (Simulation of External Source Accident with Medical images) simulation code. This code aims at making a computational dosimetric reconstruction of a radiological accident by modelling the victim by means of a voxelized phantom, as well as the accident source and environment. This new version creates a voxelized phantom of a victim whose position and morphology have been modified, thus enabling the position of victim at the moment of the accident to be taken into account. The authors report the computational and experimental validation of this new functionality, and discuss the results. They compare computed and measured doses

  10. Lifespan of human lymphocytes estimated during a six year cytogenetic follow-up of individuals accidentally exposed in the 1987 radiological accident in Brazil

    International Nuclear Information System (INIS)

    Ramalho, Adriana T.; Curado, M.P.; Natarajan, A.T.

    1995-01-01

    Following the radiological accident which occurred in the city of Goiania (Brazil), in September 1987, a cytogenetic follow-up of 15 exposed patients was started, aiming to observe the mean lifetime of lymphocytes containing dicentric and ring aberrations. The results suggest that the disappearance rate of unstable aberrations follows a two-term exponential function. Up to 470 days after exposure, there is a rapid fall in the aberration frequency. After 470 days, the disappearance rate is very slow. These results may reflect different subpopulations of human lymphocytes, with different lifespans. The estimated average half-time of elimination of dicentrics and rings among the highly exposed group (doses above 1 Gy) was 110 days for the initial period after the exposure (up to 470 days). This value is significantly shorter than the usually accepted value of 3 years reported in the literature. Statistical analysis of possible correlations between the individual half-times and biological parameters, such as sex, age, leukopenia level shown during the critical period, absorbed dose (initial frequency of chromosomal aberrations) and the administration of the bone marrow stimulating factor (rHuGM-CSF) was performed. None of these parameters showed a correlation with the half-time of disappearance of chromosomal aberrations. For the individuals who had received less than 1 Gy the disappearance of aberrations was slower, with a half-time of 160 days during the period up to 470 days after exposure. Mean disappearance functions of unstable chromosome aberrations were inferred, to be applied in accident situations in which there is a blood sampling delay

  11. Introduction of new terms and lessons for radiological protection after Fukushima Dai-Ichi accident

    International Nuclear Information System (INIS)

    Singh, Vishwanath P.; Managanvi, S.S.; Bhat, H.R.

    2012-01-01

    The nuclear accidents in the world are very few among various types of operating facilities. However when an accident happened, we have learnt a lot to improve the philosophy, term, definitions, document preparation, equipment's requirement, supporting systems, awareness program and restriction etc. After Fukushima Dai-ichi we have learnt a lot, in this view this paper has been prepared to discuss for radiological protection aspects. Discussion: The probability of nuclear accidents is negligible but when happens, it opens new doors of lessons for radiological protection practices for occupational workers, emergency workers for damage control to prevent catastrophic situation/rescue to life saving actions and the member of the public. The Chernobyl and Three Mile Island accidents have provided a lot experiences for management of emergency situations, documentation, radiation emergency preparedness, emergency equipment's, concept of defense-in-depth, emergency planning zone (EPZ), accidental dose limits, estimation of source term and public dose, intervention levels, decision supporting system, remedial actions in public domain; decontamination of person, houses/building and land and etc. Recent Fukushima Dai-ichi accident in Japan was managed in appreciable manner but still new definitions and lessons for radiological protection have been emerged out. The present paper discusses difficulties w. r. t. the radiological aspects observed/faced by Japanese during nuclear crises. The accident introduced new terms as Natural Dose Rate Unit (NDRU), voluntary evacuation, deliberate evacuation area, restricted area and difference between evacuation zone and EPZ. The Fukushima accident has enforced worldwide regulators and operators to review the individual dose limit and amendment for raise in the dose limit during accident, availability of efficient/adequate quantities of personal dosimeter in public domain, collection arrangement of bulk amount of radioactive wastes

  12. Remotely Piloted Aircraft Systems and a Wireless Sensors Network for Radiological Accidents

    Directory of Open Access Journals (Sweden)

    A. Reyes-Muñoz

    2016-01-01

    Full Text Available In critical radiological situations, the real time information that we could get from the disaster area becomes of great importance. However, communication systems could be affected after a radiological accident. The proposed network in this research consists of distributed sensors in charge of collecting radiological data and ground vehicles that are sent to the nuclear plant at the moment of the accident to sense environmental and radiological information. Afterwards, data would be analyzed in the control center. Collected data by sensors and ground vehicles would be delivered to a control center using Remotely Piloted Aircraft Systems (RPAS as a message carrier. We analyze the pairwise contacts, as well as visiting times, data collection, capacity of the links, size of the transmission window of the sensors, and so forth. All this calculus was made analytically and compared via network simulations.

  13. Radiological accidents/incidents with caesium-137 in Estonia

    International Nuclear Information System (INIS)

    Sinisoo, M.

    1998-01-01

    A report is provided of an accident and an incident involving radioactive sources in Estonia. In the 1994 occurrence, looters of a depository of radioactive waste manipulated a source containing 137 Cs and received dangerous doses of radiation. One of the persons involved died, others suffered minor burns. Another event, which occurred in early 1995, did not have a tragic outcome: an abandoned 137 Cs source was found in the vicinity of the highway linking Tallinn and Narva and was disposed of safely. Both these accidents draw attention to the potential dangers caused by the insufficient survey of the territory, radiation protection structures not yet fully operable, and the lack of equipment and know-how. The lessons to be drawn from these events are considered on the basis of the chronologies and factual data. The report contains concise descriptions of the accidents, a medical overview of the fate of the injured persons and the lessons learned from these accidents. (author)

  14. Semi-portable whole body counter deployable during post-radiological accident

    International Nuclear Information System (INIS)

    Panchal, C.G.; Bansode, P.Y.; Vinod, M.; Sarade, Bhagyashree; Jain, R.K.; Jakati, R.K.; Pithawa, C.K.

    2012-01-01

    A versatile whole body counter with the state of art electronics has been indigenously designed and developed which can be readily deployed for use during nuclear emergency. This instrument is designed to quickly identify and quantify the activity of high energy photon emitters accumulated particularly in vital organs like thyroid, lungs besides the body of the victims of the radiological incident or accident. Special features of the instruments are swivel type detectors assembly mountable on a wall or table top and detachable collimator configurable to assess the internal contamination selectively to meet protective measures of the radiological accidents, mechanically rugged and functionally reliable to perform in contaminated environmental field conditions. (author)

  15. Guidelines for attendance and registration for radiological emergencies of nuclear accidents

    International Nuclear Information System (INIS)

    1994-01-01

    Today in Brazil the use of nuclear energy is becoming an usual practice in various activities. Thus, must be a matter of great weight, directions for attendance and registration for radiological emergencies or nuclear accidents. This work shows the planning elaborated by the Comissao Nacional de Energia Nuclear (Brazilian CNEN) for nuclear plants, aiming avoid the injurious effects from the ionizing radiation exposure, radionuclides release or the direct or indirect exposure of ionizing radiation, that proceeding from a radiological emergencies or a nuclear accidents. (J.A.M.M.)

  16. History of aerial surveys in response to radiological incidents and accidents

    International Nuclear Information System (INIS)

    Jobst, J.E.

    1986-01-01

    EG and G Energy Measurements Inc., operates the Remote Sensing Laboratory for the US Department of Energy (DOE). The Laboratory plays a key role in the federal response to a radiological incident or accident. It assists the DOE in the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC). The Remote Sensing Laboratory has played a major role in more than 13 incidents, including lost sources, accidental dispersions, and nuclear reactor incidents

  17. OFFSITE RADIOLOGICAL CONSEQUENCE CALCULATION FOR THE BOUNDING MIXING OF INCOMPATIBLE MATERIALS ACCIDENT

    International Nuclear Information System (INIS)

    SANDGREN, K.R.

    2006-01-01

    This document quantifies the offsite radiological consequence of the bounding mixing of incompatible materials accident for comparison with the 25 rem Evaluation Guideline established in Appendix A of DOE-STD-3009. The bounding accident is an inadvertent addition of acid to a waste tank. The calculated offsite dose does not challenge the Evaluation Guideline. Revision 4 updates the analysis to consider bulk chemical additions to single shell tanks (SSTs)

  18. Analysis of radioactive contaminations and radiological hazard in Poland after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Zarnowiecki, K.

    1988-01-01

    It is a report on radiological impact in Poland following the Chernobyl reactor accident prepared in the Central Laboratory for Radiological Protection. The results of measurement and its analysis are presented. Isotopic composition of the contamined air and the concentration of radionuclides are determined. The trajectories of the airborne radioactive material movement from Chernobyl to Poland at the last days of April 1986 are presented. Assessment of the radiological risk of the population is done. 38 refs., 20 figs., 11 tabs. (M.F.W.)

  19. Assessment of ionizing radiation as a risk factor for breast cancer incidence in Goiania; Avaliacao da radiacao ionizante como fator de risco para a incidencia de cancer de mama em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Lage, Leonardo Bastos

    2016-11-01

    annual averages of crude rates of incidence. The spatial correlation of groups (clusters) of new cases has been verified, through the Moran index, and from geographically referenced radiometric measurements obtained in the previous step, the correlation between the incidence of breast cancer and ionizing radiation levels was assessed by unconditional linear regression. The results were presented in two papers. In the first, radiometric surveys were conducted in 1.405 of the 1.636 (85,9%) census tracts sectors that make up the seven Sanitary Districts in the city of Goiania. In total 197.811 geographically referenced measures of the absorbed dose rate in the air were made, with a average of 29,85 ± 7,47 and amplitude from 9,17 to 629,88 nGy/h. From these values were estimated the average of annual effective dose and collective effective dose for outdoor environments, with values of 0,036 ± 0,003 mSv/year and 28,51 ± 11,68 man.mSv/year, respectively. The levels of exposure to external gamma radiation, found in the city of Goiania 28 years after the radiological accident with Cesium-137, are compatible with the values estimated by UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation). And the value of the annual average of effective dose in Goiania, is lower than in other places in Brazil, which have only 'background' of natural radiation outdoors. The results obtained in this study indicate that the dosimetric situation in Goiania does not present undue risk to people and the environment. In the second article, were identified 4.105 new cases of breast cancer, 2.233 in the study area and 1.286 (57,59%) of these geographically referenced. The annual average values of crude rates of incidence, considering the total numbers of cases and geographically referenced presented in the study area are, respectively, 102,91 and 71,86 new cases per 100.000 women. The crude rate of incidence in Goiania was 66,59 cases per 100.000, while in the

  20. Below Regulatory Conern Owners Group: Radiologic impact of accidents and unexpected events from disposal of BRC waste

    International Nuclear Information System (INIS)

    Waite, D.A.; Dolan, M.M.; Rish, W.R.; Rossi, A.J.; McCourt, J.E.

    1989-07-01

    This report determines the radiological impact of accidents and unexpected events in the disposal of Below Regulatory Concern (BRC) waste. The accident analysis considers the transportation, incineration, and disposal of BRC waste as municipal solid waste. The potential greatest radiological impact for each type of accident is identified through the use of event trees. These accident events are described in terms of the generic waste property(ies) (e.g., flammability, dispersibility, leachability, and solubility) that cause the greatest radiological impact. 7 refs., 32 figs., 12 tabs

  1. Six years of cytogenetic follow-up of unstable chromosome aberrations in Goiania patients

    International Nuclear Information System (INIS)

    Ramalho, A.T.; Curado, M.P.; Natarajan, A.T.; Cohen, J.A.

    2000-01-01

    Following the radiological accident which occurred in the city of Goiania (Brazil), in September of 1987, a cytogenetic follow-up of 16 exposed patients was started, aiming to observe the mean life time of lymphocytes containing dicentric and ring aberrations. The results suggest that for the highly exposed individuals (doses above 1 Gy) the disappearance rate of unstable aberrations follows a two-term exponential function. Up to 470 days after exposure, there is a rapid fall in the aberration frequency. After 470 days, the disappearance rate is very slow. These results may reflect different subpopulations of human lymphocytes, with different life spans. The estimated average half-time of elimination of dicentrics and rings among the highly exposed group (doses above 1 Gy) was 140 days for the initial period after the exposure (up to 470 days). This value is significantly shorter than the usually accepted value of 3 years reported in the literature. For the individuals who had received less than 1 Gy the disappearance of aberrations seems to have occurred in a slower way. Mean disappearance functions of unstable chromosome aberrations were inferred, to be applied in accident situations in which there is a blood sampling delay. (author)

  2. Victims of Chernobyl and Goiania with the same symptoms of Aids

    International Nuclear Information System (INIS)

    Terra, P.; Ladislau, W.

    1991-01-01

    Some consequences of the Goiania nuclear accident are discussed, including the serious injuries and the lack of resources towards the victims and the construction of a final repository. The study of the pollucite in natura, that can cause diseases due to natural radiation is also mentioned. 6 figs

  3. Radiological accidents: methodologies of radio nuclides dis incorporation

    International Nuclear Information System (INIS)

    Jimenez F, E. A.; Paredes G, L.; Cortes, A.

    2014-08-01

    Derived of the radioactive or nuclear material management, exists the risk that accidents can happen where people cases are presented with internal radioactive contamination, who will receive specialized medical care to accelerate the radioactive dis incorporation with the purpose of diminishing the absorbed dose and the associate biological effects. In this work treatments of radioactive dis incorporation were identified, in function of the radionuclide, radiation type, radioactive half life, biological half life, critical organ, ingestion duct and patient type. The factor time is decisive for the effectiveness of the selected treatment in the blockade stage (before the accident) or dis incorporation (after the accident); this factor is related with the radioactive and biological half lives. So to achieve dis incorporation efficiencies of more to 70%, the patient clinical treatment will begin before the first third of the biological half life of the radionuclide that generated the internal contamination. (Author)

  4. National radiological emergency response to the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Dela Rosa, Alumanda M.

    2011-01-01

    The Fukushima nuclear power plant accident occurred on March 11, 2011, when two natural disasters of unprecedented strengths, an earthquake with magnitude 9 followed one hour later by a powerful tsunami struck northeastern Japan and felled the external power supply and the emergency diesel generators of the Fukushima Daiichi nuclear power station, resulting in a loss of coolant accident. There were core meltdowns in three nuclear reactors with the release of radioactivity estimated to be 1/10 of what was released to the environment during the Chernobyl nuclear power plant accident in April 1986. The Fukushima nuclear accident tested the capability of the Philippine Nuclear Research Institute (PNRI) and the National Disaster Risk Reduction and Management Council (NDRRMC) in responding to such radiological emergency as a nuclear power plant accident. The PNRI and NDRRMC activated the RADPLAN for possible radiological emergency. The emergency response was calibrated to the status of the nuclear reactors on site and the environmental monitoring undertaken around the site and off-site, including the marine environment. This orchestrated effort enabled the PNRI and the national agencies concerned to reassure the public that the nuclear accident does not have a significant impact on the Philippines, both on the health and safety of the people and on the safety of the environment. National actions taken during the accident will be presented. The role played by the International Atomic Energy Agency as the central UN agency for nuclear matters will be discussed. (author)

  5. Dose assessment for decontamination in Goiania

    International Nuclear Information System (INIS)

    Amaral, E.C.S.

    2000-01-01

    Shortly after the accident at Goiania, the need arose to set derived intervention levels for the various exposure pathways to guide and optimise clean up measures. For the members of the critical group an intervention level of 5 mSv for the total effective dose in the first year after the accident was chosen, which then was subdivided into values of 1 mSv due to the contribution of external irradiation indoors, 3 mSv from external irradiation while being outdoors, and 1 mSv due to incorporation of resuspended particles and ingestion of locally produced food. The clean up indoors could be directed such that a pre-described ambient dose rate was no longer exceeded. These exposure levels and effective doses to the critical groups predicted in 1988 are compared to actual measurements made in 1988 to 1993 in a local house near one primary contamination foci, and best estimate. It can be shown that the actual doses received by members of the public living in the affected areas were significantly lower. The various reasons for this overprediction will be discussed. (author)

  6. Nursering assistance to the radiological accident patients in Goias-Brazil

    International Nuclear Information System (INIS)

    Graciotti, M.E.

    1989-01-01

    A report of a personal experience, during two months of nursering care to the radiological accident victims, due to the disruption of a caesium-137 source, is presented. The biological radiation effects, the radiation hazards due to the doses received and the Kind of exposure, are studied. (M.A.C.) [pt

  7. Medical response for radiological accidents from Regional cooperation : Latin-American radiopathology networks

    International Nuclear Information System (INIS)

    Valverde, Nelson; Cardenas, Juan; Perez, Maria del Rosario; Trano, Jose Luiz Di; Gisone, Pablo

    2001-01-01

    The objective of this program is to have a system, in order to assure an appropriate medical response in the case of radiological accidents and to offer medical advice in aspects related to the biological effects of ionizing radiations in risk assessment of radiation workers, medical exposures, potential effects of prenatal irradiation

  8. Guidelines for mutual emergency assistance arrangements in connection with a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1984-01-01

    The document contains the recommendations of a group of experts from 22 Member States and three international organizations which met in April 1983. These recommendations may serve as guidelines for use by states for the negotiation of bilateral or regional agreements relating to emergency assistance in the event of a nuclear accident or radiological emergency

  9. Intervention of the army health service in the case of radiological accident in peace time

    International Nuclear Information System (INIS)

    Curet, P.M.; Croq, M.

    2001-01-01

    The Army Health Service has conceived an organisation and has at its disposal the means necessary to answer the consequences of an accident having a radiological type in peace time in the military field. Its intervention area can be extended to the civil medium at the public authorities demand to give assistance. (N.C.)

  10. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

    1986-01-01

    This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs

  11. Radiological health risks from accidents during transportation of spent nuclear fuels

    International Nuclear Information System (INIS)

    Chen, S.Y.; Yuan, Y.C.

    1988-01-01

    Potential radiological health risks from severe accident scenarios during the transportation of spent nuclear fuels are estimated. These extremely low probability, but potentially credible, scenarios are characterized by the U.S. Nuclear Regulatory Commission's Modal Study in terms of the maximum credible structural responses and/or the maximum credible cask temperature responses. In some accident scenarios, the spent nuclear fuel casks are assumed to be breached, resulting in the release of radioactivity to the atmosphere. Models have been developed to estimate radiological health consequences, including potential short-term exposures and health effects to individuals and potential long-term environmental dose commitments and health effects to the population. The population risks are calculated using state-level data, and the resulting overall health risks are compared for several levels of cleanup effort to determine the relative effects on long-term risks to the population in the event of an accident. 4 refs., 3 figs., 3 tabs

  12. International exchange of radiological information in the event of a nuclear accident - future perspectives

    International Nuclear Information System (INIS)

    De-Cort, M.; De-Vries, G.; Breitenbach, L.; Leeb, H.; Weiss, W.

    1996-01-01

    Immediately after the Chernobyl accident most European countries established or enhanced their national radioactivity monitoring and information systems. The large transboundary effect of the radioactive release also triggered the need for bilateral and international agreements on the exchange of radiological information in case of a nuclear accident. Based on the experiences gained from existing bi- and multilateral data exchange the Commission of the European Communities has made provision for and is developing technical systems to exchange information of common interest. Firstly the existing national systems and systems based on bilateral agreements are summarized. The objectives and technical realizations of the EC international information exchange systems ECURIE and EURDEP, are described. The experiences gained over the past few years and the concepts for the future, in which central and eastern European countries will be included, are discussed. The benefits that would result from improving the international exchange of radiological information in the event of a future nuclear accident are further being described

  13. Determination of the cesium distribution coeficient in Goiania and Abadia de Goias cities soils

    International Nuclear Information System (INIS)

    Marumo, J.T.; Suarez, A.A.

    1989-01-01

    In September, 1987, an unauthorized removal of a cesium-therapy unit and its violation caused an accident, where several places of Goiania's city, capital of Goias, Brazil, were contaminated. The removal of the radioactive wastes generated from decontamination process, was made to Abadia de Goias's city (near Goiania), where an interim storage was constructed. Soil samples collected from the 57 th Street (Goiania) and from the interim storage permitted to determine, through static method, the cesium distribution coefficient for different cesium solution concentrations. Those results allows for some migration/retention evaluations in disposal site selection. Some soils parameters (water content, density, granulometric analysis etc) as well as clay minerals constituents were also determined. (author) [pt

  14. Determination of the cesium distribution coefficient in Goiania and Abadia de Goias cities soils

    International Nuclear Information System (INIS)

    Marumo, J.T.; Suarez, A.A.

    1989-10-01

    In September, 1987, an unauthorized removal of a cesium-therapy unit and its violation caused an accident, where several places of Goiania's city, capital of Goias, Brazil, were contaminated. The removal of the radioactive wastes generated from decontamination process, was made to Abadia de Goias city (near Goiania), where an interim storage was constructed. Soil samples collected from the 57 th Street (Goiania) and from the interim storage permitted to determine, through static method, the cesium distribution coefficent for different cesium solution concentrations. Those results allows for some migration/retention evaluations in disposal site selection. Some soils parameters (water content, density, granulometric analysis etc) as well as clay minerals constituents were also determined. (author) [pt

  15. Environmental radiological consequences of a loss of coolant accident

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.

    1981-01-01

    The elaboration of a calculation model to determine safety areas, named Exclusion Zone and Low Population Zone for nuclear power plants, is dealt with. These areas are determined from a radioactive doses calculation for the population living around the NPP after occurence of a postulated ' Maximum Credible Accident' (MCA). The MCA is defined as an accident with complete loss of primary coolant and consequent fusion of a substantial portion of the reactor core. In the calculations carried out, data from NPP Angra I were used and the assumptions made were conservative, to be compatible with licensing requirements. Under the most pessimistic assumption (no filters) the values of 410m and 1000m were obtained for the Exclusion Zone and Low Population Zone radii, respectivily. (Author) [pt

  16. Medical features of the radiological accident in Chernobyl

    International Nuclear Information System (INIS)

    Oliveira, A.R. de

    1987-01-01

    The main medical features concerning the recent nuclear accident occurred in Chernobyl power station is summarized. The first measures taken by the Soviet medical authorities to minimize the effects of ionizing radiation on the victims are briefly commented on. The specialized laboratory analyses and therapeutic procedures adopted by the physicians during the course of the acute phase of the major syndromes are also discussed. (author) [pt

  17. Radiological protection issues arising during and after the Fukushima nuclear reactor accident

    International Nuclear Information System (INIS)

    González, Abel J; Akashi, Makoto; Sakai, Kazuo; Yonekura, Yoshiharu; Boice Jr, John D; Chino, Masamichi; Homma, Toshimitsu; Ishigure, Nobuhito; Kai, Michiaki; Kusumi, Shizuyo; Lee, Jai-Ki; Menzel, Hans-Georg; Niwa, Ohtsura; Yamashita, Shunichi; Weiss, Wolfgang

    2013-01-01

    Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP. While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with ‘contamination’ of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information. Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled. It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of

  18. Radiological protection issues arising during and after the Fukushima nuclear reactor accident.

    Science.gov (United States)

    González, Abel J; Akashi, Makoto; Boice, John D; Chino, Masamichi; Homma, Toshimitsu; Ishigure, Nobuhito; Kai, Michiaki; Kusumi, Shizuyo; Lee, Jai-Ki; Menzel, Hans-Georg; Niwa, Ohtsura; Sakai, Kazuo; Weiss, Wolfgang; Yamashita, Shunichi; Yonekura, Yoshiharu

    2013-09-01

    Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP. While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with 'contamination' of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information. Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled. It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of potential

  19. Recovery operations in the event of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1990-01-01

    Much progress has been made over the last decade in the field of emergency planning and preparedness, including the development of guidance, criteria, training programmes, regulations and comprehensive plans in the support of nuclear facilities. To provide a forum for international review and discussion of actual experiences gained and lessons learned from the different aspects of recovery techniques and operations in response to serious accidents at nuclear facilities and accidents associated with radioactive materials, the IAEA organized the International Symposium on Recovery Operations in the Event of a Nuclear Accident or Radiological Emergency. The symposium was held from 6 to 10 November 1989 in Vienna, Austria, and was attended by over 250 experts from 35 Member State and 7 international organizations. Although the prime focus was on on-site and off-site recovery from nuclear reactor accidents and on recovery from radiological accidents unrelated to nuclear power plants, development of emergency planning and preparedness resources was covered as well. From the experiences reported, lessons learned were identified. While further work remains to be done to improve concepts, plans, materials, communications and mechanisms to assemble quickly all the special resources needed in the event of an accident, there was general agreement that worldwide preparations to handle any possible future radiological emergencies had vastly improved. A special feature of the symposium programme was the inclusion of a full session on an accident involving a chemical explosion in a high level waste tank a a plutonium extraction plant in the Southern Urals in the USSR in 1957. Information was presented on the radioactive release, its dissemination and deposition, the resultant radiation situation, dose estimates, health effects follow-up, and the rehabilitation of contaminated land. This volume contains the full text of the 49 papers presented at the symposium together with a

  20. Radiological effects of the Chernobyl accident on West Germany

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    According to a preliminary estimate of the additional radiation exposure of West Germany's population due to the Chernobyl reactor accident, an effective dose of 150-200 mrem over the next 50 years is given as an average commitment throughout the country (accumulated natural radiation dose estimated for the same period of time is between 7 500 and 20 000 mrem). There are, however, strong regional variations. The Strahlenschutzkommission gives the calculated maximum dose to the adult population via the food chain to be 70 mrem in 1986, and 90 mrem to infants; the commission expects that real values will be about one fifth of the assessed values.

  1. Decision-Making Risks Concerning the Construction of the Goiania Waste Repository

    International Nuclear Information System (INIS)

    Paschoa, A.S.; Rozental, J.J.; Tranjan Filho, A.

    2001-01-01

    As it is well known, an accident with a teletherapy source made of 137 CsCl with an initial activity of 59 TBq occurred in Goiania, in September of 1987. This paper will discuss the decision-making process, and the struggle that followed the decision to build the final repository for the remnants of the Goiania accident. The Goiania final repository was built as planned. The two subsurface structures under the grassy artificial hills hold the overall volume of the remnants of the Goiania accident. The near hill holds 5x10 3 m3 of stabilized wastes without radioactivity, or with very low radioactivity. The far hill holds the remaining 6.5x10 3 m 3 of stabilized wastes with low and medium radioactivity. The central part of each subsurface hill has been shielded by wastes with less and less radioactivity. The overall fenced area occupies 1.85x10 5 m 2 . The external radiation levels are similar to the surrounding background, and much lower than those found in the Brazilian areas of high natural radioactivity. The site is permanently monitored by independent institutions, including Brazilian universities, and national and international organizations. As it was mentioned earlier, the final repository was build to last for at least 400 years. Although the initial decision to adopt a too conservative decontamination criterion in the case of the Goiania accident was bound to produce excessive amount of waste; such decision proved, retrospectively, not to be bad because the excess low radioactive waste produced was used as extra shielding material in final repository. The technical decision-maker should not abandon risk estimates, but should be aware that credibility is the main basis to achieve acceptability of a decision by the general public. Risk perception should be regarded as only a first step towards what may be called knowledge, or comprehension of risk estimates, but risk perception by the general public is still an open issue. The problem of a fixed, or near

  2. Decision-Making Risks Concerning the Construction of the Goiania Waste Repository

    Energy Technology Data Exchange (ETDEWEB)

    Paschoa, A.S. [Pontificia Univ. Catolica, Rio de Janeiro (Brazil); Rozental, J.J. [Ministry of Environment (Israel); Tranjan Filho, A. [Comissao Nacional de Energia Nuclear (CNEN) (Brazil)

    2001-07-01

    As it is well known, an accident with a teletherapy source made of {sup 137}CsCl with an initial activity of 59 TBq occurred in Goiania, in September of 1987. This paper will discuss the decision-making process, and the struggle that followed the decision to build the final repository for the remnants of the Goiania accident. The Goiania final repository was built as planned. The two subsurface structures under the grassy artificial hills hold the overall volume of the remnants of the Goiania accident. The near hill holds 5x10{sup 3} m3 of stabilized wastes without radioactivity, or with very low radioactivity. The far hill holds the remaining 6.5x10{sup 3} m{sup 3} of stabilized wastes with low and medium radioactivity. The central part of each subsurface hill has been shielded by wastes with less and less radioactivity. The overall fenced area occupies 1.85x10{sup 5} m{sup 2}. The external radiation levels are similar to the surrounding background, and much lower than those found in the Brazilian areas of high natural radioactivity. The site is permanently monitored by independent institutions, including Brazilian universities, and national and international organizations. As it was mentioned earlier, the final repository was build to last for at least 400 years. Although the initial decision to adopt a too conservative decontamination criterion in the case of the Goiania accident was bound to produce excessive amount of waste; such decision proved, retrospectively, not to be bad because the excess low radioactive waste produced was used as extra shielding material in final repository. The technical decision-maker should not abandon risk estimates, but should be aware that credibility is the main basis to achieve acceptability of a decision by the general public. Risk perception should be regarded as only a first step towards what may be called knowledge, or comprehension of risk estimates, but risk perception by the general public is still an open issue. The

  3. Offsite radiological consequence analysis for the bounding aircraft crash accident

    International Nuclear Information System (INIS)

    OBERG, B.D.

    2003-01-01

    The purpose of this calculation note is to quantitatively analyze a bounding aircraft crash accident for comparison to the DOE-STD-3009-94, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', Appendix A, Evaluation Guideline of 25 rem. The potential of aircraft impacting a facility was evaluated using the approach given in DOE-STD-3014-96, ''Accident Analysis for Aircraft Crash into Hazardous Facilities''. The following aircraft crash FR-equencies were determined for the Tank Farms in RPP-11736, ''Assessment Of Aircraft Crash FR-equency For The Hanford Site 200 Area Tank Farms'': (1) The total aircraft crash FR-equency is ''extremely unlikely.'' (2) The general aviation crash FR-equency is ''extremely unlikely.'' (3) The helicopter crash FR-equency is ''beyond extremely unlikely.'' (4) For the Hanford Site 200 Areas, other aircraft type, commercial or military, each above ground facility, and any other type of underground facility is ''beyond extremely unlikely.'' As the potential of aircraft crash into the 200 Area tank farms is more FR-equent than ''beyond extremely unlikely,'' consequence analysis of the aircraft crash is required

  4. Transporting radioactive materials and possible radiological consequences from accidents as might be seen by medical institutions

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1990-01-01

    This paper discusses how medical personnel faced with treating victims of an accident involving radioactive material should be suspicious concerning possible radiological involvement. At the same time, they should be careful to obtain the necessary information in order to make a rational decision as to the likelihood of such involvement. Having made that decision, it is entirely possible then to approach the problem from a medical standpoint in such a way as to determine the extent of radiological involvement and to apply proper medical treatment consistent with that exposure

  5. Management of a radiological emergency. Experience feedback and post-accident management

    International Nuclear Information System (INIS)

    Dubiau, Ph.

    2007-01-01

    In France, the organization of crisis situations and the management of radiological emergency situations are regularly tested through simulation exercises for a continuous improvement. Past severe accidents represent experience feedback resources of prime importance which have led to deep changes in crisis organizations. However, the management of the post-accident phase is still the object of considerations and reflections between the public authorities and the intervening parties. This document presents, first, the nuclear crisis exercises organized in France, then, the experience feedback of past accidents and exercises, and finally, the main aspects to consider for the post-accident management of such events: 1 - Crisis exercises: objectives, types (local, national and international exercises), principles and progress, limits; 2 - Experience feedback: real crises (major accidents, other recent accidental situations or incidents), crisis exercises (experience feedback organization, improvements); 3 - post-accident management: environmental contamination and people exposure, management of contaminated territories, management of populations (additional protection, living conditions, medical-psychological follow up), indemnification, organization during the post-accident phase; 4 - conclusion and perspectives. (J.S.)

  6. Radiological effects of Chernobyl reactor accident on the lakes of Southern Bavaria

    International Nuclear Information System (INIS)

    Laschka, D.; Hermann, H.; Huebel, K.; Luensmann, W.

    1988-03-01

    In order to detect the radiological effects of the Chernobyl reactor accident to the large lakes of Southern Bavaria and to assess the radiation exposure of man on the different aquatic pathways, the radioactive contamination of the surface water, the sediments and the fishes was investigated. The dependence of time of the activity concentrations in the tested medias is shown and an outlook is made on the expected further evolution. The radiation exposure of man by swimming, boating and fish consumption in the fast year after the reactor accident is calculated [fr

  7. Radiation protection program for assistance of victims of radiation accidents

    International Nuclear Information System (INIS)

    Fajardo, P.W.; Costa Silva, L.H. da; Rosa, R.

    1991-11-01

    The principles aspects of a radiological protection program for hospitals in case of medical assistance to external and internal contaminated persons are showed. It is based on the experience obtained at Centro Medico Naval Marcilio Dias during the assistance to the victims of Goiania accident in 1987. This paper describes the basic infrastructure of a nursery and the radiation protection procedures for the access control of people and materials, area and personal monitoring, decontamination and the support activities such as calibration of radiation monitors and waste management. Is is also estimated the necessary radiation protection materials and the daily quantity of waste generated. (author)

  8. Radiological impact to the population of the three major accidents happened in the civil nuclear industry

    International Nuclear Information System (INIS)

    Ortiz M, J. R.

    2013-10-01

    The greatest fear of the population before a nuclear accident, is the radiological impact to the health of people, due to the exposure to the liberated radioactive material during the accident, this fear is generally exaggerated or not well managed by the media. The best estimate in the received doses and their possible effects is carried out based on the information obtained during a certain time after the accident event. This work contains a summary of the information in the topic that at the present time has presented institutions as: the World Health Organization (Who), the United Nations Scientific Committee on Effects of Atomic Radiation (UNSCEAR), the Nuclear Regulatory Commission (NRC) and the World Nuclear Association, among others. The considered accidents are: first, the Unit-2 of the nuclear power plant of the Three Mile Island in Pennsylvania, USA occurred 28 March of 1979, in the Reactor TMI-2, type PWR of 900 M We; the second accident was 26 April of 1986, in the Unit-4 of the nuclear power plant of Chernobyl, in Ukraine, the involved reactor was type BRMK, of 1000 M We moderated by graphite and cooled with light water, the power plant is located to 100 Km to the northwest of Kiev; 25 years later occurred the third accident in the nuclear power plant of Fukushima Dai-ichi, in Japan, affecting at four of the six reactors of the power plant. A brief description of the accident is presented in each case, including the magnitude of the provoked liberations of radioactive material, the estimate doses of the population and the affected workers are presented, as well as the possible consequences of these doses on the health. The objective of this diffusion work is to give knowledge to the nuclear and radiological community of the available information on the topic, in order to be located in the appropriate professional context. (author)

  9. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities

    International Nuclear Information System (INIS)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J.; Laub, T.W.

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10 -11 /yr to 10 -5 /yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10 -9 /yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution

  10. CEC workshop on methods for assessing the offsite radiological consequences of nuclear accidents

    International Nuclear Information System (INIS)

    Luykx, F.; Sinnaeve, J.

    1986-01-01

    On Apr 15-19, 1985, in Luxembourg, the Commission of the European Communities (CEC), in collaboration with the Kernforschungszentrum Karlsruhe (KfK), Federal Republic of Germany, and the National Radiological Protection Board (NRPB), United Kingdom, presented a workshop on methods for assessing the offsite radiological consequences of nuclear accidents. The program consisted of eight sessions. The main conclusions, which were presented in the Round Table Session by the individual Session Chairmen, are summarized. Session topics are as follows: Session I: international developments in the field of accident consequence assessment (ACA); Session II: atmospheric dispersion; Session III: food chain models; Session IV: urban contamination; Session V: demographic and land use data; Session VI: dosimetry, health effects, economic and counter measure models; Session VII: uncertainty analysis; and Session VIII: application of probabilistic consequence models as decision aids

  11. Nuclear accident/radiological emergency assistance plan. NAREAP - edition 2000. Emergency preparedness and response

    International Nuclear Information System (INIS)

    2000-01-01

    The purpose of the Nuclear Accident/Radiological Emergency Assistance Plan (NAREAP) is to describe the framework for systematic, integrated, co-ordinated, and effective preparedness and response for a nuclear accident or radiological emergency involving facilities or practices that may give rise to a threat to health, the environment or property. The purpose of the NAREAP is: to define the emergency response objectives of the Agency's staff in a nuclear accident or a radiological emergency; to assign responsibilities for performing the tasks and authorities for making the decisions that comprise the Agency staff's response to a nuclear accident or radiological emergency; to guide the Agency managers who must ensure that all necessary tasks are given the necessary support in discharging the Agency staff responsibilities and fulfilling its obligations in response to an emergency; to ensure that the development and maintenance of detailed and coherent response procedures are well founded; to act as a point of reference for individual Agency staff members on their responsibilities (as an individual or a team member) throughout a response; to identify interrelationships with other international intergovernmental Organizations; and to serve as a training aid to maintain readiness of personnel. The NAREAP refers to the arrangements of the International Atomic Energy Agency and of the United Nations Security and Safety Section at the Vienna International Centre (UNSSS-VIC) that may be necessary for the IAEA to respond to a nuclear accident or radiological emergency, as defined in the Early Notification and Assistance Conventions. It covers response arrangements for any situation that may have actual, potential or perceived radiological consequences and that could require a response from the IAEA, as well as the arrangements for developing, maintaining and exercising preparedness. The implementing procedures themselves are not included in the NAREAP, but they are required

  12. SESAME: a software tool for the numerical dosimetric reconstruction of radiological accidents involving external sources and its application to the accident in Chile in December 2005.

    Science.gov (United States)

    Huet, C; Lemosquet, A; Clairand, I; Rioual, J B; Franck, D; de Carlan, L; Aubineau-Lanièce, I; Bottollier-Depois, J F

    2009-01-01

    Estimating the dose distribution in a victim's body is a relevant indicator in assessing biological damage from exposure in the event of a radiological accident caused by an external source. This dose distribution can be assessed by physical dosimetric reconstruction methods. Physical dosimetric reconstruction can be achieved using experimental or numerical techniques. This article presents the laboratory-developed SESAME--Simulation of External Source Accident with MEdical images--tool specific to dosimetric reconstruction of radiological accidents through numerical simulations which combine voxel geometry and the radiation-material interaction MCNP(X) Monte Carlo computer code. The experimental validation of the tool using a photon field and its application to a radiological accident in Chile in December 2005 are also described.

  13. The radiological situation in south Bavaria after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Wirth, E; Leising, C [Institute for Radiation Hygiene, Federal Health Office, Neuherberg (Germany)

    1986-07-01

    After the reactor accident at Chernobyl a radioactive cloud reached Bavaria on April 30th 1986 inducing activities in the air of 52 Bq iodine 131/m{sup 3} and 10 Bq cesium 137/m{sup 3} (measured in Munich on April 30th between 10am and 2pm). Further on, significant amounts of ruthenium 103, tellurium 132, iodine 132, iodine 133 and cesium 134 were found. Especially in the southern region of Bavaria the majority of the radioactivity in the air was washed out by heavy thundershowers and deposited on the ground. The local deposition was closely linked with the local precipitation rate between April 30th and May 2nd. The deposition of cesium 137 in Bavaria varied from less than 6000 to more than 40000 Bq/m{sup 2}. This radioactive contamination of the environment adds a further radioactive exposure to man. The three major exposure pathways, direct radiation, inhalation, and ingestion, will be considered in this paper.

  14. Radiological impact of the Chernobyl accident in EEC countries

    International Nuclear Information System (INIS)

    Vavrousek, J.

    1988-01-01

    The results are presented of an evaluation of the impact of radioactive substances escaped during the Chernobyl accident, on the population in EEC countries. The results have been processed from data provided by all member countries and relate to the most dangerous radionuclides namely 131 I, 134 Cs and 137 Cs. The population was divided into three groups: one-year olds, 10 year olds and adults. Assessed were external whole-body irradiation by the radioactive cloud and material deposited on the body surface, and internal irradiation with regard to the human food chain. The irradiation of the thyroid was assessed separately. As for 131 I, the most endangered group were the infants with the exception of Italy where 10 year olds were the most affected group. Values calculated for the individual countries are given of the effective dose equivalent for the first year, the dose equivalent for the thyroide, the dose commitment in the first year, the collective effective dose equivalent and the collective dose equivalent for the thyroid gland. Measures taken to reduce the irradiation of the population (restrictions on distribution and consumption of milk, dairy products and leafy vegetables, feeding cattle with preserved feeds, etc.) reduced the collective dose equivalent by a mere 5% and the collective dose equivalent for the thyroid by 26%. (E.S.). 3 tabs

  15. Investigation of evaluation method for marine radiological impact during an accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In 2012, JNES investigated the evaluation method, long-term seawater and marine deposition for release and diffusion to the ocean at the accident, and marine impact assessment code, in Japan and overseas. Also, the foreign regulations for marine radiological impact (direct release to ocean from the facilities and fallout on marine, etc.) were investigated. Furthermore, the index (e.g., intervention level) at emergency control in USA and Europe were investigated. (author)

  16. Investigation of evaluation method for marine radiological impact during an accident

    International Nuclear Information System (INIS)

    2013-01-01

    In 2012, JNES investigated the evaluation method, long-term seawater and marine deposition for release and diffusion to the ocean at the accident, and marine impact assessment code, in Japan and overseas. Also, the foreign regulations for marine radiological impact (direct release to ocean from the facilities and fallout on marine, etc.) were investigated. Furthermore, the index (e.g., intervention level) at emergency control in USA and Europe were investigated. (author)

  17. An assessment of the radiological consequences of accidents in research reactors

    International Nuclear Information System (INIS)

    Ferreira, N.L.D.

    1992-01-01

    This work analyses the radiological consequences of accidents in two types of research reactors: a 5 MWt open pool reactor and a 50 MWt PWR reactor. Two siting cases have been considered: the reactor located near to a large population center and sited in a rural area. The influence of several factors such as source term, meteorological conditions and population distribution have been considered in the present analysis. (author)

  18. Convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1987-03-01

    The document presents the status of signatures and notifications of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency which entered into force on 26 February 1987, i.e. thirty days after the date (26 January 1987) on which the third State expressed its consent to be bound by the Convention. The list of signature, notification, acceptance, approval or accession by States or Organizations is given

  19. RADIOLOGICAL AND MEDICAL CONSEQUENCES OF THE CHERNOBYL ACCIDENT

    Directory of Open Access Journals (Sweden)

    V. G. Bebeshko

    2012-01-01

    Full Text Available From the position of a 25-years’ experience to overcome the health effects of Chernobyl the dynamics of the radiation environment, the first summarizing at the international level (1988, the results of completed research and practical monitoring are analyzed. Cohort of acute radiation syndrome (ARS survivors under medical observation at the S.I. "Research Center for Radiation Medicine of the National Academy of Medical Sciences of Ukraine" is the largest. Within the 25 years the functional state of the major organs and body systems, and metabolic homeostasis for this category of persons were studied, a comprehensive assessment of their health, mental and physical performance were given, and risk factors and peculiarities of stochastic and non-stochastic pathology courses were identified, as well as a system of rehabilitation patients after ARS was developed. ARS survivors are suffering from chronic diseases of internal organs and systems (from 5-7 to 10-12 diagnoses at the same time. A correlation between acute radiation effects and specific HLA phenotypes were revealed. The dynamics of the immune system recovery after irradiation was studied. The role and prognostic value of telomere length and programmed cell death of lymphocytes in the formation of the cellular effects of ionizing radiation were determined for the first time. Differences between spontaneous and radiation-induced acute myeloid leukemias were found. Dose-dependent neuropsychiatric, neurophysiological, neuropsychological and neuroimaging deviations were identified after irradiation at doses above 0.3 Sv. It was shown that the lymphocytes of Chernobyl clean-up workers with doses 350 – 690 mGy can induce "the bystander effect" in the non-irradiated cells even after 19 years after exposure. The rates of cancer incidence and mortality of victims, the lessons and key problems to be solved in the third decade after the Chernobyl accident are considered.

  20. The protection of on-site personnel in the event of a radiological accident

    International Nuclear Information System (INIS)

    Morrey, M.; Simister, D.N.

    2003-01-01

    The National Radiological Protection Board (NPRB) is responsible in the UK for advising Government and other responsible bodies on the principles for responding to radiological emergencies. NRPB has published appropriate advice on the off-site protection of the public and on the protection of workers involved in taking mitigating actions to reduce the exposure of others. This paper puts forward a suggested framework for the protection of on-site personnel in the event of a radiological emergency which might include a criticality accident. This framework both dovetails with existing planning for the protection of members of the public off-site, and also takes account of specific differences between the situations on and off-site. (author)

  1. Study on generic intervention levels for protecting the public in a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    Suzuki, Fabio Fumio

    2003-01-01

    After a nuclear accident or radiological emergency, several social and economical factors shall be considered for the actions to protect the public and to recover the environment. The application of the radiological protection principles on practices in intervention situations may lead to adoption of protective measures disproportional to the involved risk, compromising the resources available to more effective actions. This causes a negative impact on the population and may conduct to discredit about the protective measures and the lost of confidence on the authorities. In this context, the principles of radiological protection for interventions should be studied and analyzed for being adequately applied in accident situations or radiological emergencies that involves the country. These principles are constantly improved and the concept of generic intervention level plays an important role in the decision-making to protect the public. The costs involved to the protective measures for the public in Brazil were studied and cost benefit analysis techniques were applied to estimate the generic intervention levels for public protection applicable in the country. These results were compared to those values internationally recommended, as well to values obtained in a similar study accomplished for Japan. It was also performed a sensibility analysis of the results regarding a value and a simple analysis of the results considering the costs of the several protective measures. (author)

  2. Medical SisRadiologia: a new software tool for analysis of radiological accidents and incidents in medical radiology

    International Nuclear Information System (INIS)

    Lima, Camila M. Araujo; Silva, Francisco C.A. da; Araujo, Rilton A.; Pelegrineli, Samuel Q.

    2013-01-01

    The man's exposure to ionizing radiation in health are has increased considerably due not only the great request of medical examinations as well as the improvement of the techniques used in diagnostic imaging, for example, equipment for conventional X-rays, CT scans, mammography, hemodynamic and others. Although the benefits of using of radiology techniques are unquestionable, the lack of training in radiation protection of the workers, associated with procedure errors, have been responsible for the increasing number of radiation overexposures of these workers. Sometimes these high doses are real and there is a true radiological accident. The radiation workers, named occupationally Exposed Individual (IOE), must comply with two national regulations: Governmental Decree 453/1998 of the National Agency of Sanitary Surveillance (Portaria 453/1998 ANVISA Agencia Nacional de Vigilancia Sanitaria), which establishes the basic guidelines for radiation protection in medial and dental radiology and; the Governmental Decree NR-32/2002 of the Ministry of Labour and Employment (Ministerio do Trabalho e Emprego), which establishes the basic guidelines for the worker's health. The two mandatory regulations postulate a detailed investigation in the event of radiation overexposure of an IOE. In order to advice the diagnostic institution to perform an efficient analysis, investigation and report of high doses, it is proposed the use of a computational tool named 'Medical SisRadiologia'. This software tool enables the compilation and record of radiological abnormal data occurred in a diagnostic institution. It will also facilitate the detailed analysis of the event and will increase the effectiveness and development of work performed by the Radiation Protection Service. At the end, a technical report is issued, in accordance with the regulations of the technical regulations, which could also be used as training tool to avoid another event in the future. (author)

  3. Medical SisRadiologia: a new software tool for analysis of radiological accidents and incidents in medical radiology

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Camila M. Araujo; Silva, Francisco C.A. da, E-mail: araujocamila@yahoo.com.br, E-mail: dasilva@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Araujo, Rilton A.; Pelegrineli, Samuel Q., E-mail: consultoria@maximindustrial.com.br, E-mail: samuelfisica@maximindustrial.com.br [Maxim Industrial, Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The man's exposure to ionizing radiation in health are has increased considerably due not only the great request of medical examinations as well as the improvement of the techniques used in diagnostic imaging, for example, equipment for conventional X-rays, CT scans, mammography, hemodynamic and others. Although the benefits of using of radiology techniques are unquestionable, the lack of training in radiation protection of the workers, associated with procedure errors, have been responsible for the increasing number of radiation overexposures of these workers. Sometimes these high doses are real and there is a true radiological accident. The radiation workers, named occupationally Exposed Individual (IOE), must comply with two national regulations: Governmental Decree 453/1998 of the National Agency of Sanitary Surveillance (Portaria 453/1998 ANVISA Agencia Nacional de Vigilancia Sanitaria), which establishes the basic guidelines for radiation protection in medial and dental radiology and; the Governmental Decree NR-32/2002 of the Ministry of Labour and Employment (Ministerio do Trabalho e Emprego), which establishes the basic guidelines for the worker's health. The two mandatory regulations postulate a detailed investigation in the event of radiation overexposure of an IOE. In order to advice the diagnostic institution to perform an efficient analysis, investigation and report of high doses, it is proposed the use of a computational tool named 'Medical SisRadiologia'. This software tool enables the compilation and record of radiological abnormal data occurred in a diagnostic institution. It will also facilitate the detailed analysis of the event and will increase the effectiveness and development of work performed by the Radiation Protection Service. At the end, a technical report is issued, in accordance with the regulations of the technical regulations, which could also be used as training tool to avoid another event in the future. (author)

  4. A model national emergency plan for radiological accidents; Plan modelo nacional de respuesta de emergencia para accidentes radiologicos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The IAEA has supported several projects for the development of a national response plan for radiological emergencies. As a result, the IAEA has developed a model National Emergency Response Plan for Radiological Accidents (RAD PLAN), particularly for countries that have no nuclear power plants. This plan can be adapted for use by countries interested in developing their own national radiological emergency response plan, and the IAEA will supply the latest version of the RAD PLAN on computer diskette upon request.

  5. Determination of the cesium-137 concentration profile in the main contamination focus of the radiological accident at Goiania-GO, Brazil

    International Nuclear Information System (INIS)

    Rocca, H.C.; Aoki, P.E.; Enokihara, C.T.; Rostelato, M.E.C.M.; Lepki, V.; Bambalas, E.

    1988-01-01

    The purpose of this paper is to describe the method used to determinate cesium-137 concentration profiles measured in function of depth and applied in seven areas considered as the main contamination focus. Since november 14 th to december 17 th 1987, 125 soil drillings were made and a total of 740 soil samples were prepared. Obtained data allowed to calculate the soil volume to be removed from contaminate areas. It was verified that after remotions the remaining activity was approximately 0,89 Ci. (author) [pt

  6. The environmental restoration in the management of radiological accidents with off site consequences

    International Nuclear Information System (INIS)

    Vazquez, C.; Montero, M.; Moraleda, M.; Diaz, J.; Claver, F.; Valles, O.; Rodriguez, N.; Gutierrez, J.

    1998-01-01

    Radiological accidents are among the potential cases of environmental contamination that could have consequences on the health of the population. These accidents, associated with an increase in the level of radiological exposure surpassing the natural background, have been investigated in greater depth than other conventional accidents. This investigation has included the evaluation of their probability, magnitude and consequences in order to establish safety norms. Nevertheless, the social perception of this type of risk appears to be disproportionately high. The development of a comprehensible and adequate standardized system for the evaluation of the radiological risk and the applicability of corrective actions to reduce this type of risk at local level, will undoubtedly contribute to increase the public confidence in the advised options for the restoration of environments contaminated with the long lived radionuclides. This system should consider the local specificity of each contaminated place, and take into account the associated unwanted consequences for each option. This paper presents the first results of a system to help the decision makers in the quantitative evaluation of the radiological risk produced by long lived radionuclides Cs 137, Cs 134 and Sr 90 spread over urban, agricultural and semi-natural environments and the applicable options to reduce it. The evaluation of these applicable options is made considering the reduction of dose that can be reached, the monetary costs and the significant associated secondary effects if there are any. All these factors are integrated for a time period depending on the half-life of the contaminants and on their strength and distribution on the scenario when intervention is being planned. (authors)

  7. Improvement of the plan of measures for cases of catastrophes corresponding to radiological accidents

    International Nuclear Information System (INIS)

    Jerez Vegueria, Pablo F.; Lopez Forteza; Yamil; Diaz Guerra, Pedro I.

    2003-01-01

    In the year 1988 the Plan of Measures for Cases of Catastrophe (PMCC) it was focused basically to the Central Electronuclear of Juragua and the Center of Investigations Nuclear both in construction in that moment. In Cuba, with the Ordinance Law Not. 170 of the System of Civil Defense of 1997 assign the EMNDC the responsibility for the address and coordination of the material resources and humans to make in front of any catastrophe type, including the emergencies radiological. However the radiological events that could happen in rest of those practical with ionizing radiations that were carried out in the country they were not contemplated in the old conception of planning of emergency of the PMCC. In the year 2001 the CNSN and EMNDC begin a revision of the national planning from the answer to radiological emergencies developing new conceptions of planning, preparation and answer to radiological emergencies using for it categories of planning recommended by the IAEA in new technical documents emitted to the effect. Presently work is exposed the new philosophy of planning and national answer that it sustains the current Annex radiological Accidents of the PMCC

  8. National plan of response to a major nuclear or radiological accident

    International Nuclear Information System (INIS)

    2014-02-01

    The first part of this document presents the response strategies and principles to be applied in the case of a major nuclear or radiological accident. It presents the general framework and the 8 reference situations which are used as references for the plan. It presents the general organisation of crisis management by the State (initial organisation, organisation at the national level, communication channel, international channels, case of transport of radioactive materials, responsibility of the various actors). Then, it presents the strategies of response, i.e., a global strategy and more specific strategies applicable in different sectors or fields: for the control of the concerned installation or transport, in the case of transport of radioactive materials, for the protection of the population, for the taking into care, for communication, for the continuity of social and economic life, at the European level, for the post-accidental management. The second part is a guide which contains sheets describing reactions in different situations: uncertainty, accident in an installation resulting in an either immediate and short, or immediate and long, or delayed and long release, accident in a transport of radioactive materials with potential release, accident occurring abroad which may have a more or less significant impact in France, and accident at sea

  9. The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences. Annexes

    International Nuclear Information System (INIS)

    2015-08-01

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  10. Methodology of radionuclides dis incorporation in people related to nuclear and radiological accidents

    International Nuclear Information System (INIS)

    Jimenez F, E. A.

    2014-01-01

    In this paper a classification of the radiological and nuclear accidents is presented, describing which the activities are, where they have occurred, their incidence and the learned lessons in these successes. The radiological accidents in which radioactive materials intervene can occur anywhere, and they are related to no controlled dangerous sources (abandoned, lost, stolen, or found sources), improper use of dangerous industrial and medical sources, exposition and contamination of people in general by an unknown origin, serious over expositions, menaces and willful misconduct, emergencies during transportation of radioactive material. A person can receive a dose of radiation from an external source, because of radioactive material placed on skin or on equipment, or because of ingestion or inhalation of radiological particles. The ingestion or the inhalation of radioactive material can cause an internal dose to the whole body or to a specific organ during a period of time. That is why a description of the processes of incorporation, the stages of incorporation and a description of the biokinetic models are also realized to understand the ingestion, transference and the excretion of the radioactive elements. In order to offer help to a victim of internal contamination, the dosimetric and medical diagnosis is very important. The most important techniques of dosimetric diagnosis are the dosimetry in vivo (cytogenetics and the counting in vivo of the whole body) and the bioassays. These techniques allow obtain data such as the radionuclide, the target organ, the absorbed dose, etc. At the same time, the doctor in charge must be attentive to the patients symptoms and their manifestation time, since they are an indicator, first, the patient suffered an irradiation, and second, of the range esteem of the received radiation dose. These are the parameters that are useful as criterion to decide if a person has to receive some treatment and select the methodologies that

  11. Two decades of radiological accidents direct causes, roots causes and consequences

    Directory of Open Access Journals (Sweden)

    Rozental Jose de Julio

    2002-01-01

    Full Text Available Practically all Countries utilize radioisotopes in medicine, industry, agriculture and research. The extent to which ionizing radiation practices are employed varies considerably, depending largely upon social and economic conditions and the level of technical skills available in the country. An overview of the majority of practices and the associated hazards will be found in the Table IV to VII of this document. The practices in normal and abnormal operating conditions should follow the basic principles of radiation protection and the Safety of Radiation Sources, considering the IAEA Radiation Protection and the Safety of Radiation Sources, Safety Series 120 and the IAEA Recommendation of the Basic Safety Standards for Radiation Protection, Safety Series Nº 115. The Standards themselves underline the necessity to be able to predict the radiological consequences of emergency conditions and the investigations that should need to be done. This paper describes the major accidents that had happened in the last two decades, provides a methodology for analyses and gives a collection of lessons learned. This will help the Regulatory Authority to review the reasons of vulnerabilities, and to start a Radiation safety and Security Programme to introduce measurescapable to avoid the recurrence of similar events. Although a number of accidents with fatalities have caught the attention of the public in recent year, a safety record has accompanied the widespread use of radiation sources. However, the fact that accidents are uncommon should not give grounds for complacency. No radiological accident is acceptable. From a radiation safety and security of the sources standpoint, accident investigation is necessary to determine what happened, why, when, where and how it occurred and who was (were involved and responsible. The investigation conclusion is an important process toward alertness and feedback to avoid careless attitudes by improving the comprehension

  12. Evaluation of the radiological situation of the remedied areas - 30 years after the radiological accident with Cesium-137

    International Nuclear Information System (INIS)

    Correa, R. da S.; Santos, E.E. dos; Barbosa, R.C.; Borges, A.F. de Almeida; Costa, H.F.; Pimenta, L.

    2017-01-01

    In September 1987, the radiation accident resulting from the removal and dismantling of a sealed source containing Cesium-137 chloride happened in Goiânia, GO, Brazil. Due to its high solubility and the weather conditions of the time, there were dispersion in the environment around seven main concentrations, located in the central region. This study aimed to present the evaluation of the radiological situation of the remedied areas - 30 years after the radiation accident with cesium-137. The three main focuses were studied, being the plot of land at the 57 street, Scrap Metal I and II. Radiometric surveys were performed using a SPP2 detector, 10 cm from the floor to evaluate the integrity of the concrete and 1 m from the soil, using the IDENTIFIDER detector model NG + , to compare with the values of background radiation. A 2 x 2m pre-fixed sampling loop was used. In the plot of land at the 57 street, measurements were made at 154 points, at 10 cm from the floor, at a mean of 150 ± 121 cps, while at 1 m from the soil, the average was 0.19 ± 0.10 μSv / h. In the Scrap Metal I were 262 measurements and the average at 10 cm of the floor was 147 ± 113 cps and the 1 meter of the soil was of 0.18 ± 0.12 μSv / h. In Scrap Metal II the average of the 66 measurements carried out at 10 cm was 117 ± 58 cps and at 1 meter it was 0.13 ± 0.03 μSv / h. Currently the radiological situation of the lots, are below the limits established by the norms of CNEN

  13. Dosimetric reconstruction of radiological accident by numerical simulations by means associating an anthropomorphic model and a Monte Carlo computation code

    International Nuclear Information System (INIS)

    Courageot, Estelle

    2010-01-01

    After a description of the context of radiological accidents (definition, history, context, exposure types, associated clinic symptoms of irradiation and contamination, medical treatment, return on experience) and a presentation of dose assessment in the case of external exposure (clinic, biological and physical dosimetry), this research thesis describes the principles of numerical reconstruction of a radiological accident, presents some computation codes (Monte Carlo code, MCNPX code) and the SESAME tool, and reports an application to an actual case (an accident which occurred in Equator in April 2009). The next part reports the developments performed to modify the posture of voxelized phantoms and the experimental and numerical validations. The last part reports a feasibility study for the reconstruction of radiological accidents occurring in external radiotherapy. This work is based on a Monte Carlo simulation of a linear accelerator, with the aim of identifying the most relevant parameters to be implemented in SESAME in the case of external radiotherapy

  14. Emergency preparedness and response to 'Not-in-a-Facility' radiological accidents

    International Nuclear Information System (INIS)

    Grlicarev, Igor

    2008-01-01

    The paper provides an overview of lessons learned from the past radiological accidents, which have not occurred in an operating facility, i.e. 'not-in-a-facility' radiological emergencies. A method to analyze status of prevention of accidents is proposed taking into account the experiences and findings from the past events. The main emergency planning items are discussed, which would render effective response in case of such emergencies. Although the IAEA has published many documents about establishing an adequate emergency response capability, it is not an easy task to bring these recommendations into life. This paper gives some hints how to overcome the most obvious difficulties while users of these documents trying to adapt the guidance to their own needs. The special cases of alpha emitters and radiological dispersal devices were considered separately. The balanced approach to emergency response is promoted throughout the text, which means that a level of preparedness should be commensurate to the threat and the existing resources should be used to the extent possible. (author)

  15. Resuspension and spreading of 137 Cs in urban areas: the Goiania experience

    International Nuclear Information System (INIS)

    Rio, M.A.P. do.

    1993-01-01

    The characteristics of the Goiania accident (a restricted and local contamination) together with the fact that the region has received no contribution from the Chernobyl accident, neither from the atomic tests represents an unique opportunity to study the behaviour of 147 Cs at an urban area. The study of the resuspension and deposition processes of the 137 Cs associated to surface soil was performed at a house at the 57th. street near the main primary focus. It was decided to use the two gardens of the house, where continuous measurements of aerosol and total deposition took place. Impactor measurements were also performed to evaluate the size distribution of particles in the air. The results as a whole suggests a very complex pattern for the 137 Cs resuspension and deposition in Goiania, indicating to be these mechanisms local,phenomena and without evidences of a significant spreading of 137 Cs from the places of primary contamination. (author). 63 refs., 14 figs., 9 tabs

  16. Convention on early notification of a nuclear accident. Convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1987-05-01

    The document refers to the Convention on early notification of a nuclear accident (INFCIRC-335) and to the Convention on assistance in the case of a nuclear accident or radiological emergency (INFCIRC-336). Part I of the document contains the texts of reservations/declarations made by some of the countries upon or following signature. Part II contains the texts of reservations/declarations made upon or following deposit of instrument, expressing consent to be bound

  17. Convention on early notification of a nuclear accident and convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1991-09-01

    The document refers to the Convention on Early Notification of a Nuclear Accident (IAEA-INFCIRC-335) and to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (IAEA-INFCIRC-336). Part I contains the status lists as of August 31, 1991. Part II contains reservations/declarations made upon expressing consent to be bound and objections there to. Part III contains reservations/declarations made upon signature

  18. Convention on Early Notification of a Nuclear Accident and Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency

    International Nuclear Information System (INIS)

    1997-01-01

    Part I: Status lists as of 31 December 1996. A. Convention on Early Notification of a Nuclear Accident (Notification Convention). B. Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention). PART II: Texts of reservations/declarations made upon or following expressing consent to be bound and objections thereto Part III: Texts of reservations/declarations made upon signature

  19. Convention on early notification of a nuclear accident and convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1992-09-01

    The document refers to the Convention on Early Notification of a Nuclear Accident (CENNA) (IAEA-INFCIRC-335) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) (IAEA-INFCIRC-336). Part I contains the status lists as of 10 September 1992, part II contains the texts of reservations/declarations made upon expressing consent to be bound and objections there to, and part III contains the texts of reservations/declarations made upon signature

  20. Convention on early notification of a nuclear accident and convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1997-01-01

    The document refers to the Convention on Early Notification of a Nuclear Accident (CENNA) (IAEA-INFCIRC-335) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) (IAEA-INFCIRC-336). Part I contains the status list as of 31 December 1996, Part II contains the texts of reservations/declarations made upon or following expressing consent to be bound and objections thereto, and Part III contains the texts of reservations/declarations made upon signature

  1. Convention on early notification of a nuclear accident and convention on assistance in the case of a nuclear accident or radiological emergency

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-28

    The document refers to the Convention on Early Notification of a Nuclear Accident (CENNA) (IAEA-INFCIRC-335) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) (IAEA-INFCIRC-336). Part I contains the status list as of 31 December 1996, Part II contains the texts of reservations/declarations made upon or following expressing consent to be bound and objections thereto, and Part III contains the texts of reservations/declarations made upon signature.

  2. Adjusting ability and sensibility for an accident

    International Nuclear Information System (INIS)

    Rozental, J.J.

    1998-01-01

    Adjusting ability (technical competence) and sensibility (consciousness) are the two most important priorities any staff member of any organization should bear in mind while acting during a nuclear or radiological emergency. The discussion is aimed at the national authorities of states which do not have a major nuclear power reactor programme, and especially at the IAEA and WHO: although a decade has gone by, the lessons from the radiological accident in Goiania have not been fully learned. The events which unravelled in the fall of 1987 took the population of the city of Goiania completely by surprise: they did not comprehend what had happened and failed to grasp what measures needed to be taken, a situation which precipitated a very complex psychological reaction, coupled with discrimination. To ensure the safety of radiation sources and nuclear installations, national and international organizations should direct their efforts towards educating and training staff in developing countries who work with ionizing radiation and promoting organizational capacity. This should be done first, by improving safety qualitatively so as to better control the uses of radioactive materials in medicine, agriculture, industry and research, and secondly, by assisting countries without a major nuclear power reactor programme to develop an objective and realistic emergency response training programme. (author)

  3. Status of safety technology for radiological consequence assessment of postulated accidents in liquid metal fast breeder reactors, Canoga Park, California, 29 July--31 July 1975

    International Nuclear Information System (INIS)

    1975-07-01

    State-of-the-art capabilities are examined for prediction and mitigation of radiological consequences of postulated LMFBR accidents. The following topics are treated: radioactive source terms, sodium reactions, aerosol behavior, radiological dose assessment, and engineered safeguards. (U.S.)

  4. Risks and consequences of a hypothetical radiological accident on nuclear powered submarine traversing Suez canal

    International Nuclear Information System (INIS)

    Salama, Mohamed

    2008-01-01

    Full text: Egypt has unique problem in Suez Canal, although there are, a number of radioactive Cargos traveling through the Canal which includes new and spent reactor fuel and about 100 metric tons of uranium hexafluoride each year, under the regulatory control of the Egyptian Atomic Energy Authority, there is, still a major problem concerning the passage of a number of nuclear powered vessels and submarines passing through the canal several times each year. The passage of these vessels and submarines has a political situation and not under the regulatory control of the Egyptian regulatory body. In spite of all precautions that are taken, in the nuclear powered vessels and submarines from the point of view of the rugged design of the reactor plant, multiple safety systems and operation with exceptional consideration for safety. Although of all of these a potential for a serious accident may does arise, even though, its probability is minimal. The Government of Egypt has established a national radiological emergency plan in order to cope with any radiological accidents, which may arise inside the country. Suez Canal lies in the north east of Egypt, and passes through a zone of considerable business, agriculture and industrial activities. The zone consists of three populated provinces, Port Said, Ismailia and Suez. According to Suez Canal authority regulations it is not allowed for these vessels and submarines to be landed in port. The motivation of the present paper was undertaken to discuss a hypothetical nuclear reactor accident aboard a nuclear powered submarine occurred during its passage in the Suez Canal. Such an accident will produce a radioactive cloud containing a number of radioactive materials. In such type of accidents contamination and causality zones, could extend to several kilometers. The different phases of the accident are going to be discussed and analyzed. The emergency actions taken during the accident phases are going to be presented. The

  5. Radiological Emergency Preparedness after the Early Phase of an Accident : Focusing on an Air Contamination Event

    International Nuclear Information System (INIS)

    Jeong, Hyo Joon; Hwang, Won Tae; Kim, Eun Han; Han, Moon Hee

    2010-01-01

    Toxic materials in an urban area can be caused by a variety of events, such as accidental releases on industrial complexes, accidents during the transportation of hazardous materials and intentional explosions. Most governments around the world and their citizens have become increasingly worried about intentional accidents in urban area after the 911 terrorist attack in the United States of America. Even though there have been only a few attempted uses of Radiological Dispersal Devices (RDDs), accidental releases have occurred many times at commercial nuclear power plants and nuclear waste disposal sites. When an intentional release of radioactive materials occurs in an urban area, air quality for radioactive materials in the environment is of great importance to take action for countermeasures and environmental risk assessments. Atmospheric modeling is part of the decision making tasks and that it is particularly important for emergency managers as they often need to take actions quickly on very inadequate information(1). A simple model such as HOTSPOT required wind direction and source term would be enough to support the decision making in the early phase of an accident, but more sophisticated atmospheric modeling is required to adjust decontamination area and relocation etc after the early phase of an accidental event. In this study, we assume an explosion of 137 Cs using RDDs in the metropolitan area of Soul, South Korea. California Puff Model (CALPUFF) is used to calculate an atmospheric dispersion and transport for 137 Cs. Atmospheric dispersion and quantitative radiological risk analysis for 137 Cs were performed assuming an intentional explosion in the metropolitan area of Soul, South Korea after the early phase of emergency. These kinds of atmospheric modeling and risk analysis could provide a means for decision makers to take action on important issues such as the cleanup of the contaminated area and countermeasures to protect the public caused by

  6. Research activities about the radiological consequences of the Chernobyl NPS accident and social activities to assist the sufferers by the accident

    International Nuclear Information System (INIS)

    Imanaka, T.

    1998-03-01

    The 12th anniversary is coming soon of the accident at the Chernobyl nuclear power station in the former USSR on April 26, 1986. Many issues are, however, still unresolved about the radiological impacts on the environment and people due to the Chernobyl accident. This report contains the results of an international collaborative project about the radiological consequences of the Chernobyl accident, carried out from November 1995 to October 1997 under the research grant of the Toyota foundation. Collaborative works were promoted along with the following 5 sub-themes: 1) General description of research activities in Russia, Belarus and Ukraine concerning the radiological consequences of the accident. 2) Investigation of the current situation of epidemiological studies about Chernobyl in each affected country. 3) Investigation of acute radiation syndrome among inhabitants evacuated soon after the accident from the 30 km zone around the Chernobyl NPS. 4) Overview of social activities to assist the sufferers by the accident in each affected country. 5) Preparation of special reports of interesting studies being carried out in each affected country. The 27 papers are indexed individually. (J.P.N.)

  7. Recommendations guide in radiological accidents for first respondents, firemen and policemen

    International Nuclear Information System (INIS)

    Astudillo, A. J.; Ambriz, J. J.; Paredes, L. C.

    2011-10-01

    The action guides for the primary task forces of the Firemen Corps and the Public Security Elements, before the presence of radiological accidents are presented. The objective of these guides is to give the recommendations for the initial response to the emergency that fulfills the following criterions: to to Apply with readiness all the reasonable measures to protect the victims and the public, in order to minimizing the radiological and non radiological effects to the health; b) to Retrieve the control of the situation and to mitigate the consequences; c) to Protect the emergency personnel during the response operations; d) to Compile and to protect the information that can be useful to treat the effects to the health, of the victims and public in general, and to prevent that emergencies seemed are repeat in the future; e) to Create and to maintain the public's trust in the response; f) to Establish a base for an action of lingering response, and to Suggest evaluation criterions of the radiological emergency, the organization criterions, operation and surrounding of the emergency area. (Author)

  8. Radiological consequences of the reactor accident at Three Mile Island, Pennsylvania, USA

    International Nuclear Information System (INIS)

    Bryant, P.M.

    1979-01-01

    The findings of the Ad Hoc Population Dose Assessment Group are reviewed and summarized (Population Dose and Health Impact of the Accident at the Three Mile Island Nuclear Station. A preliminary assessment for the period March 28 through April 7, 1979; May 10, 1979. Washington DC, US Government Printing Office, 1979). The principal radionuclides released were xenon-133 and xenon-135, with some iodine-131. External exposure to gamma radiation was estimated from TLDs positioned at various on-site and off-site locations. Lung exposure from inhaled xenon-133 was calculated and air and milk monitoring results gave potential dose equivalents to a child's thyroid. These numerical estimates will be further refined, but only minor corrections to the present values are anticipated. The findings of this preliminary assessment have indicated that the radiological consequences to the public of the reactor accident are minimal. (UK)

  9. Environment radiological monitoring by JNC related to the JCO criticality accident

    International Nuclear Information System (INIS)

    Watanabe, Hitoshi

    2001-01-01

    Concerning the criticality accident at JCO Co., Ltd. (JCO) which occurred at 10:35 on 30th Sep. 1999, Japan Nuclear Cycle Development Institute (JNC) established ''JNC's task force'' at 12:35 on the same data in conjunction with Head Office and Tokai Works. JNC's task force had collaborated on environmental radiological monitoring with the government of Japan and the local governments. This report compiles the results of the environmental monitoring performed by JNC's task force based on the request from the government of Japan and the local governments. (author)

  10. Report on a radiological accident in the southern Urals on 29 September 1957

    International Nuclear Information System (INIS)

    Nikipelov, B.V.; Romanov, G.N.; Buldakov, L.A.; Babaev, N.S.; Kholina, Yu.B.; Mikerin, E.I.

    1989-07-01

    In response to concern expressed by the international community about the possible consequences of a radiological accident which occurred at a military installation in the southern Urals in 1957, Soviet specialists have prepared this report containing information on this event. Owing to a fault in the cooling system used for the concrete tanks containing highly active nitrate acetate wastes, a chemical explosion occurred in these materials on 29 September 1957 and radioactive fission products were released into the atmosphere and subsequently scattered and deposited in parts of the Chelyabinsk, Svendlovsk and Tyumensk provinces. 9 tabs

  11. Remediation strategies after nuclear or radiological accidents: part 1 - database development

    International Nuclear Information System (INIS)

    Silva, Diogo N.G.; Wasserman, Maria Angelica V.; Rochedo, Elaine R.R.

    2009-01-01

    The selection of protective measures and of remediation strategies of areas after a nuclear or radiological accident needs to be based on previously established criteria, in way to minimize the public's emotional stress and the exposure to workers involved in cleanup operations due to the implementation of procedures that are not effective in reducing doses to the public. Thus this work intended to develop a database which allows supporting the decision-making process after these accidents, by describing the foreseen strategies according to the type of accident and the type of affected environment, in order to be used in a multi-criteria selective process. To achieve that, in this first stage, the database has been developed including the following aspects: type of environment (urban, rural or aquatic); their contamination removal efficiency, as function of the time elapsed since the contamination event; the type and the amount of waste generated in the application of the strategy; the expected doses to the work team and basic needs such as specific materials, equipment, training, IPE, among others. The protection measures are usually described in literature considering their activity removal efficiency of a certain surface or environment. In order to determine their efficiency in the reduction of doses, a second stage is foreseen, involving the simulation of the implementation of the measures in different moments after the contamination, based on pre-defined accidents and scenarios, with focus on the surroundings of the Brazilian Nuclear Power Plants in Angra dos Reis. (author)

  12. Remediation strategies after nuclear or radiological accidents: part 1 - database development

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo N.G.; Wasserman, Maria Angelica V. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)], e-mail: dneves@ird.gov.br, e-mail: angelica@ird.gov.br, e-mail: lfcconti@ird.gov.br; Rochedo, Elaine R.R. [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil). Coordenacao de Instalacoes Nucleares], e-mail: erochedo@cnen.gov.br

    2009-07-01

    The selection of protective measures and of remediation strategies of areas after a nuclear or radiological accident needs to be based on previously established criteria, in way to minimize the public's emotional stress and the exposure to workers involved in cleanup operations due to the implementation of procedures that are not effective in reducing doses to the public. Thus this work intended to develop a database which allows supporting the decision-making process after these accidents, by describing the foreseen strategies according to the type of accident and the type of affected environment, in order to be used in a multi-criteria selective process. To achieve that, in this first stage, the database has been developed including the following aspects: type of environment (urban, rural or aquatic); their contamination removal efficiency, as function of the time elapsed since the contamination event; the type and the amount of waste generated in the application of the strategy; the expected doses to the work team and basic needs such as specific materials, equipment, training, IPE, among others. The protection measures are usually described in literature considering their activity removal efficiency of a certain surface or environment. In order to determine their efficiency in the reduction of doses, a second stage is foreseen, involving the simulation of the implementation of the measures in different moments after the contamination, based on pre-defined accidents and scenarios, with focus on the surroundings of the Brazilian Nuclear Power Plants in Angra dos Reis. (author)

  13. Radiological dose assessment for bounding accident scenarios at the Critical Experiment Facility, TA-18, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    1991-09-01

    A computer modeling code, CRIT8, was written to allow prediction of the radiological doses to workers and members of the public resulting from these postulated maximum-effect accidents. The code accounts for the relationships of the initial parent radionuclide inventory at the time of the accident to the growth of radioactive daughter products, and considers the atmospheric conditions at time of release. The code then calculates a dose at chosen receptor locations for the sum of radionuclides produced as a result of the accident. Both criticality and non-criticality accidents are examined

  14. SisRadiologia: a new software tool for analysis of radiological accidents and incidents in industrial radiography

    International Nuclear Information System (INIS)

    Lima, Camila M. Araujo; Silva, Francisco C.A. da; Araujo, Rilton A.

    2013-01-01

    According to the International Atomic Energy Agency (IAEA), many efforts have been made by Member states, aiming a better control of radioactive sources. Accidents mostly happened in practices named as high radiological risk and classified by IAEA in categories 1 and 2, being highlighted those related to radiotherapy, large irradiators and industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography area, involving 37 workers, 110 members of the public and 12 fatalities. Records display 5 severe radiological accidents in industrial radiography activities in Brazil, in which 7 workers and 19 members of the public were involved. Such events led to hands and fingers radiodermatitis, but to no death occurrence. The purpose of this study is to present a computational program that allows the data acquisition and recording in the company, in such a way to ease a further detailed analysis of radiological event, besides providing the learning cornerstones aiming the avoidance of future occurrences. After one year of the 'Industrial SisRadiologia' computational program application - and mostly based upon the workshop about Analysis and Dose Calculation of Radiological Accidents in Industrial Radiography (Workshop sobre Analise e Calculo de dose de acidentes Radiologicos em Radiografia Industrial - IRD 2012), in which several Radiation Protection officers took part - it can be concluded that the computational program is a powerful tool to data acquisition, as well as, to accidents and incidents events recording and surveying in Industrial Radiography. The program proved to be efficient in the report elaboration to the Brazilian Regulatory Authority, and very useful in workers training to fix the lessons learned from radiological events.

  15. Evaluation of secular trend and the existence of cases of clusters of bladder cancer in Goiania: descriptive study population-based; Avaliacao da tendencia temporal e da existencia de casos de clusters de cancer de bexiga em Goiania: estudo descritivo de base populacional

    Energy Technology Data Exchange (ETDEWEB)

    Antonio, Gisele Guimaraes Daflon

    2008-07-01

    More than 20 years after the radiological accident with cesium-137 in the city of Goiania, there is still a feeling in local population that the number of cases of cancer in the city is growing up due to the past radiation exposure and that the number of people contaminated or exposed was higher than the number reported. The present study aims to evaluate the temporal trend and the space-time distribution of bladder cancer cases in Goiania from 1988 and 2003, taking into account that bladder cancer presents the highest risk coefficients per unit of radiation dose among solid cancers. The study population was composed of all incident cases of bladder cancer registered in the Population-Based Cancer Registry of Goiania, between 1988 and 2003.Temporal trend of bladder cancer incidence was analyzed by sex and age groups ( < 60 and {>=} 60 years of age) through polynomial regression using age standardized incidence rates of bladder cancer (world population). SaTscan was used to determine whether statistical significant geographic clusters of high incidence of bladder cancer cases can be located in the city. The results showed a significant increase of bladder cancer incidence rates in males of all ages (p= 0.025) and for age group higher or equal to 60 years old (p=O.022), and a stability in trends for female sex. In the space-time analysis, a cluster was identified, however without statistical significance (p=0.278) and its location has no relationship with the main focuses of contamination of the radiological accident in 1987. We concluded that, despite of the increase of incidence rates in males, this can be explained by the improvement in diagnostic procedures throughout time, being this increase still not perceived in females considering the small number of cases. As chance can not be ruled out as the explanation of the identified cluster, we do not suggest any further detailed investigation in this cluster, as the occurrence of cluster diseases in space can occur

  16. The Fukushima accident: radiological consequences and first lessons. Proceedings; L'accident de Fukushima: consequences radiologiques et premiers enseignements. Recueil des presentations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document brings together the available presentations given at the conference organised by the French society of radiation protection about the Fukushima accident, its radiological consequences and the first lessons learnt. Sixteen presentations (slides) are compiled in this document and deal with: 1 - Accident progress and first actions (Thierry Charles, IRSN); 2 - Conditions and health monitoring of the Japanese intervention teams (Bernard Le Guen, EDF); 3 - The Intra Group action after the Fukushima accident (Michel Chevallier, Groupe Intra; Frederic Mariotte, CEA); 4 - Processing of effluents (Georges Pagis, Areva); 5 - Fukushima accident: impact on the terrestrial environment in Japan (Didier Champion, IRSN); 6 - Consequences of the Fukushima accident on the marine environment (Dominique Boust, IRSN); 7 - Territories decontamination perspectives (Pierre Chagvardieff, CEA); 8 - Actions undertaken by Japanese authorities (Florence Gallay, ASN); 9 - Japanese population monitoring and health stakes (Philippe Pirard, InVS); 10 - Citizen oversight actions implemented in Japan (David Boilley, ACRO); 11 - Implementation of ICRP's (International Commission on Radiological Protection) recommendations by Japanese authorities: first analysis (Jacques Lochard, CIPR); 12 - Control of Japan imported food stuff (David Brouque, DGAL); 13 - Questions asked by populations in France and in Germany (Florence-Nathalie Sentuc, GRS; Pascale Monti, IRSN); 14 - Labour law applicable to French workers working abroad (Thierry Lahaye, DGT); 15 - Protection of French workers working in Japan, Areva's experience (Patrick Devin, Areva); 16 - Fukushima accident experience feedback and post-accident nuclear doctrine (Jean-Luc Godet, ASN)

  17. Radiological review of accident and emergency radiographs: A 1-year audit

    International Nuclear Information System (INIS)

    Williams, Stuart M.; Connelly, Daniel J.; Wadsworth, Susan; Wilson, David

    2000-01-01

    AIM: To assess the impact and cost effectiveness of a system of radiological review of accident and emergency (A and E) plain films. MATERIALS AND METHODS: Review documentation was studied retrospectively over a 1-year period. Six hundred and eighty-four actual or suspected errors in the initial radiological interpretation by A and E staff were highlighted by radiologists in training. These selected 'red reports' were then further reviewed by a musculoskeletal radiologist and a more senior member of the A and E team. RESULTS: Three hundred and fifty-one missed or strongly suspected fractures were detected, with ankle, finger and elbow lesions predominating. Other errors included 11 missed chest radiograph abnormalities and 24 A and E false-positives. Radiologists in training tended to over-report abnormalities with an 18% false-positive rate when compared to the subsequent musculoskeletal radiology opinion. Following review, further action was taken by A and E staff in 286 (42.6%) of cases. No operative intervention was required in those patients with a delayed or missed A and E diagnosis. Consideration is given to the cost of providing this form of review and the impact of medico-legal factors. CONCLUSION: Compared with the large numbers of patients seen and radiographed in a busy A and E department, the number of radiological errors was small. There were even fewer changes in management. Despite this, concern over litigation, clinical governance and future work patterns in A and E make this form of review a useful means of risk reduction in a teaching hospital. Williams, S.M. (2000). Clinical Radiology 55, 861-865

  18. Radiological consequences of accidents during disposal of spent nuclear fuel in a deep borehole

    International Nuclear Information System (INIS)

    Grundfelt, Bertil

    2013-07-01

    In this report, an analysis of the radiological consequences of potential accidents during disposal of spent nuclear fuel in deep boreholes is presented. The results presented should be seen as coarse estimates of possible radiological consequences of a canister being stuck in a borehole during disposal rather than being the results of a full safety analysis. In the concept for deep borehole disposal of spent nuclear fuel developed by Sandia National Laboratories, the fuel is assumed to be encapsulated in mild steel canisters and stacked between 3 and 5 km depth in boreholes that are cased with perforated mild steel casing tubes. The canisters are joined together by couplings to form strings of 40 canisters and lowered into the borehole. When a canister string has been emplaced in the borehole, a bridge plug is installed above the string and a 10 metres long concrete plug is cast on top of the bridge plug creating a floor for the disposal of the next sting. In total 10 canister strings, in all 400 canisters, are assumed to be disposed of at between 3 and 5 kilometres depth in one borehole. An analysis of potential accidents during the disposal operations shows that the potentially worst accident would be that a canister string is stuck above the disposal zone of a borehole and cannot be retrieved. In such a case, the borehole may have to be sealed in the best possible way and abandoned. The consequences of this could be that one or more leaking canisters are stuck in a borehole section with mobile groundwater. In the case of a leaking canister being stuck in a borehole section with mobile groundwater, the potential radiological consequences are likely to be dominated by the release of the so-called Instant Release Fraction (IRF) of the radionuclide inventory, i.e. the fraction of the radionuclides that as a consequence of the in-core conditions are present in the annulus between the fuel pellets and the cladding or on the grain boundaries of the UO 2 matrix. The

  19. Radiological consequences of accidents during disposal of spent nuclear fuel in a deep borehole

    Energy Technology Data Exchange (ETDEWEB)

    Grundfelt, Bertil [Kemakta Konsult AB, Stockholm (Sweden)

    2013-07-15

    In this report, an analysis of the radiological consequences of potential accidents during disposal of spent nuclear fuel in deep boreholes is presented. The results presented should be seen as coarse estimates of possible radiological consequences of a canister being stuck in a borehole during disposal rather than being the results of a full safety analysis. In the concept for deep borehole disposal of spent nuclear fuel developed by Sandia National Laboratories, the fuel is assumed to be encapsulated in mild steel canisters and stacked between 3 and 5 km depth in boreholes that are cased with perforated mild steel casing tubes. The canisters are joined together by couplings to form strings of 40 canisters and lowered into the borehole. When a canister string has been emplaced in the borehole, a bridge plug is installed above the string and a 10 metres long concrete plug is cast on top of the bridge plug creating a floor for the disposal of the next sting. In total 10 canister strings, in all 400 canisters, are assumed to be disposed of at between 3 and 5 kilometres depth in one borehole. An analysis of potential accidents during the disposal operations shows that the potentially worst accident would be that a canister string is stuck above the disposal zone of a borehole and cannot be retrieved. In such a case, the borehole may have to be sealed in the best possible way and abandoned. The consequences of this could be that one or more leaking canisters are stuck in a borehole section with mobile groundwater. In the case of a leaking canister being stuck in a borehole section with mobile groundwater, the potential radiological consequences are likely to be dominated by the release of the so-called Instant Release Fraction (IRF) of the radionuclide inventory, i.e. the fraction of the radionuclides that as a consequence of the in-core conditions are present in the annulus between the fuel pellets and the cladding or on the grain boundaries of the UO{sub 2} matrix

  20. Physical dose reconstruction in case of radiological accidents: an asset for the victims' management

    International Nuclear Information System (INIS)

    Huet, Christelle; Trompier, Francois; Clairand, Isabelle; Bottollier-Depois, Jean-Francois

    2008-01-01

    In most cases of radiological accidents caused by an external source, the irradiation is heterogeneous, even for a whole body irradiation. Therefore, more than a whole body dose, estimating the dose distribution in the victim's organism is essential to assess biological damages. This dose distribution can be obtained by physical dosimetric reconstruction methods. The laboratory has developed several techniques based on experimental and numerical dose reconstruction and retrospective dosimetry by ESR in order to assess as accurately as possible and as quickly as possible the dose received and especially its distribution throughout the organism so that the physicians may fine tune their diagnosis and prescribe the most suitable treatment. These last years, these techniques were applied several times and each time the results obtained proved to be essential for the physicians in charge of the victims in order to define the therapeutic strategy. This article proposes a review of the physical dose reconstructions performed in the laboratory for recent radiological accidents focusing on the complementarity of the methods and the gain for the victims' management. (author)

  1. Assessment of the radiological risks of road transport accidents involving type A package shipments

    International Nuclear Information System (INIS)

    Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; Hughes, J.S.; Shaw, K.B.; Hedberg, B.; Simenstad, P.; Svahn, B.; Hienen, J.F.A.; Jansma, R.

    1998-01-01

    This paper is an account of work performed within a multi-lateral research project on the radiological risks associated with the transportation of Type A packaged radioactive material. The research project has been performed on behalf of the European Commission and various national agencies of the participating countries and involved organizations and institutes of five EU Member States, France, Germany, The Netherlands, Sweden, and the UK. The main objectives of the research project were the assessment and appraisal of the potential radiological risks of road transport accidents involving Type A package shipments in participating EU Member States. Data were collected and include harmonized sets information related to the type, quantity and characteristics of Type A package shipments by road. Such databases were basically non-existent until recently. The results are expected to be valuable to both national agencies and international organizations, with responsibilities for the safe transport of radioactive materials by providing some insight in the carriage of radioactive materials by road making up a major fraction of radioactive material transports. Similarly, a wide body of information has been collected and compiled on road transport accidents in terms of the frequency of occurrence and the severity of accidental impact loads potentially experienced by a Type A package.In addition, the results will facilitate judgement of the adequacy of the IAEA Transport Regulations as far as Type A packages are concerned. (O.M.)

  2. How to effectively manage crisis situation in the early phase of a radiological accident?

    International Nuclear Information System (INIS)

    Borysiewicz, M.; Potempski, S.

    2003-01-01

    Full text: In the early phase of accident reasonable decisions should be undertaken in a short time, where often there is still an uncertainty in assessment of radiological situation. The following key factors are of important meaning in a process of working out an optimized decision: (a) accurate information on accident, (b) proper assessment of current status and prognosis of development of radiological situation, (c) proper information on availability of means needed for emergency action like rescue teams, technical and medical equipment, means of transport etc., (d) reliable and fast communication system between decision makers, persons responsible for management of crisis situation, rescue teams and people in affected areas. All these elements can be supported by more or less computerized systems. The first two (a) and (b), depend, in general, on radiological monitoring and decision support systems, using pre-defined scenarios and sometimes sophisticated methods for assessment of radiological situation. The element (c) is very often supported by GIS-like systems available at crisis centres. The last issue however is, to much extent, a question of proper organization of decision making process and management during emergency action. lt seems also that often there are some kind of gaps between items (a)e) and (c)/(d) or maybe particularly between (d) and other factors mentioned above. Hence, there is still a need for more integrated approach. lt should be also mentioned that the last element (d) is usually the weakest point in the whole system. This is often caused by not clear organization and division of responsibilities between persons engaged in the decision making process and management. The problem of communication has also some technical aspects. This can be solved by using more advanced techniques like satellite technologies and centralized computer communication systems of new generation, which allows for fast and reliable sending and receiving messages

  3. Validation of a mathematical phantom for dose assessment of radiological accidents

    International Nuclear Information System (INIS)

    Gomes, Joana D' Arc R.L.; Gomes, Rogerio S.; Costa, Mara Lucia L.

    2013-01-01

    Sealed radioactive sources are widely used in the industry with the purpose of well logging, non-destructive testing, food irradiation, process control systems, elemental analysis and others. Among the most used sources, it can mention: 137 Cs, 60 Co, 192 Ir, 85 Kr and Americium-Beryllium with radiation activities ranging between a few MegaBecquerels (MBq) to million of GBq, as the case of food irradiation. In general, these sources present sufficient activity to represent a significant health hazard when inadequately shielded or not handled according to proper safety procedures, producing radiation exposures to workers and to members of public. In cases of overexposure to ionizing radiation, an estimative of the dose received by victims of radiation accidents, as well as its distribution within the organism, can be provided by use an anthropomorphic phantom associates with a theoretical simulation Monte Carlo method to simulate the radioactive source and its interactions with the phantom. In this work is presented the validation results of application of a mathematical phantom modeled in Geant4, as a tool to reconstruct dose of radiological accidents due to external exposure. The results are compared with the dosimetry of real accidents. (author)

  4. Characteristics of the development of the radiological situation resulting from the accident, intervention levels and countermeasures

    International Nuclear Information System (INIS)

    Belyaev, S.T.; Demin, V.F.; Kutkov, V.A.; Bariakhtar, V.G.; Petriaev, E.P.

    1996-01-01

    Great efforts have been made in the frame of the national and international research programs to get complete data on the radioactive releases, environmental contamination and radiological situation resulted from the Chernobyl accident. Beginning from the first publication (IAEA meeting, August 1986) these data have been considerably improved and added. The most important change of them with their influence on the decision making in the mitigation activity and the current situation is described and analyzed. The national and international regulatory documents at the moment of the accident were neither complete nor perfect in some necessary aspects especially in respect to the countermeasures at the intermediate and long-term phases. New documents have been worked out during the intervention activity. From 1986 series of documents were developed on the national and international levels. These documents are considered and analyzed in the context of their practical implementation and by the modern experience and research results. The history of countermeasures adopted on the different intervention phases are described. These documents mainly establish intervention levels in terms of averted doses and regulate only radiation protection. They don't content any intervention levels in terms of residual doses and risk, which are necessary for regulation of social and health protection of population suffered from the accident. Other restriction for the optimal regulation comes from use of the effective dose for establishing intervention levels. These and other respective aspects are discussed

  5. Information support for analysing the radiological impact of areas affected by the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Shershakov, V.M.; Baranov, A.Yu.; Borodin, R.V.; Golubenkov, A.V.; Godko, A.M.; Kosykh, V.S.; Korenev, A.I.; Meleshkin, M.A. [SPA `Typhoon`, Obninsk (Russian Federation)

    1996-09-01

    The organisation and management of data banks generated using data from monitoring the radiological situation after the Chernobyl accident is of key importance to health care and rehabilitation in the contaminated areas. Measures following the accident were based on large scale studies involving analysis and prediction of radioactive contamination. These studies included measurements of radioactivity in air, soil and water, modelling and prediction of radionuclides transport and transformation. This required the development of a computer system RECASS (RadioEcological Analysis Support System) which is currently being developed in SPA ``Typhoon``. The main tasks of RECASS are to integrate data on existing characteristics of the environment, and data on air, soil, water and biota-contamination with numerical models that account for radionuclide behaviour in all environmental media, and with radiation dose formations that are based on geographic information system (GIS) principles. The data bank of the system includes the following data bases: a data base with measurement of radioactive contamination levels in environmental media (soil, air, water); a meteorological data base; and a data base with administrative and demographic data. A set of models for radionuclide transfer in various environments incorporated in the chain permits short or long-term predictions to be made. The results of implementing RECASS to reconstruct the time and space picture of contamination in the first days after the Chernobyl accident are presented. (Author).

  6. Informatics support for analysing the radiological impact of areas affected by the Chernobyl accident

    International Nuclear Information System (INIS)

    Shershakov, V.M.; Baranov, A.Yu.; Borodin, R.V.; Golubenkov, A.V.; Godko, A.M.; Kosykh, V.S.; Korenev, A.I.; Meleshkin, M.A.

    1996-01-01

    The organisation and management of data banks generated using data from monitoring the radiological situation after the Chernobyl accident is of key importance to health care and rehabilitation in the contaminated areas. Measures following the accident were based on large scale studies involving analysis and prediction of radioactive contamination. These studies included measurements of radioactivity in air, soil and water, modelling and prediction of radionuclides transport and transformation. This required the development of a computer system RECASS (RadioEcological Analysis Support System) which is currently being developed in SPA ''Typhoon''. The main tasks of RECASS are to integrate data on existing characteristics of the environment, and data on air, soil, water and biota-contamination with numerical models that account for radionuclide behaviour in all environmental media and with radiation dose formations that are based on geographic information system (GIS) principles. The data bank of the system includes the following databases: a data base with measurement of radioactive contamination levels in environmental media (soil, air, water); a meteorological data base; and a data base with administrative and demographic data. A set of models for radionuclide transfer in various environments incorporated in the chain permits short or long-term predictions to be made. The results of implementing RECASS to reconstruct the time and space picture of contamination in the first days after the Chernobyl accident are presented. (Author)

  7. Information support for analysing the radiological impact of areas affected by the Chernobyl accident

    International Nuclear Information System (INIS)

    Shershakov, V.M.; Baranov, A.Yu.; Borodin, R.V.; Golubenkov, A.V.; Godko, A.M.; Kosykh, V.S.; Korenev, A.I.; Meleshkin, M.A.

    1996-01-01

    The organisation and management of data banks generated using data from monitoring the radiological situation after the Chernobyl accident is of key importance to health care and rehabilitation in the contaminated areas. Measures following the accident were based on large scale studies involving analysis and prediction of radioactive contamination. These studies included measurements of radioactivity in air, soil and water, modelling and prediction of radionuclides transport and transformation. This required the development of a computer system RECASS (RadioEcological Analysis Support System) which is currently being developed in SPA ''Typhoon''. The main tasks of RECASS are to integrate data on existing characteristics of the environment, and data on air, soil, water and biota-contamination with numerical models that account for radionuclide behaviour in all environmental media, and with radiation dose formations that are based on geographic information system (GIS) principles. The data bank of the system includes the following data bases: a data base with measurement of radioactive contamination levels in environmental media (soil, air, water); a meteorological data base; and a data base with administrative and demographic data. A set of models for radionuclide transfer in various environments incorporated in the chain permits short or long-term predictions to be made. The results of implementing RECASS to reconstruct the time and space picture of contamination in the first days after the Chernobyl accident are presented. (Author)

  8. 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)

  9. Consequences of Fukushima 11032011 - Radiological consequences from the nuclear accidents in Fukushima on 11 March 2011

    International Nuclear Information System (INIS)

    2011-12-01

    On 11 March 2011 at 14.46 the strongest earthquake ever recorded in Japan struck the Pacific coast in front of Fukushima. The earthquake and the following tsunami damaged the nuclear power plants in Fukushima Dai-ichi to such an extent that the Japanese government declared the state of catastrophic accident with degree 7 according to the International Nuclear and Radiological Event Scale (INES). At Fukushima Dai-ichi there were 6 boiling water reactors (BWR), a storage pool for spent fuel assemblies and a dry cask storage. 12 km apart at Fukushima Dai-ni there were 4 more BWR. At the moment of the earthquake the reactors 1 to 3 of Fukushima Dai-ichi, as well as the 4 reactors at Fukushima Dai-ni, were at full power, while the reactors 4 to 6 of Fukushima Dai-ichi were shut down for revision. From 12 March 2011 on, fairly large quantities of radioactive materials were released from Fukushima Dai-ichi reactors with meaningful consequences on the population in the near neighbourhood. The irradiation from the radioactivity bearing clouds, the ingestion and inhalation, and the deposit of radioactive materials on the ground threatened the population. The inhabitants of large areas had to be evacuated. Furthermore, radioactive materials contaminated the drinking water, the sea water and finally the plants and animals, i.e. the food chain of the people living there. The Swiss Federal Nuclear Safety Inspectorate (ENSI) continuously proceeded with the evaluation of the situation in Japan and a specialists' team made a detailed analysis of the accident, with emphasis on the human and organisational factors and on the lessons learned from this. The present report describes the present knowledge about the radiological consequences of the accident in Fukushima Dai-ichi on the population in the neighbourhood and on the staff at the power plant, until October 2011. First, the unrolling of the accident and its consequences on the plant site are analysed according to international

  10. Reconstructive dosimetry of radiological accidents - a brazilian case study of industrial gammagraphy

    International Nuclear Information System (INIS)

    Silva, Francisco Cesar Augusto da; Hunt, John G.; Ramalho, Adriana; Pinto, Livia M.F. Amalfi

    2001-01-01

    In may 2000, an operator of industrial gammagraphy, during a work of maintenance of a cobalt source irradiator, suffered a radiological accident which caused serious consequences for its left hand. Specialists who work in the Group of Overexposure Analysis (GADE/IRD/CNEN), began the reconstructive dosimetry for estimate the radiation dose. The objective was to determine the real dose received by the operator and to make possible the medical evaluation and to prescribe the medical procedures for the involved victim's treatment. This work presents the reconstructive dosimetry done by theoretical, experimental and computation methods for determining the radiation doses of the operator. Related to the computation method a program was used for external dose calculation based on Monte Carlo's Method and a human body simulator composed by voxels. It is also showed values of the effective and equivalent doses that caused serious lesions in the operator's hand. (author)

  11. Containment response and radiological release for a TMLB' accident sequence in a large dry containment

    International Nuclear Information System (INIS)

    Gasser, R.D.; Bieniarz, P.P.; Tills, J.L.

    1987-01-01

    An analysis has been performed for the Bellefonte Pressurized Water Reactor (PWR) Unit 1 to determine the containment loading and the radiological releases into the environment from a station blackout accident. A number of issues have been addressed in this analysis, which include the effects of direct heating on containment loading and the effects of fission product heating and natural convection on releases from the primary system. The results indicate that direct heating, which involves more than about 50% of the core, may fail the Bellefonte containment, but natural convection in the Reactor Coolant System (RCS) may lead to overheating and failure of the primary system piping before core slump, thus, eliminating or mitigating direct heating. Releases from the primary system are significantly increased before vessel breach, due to natural circulation, and after vessel breach, due to reevolution of retained fission products by fission product heating of RCS structures. (orig.)

  12. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    Energy Technology Data Exchange (ETDEWEB)

    Homma, Toshimitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Tomoyuki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Yonehara, Hidenori [National Inst. of Radiological Sciences, Chiba (Japan)] [eds.

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  13. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    International Nuclear Information System (INIS)

    Homma, Toshimitsu

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  14. Degraded core accidents for the Sizewell PWR A sensitivity analysis of the radiological consequences

    CERN Document Server

    Kelly, G N; Clarke, R H; Ferguson, L; Haywood, S M; Hemming, C R; Jones, J A

    1982-01-01

    The radiological impact of degraded core accidents postulated for the Sizewell PWR was assessed in an earlier study. In this report the sensitivity of the predicted consequences to variation in the values of a number of important parameters is investigated for one of the postulated accidental releases. The parameters subjected to sensitivity analyses are the dose-mortality relationship for bone marrow irradiation, the energy content of the release, the warning time before the release to the environment, and the dry deposition velocity for airborne material. These parameters were identified as among the more important in determining the uncertainty in the results obtained in the initial study. With a few exceptions the predicted consequences were found to be not very sensitive to the parameter values investigated, the range of variation in the consequences for the limiting values of each parameter rarely exceeded a factor of a few and in many cases was considerably less. The conclusions reached are, however, p...

  15. Reconstructive dosimetry of radiological accidents - study of a brazilian case of industrial gamma radiography

    International Nuclear Information System (INIS)

    Silva, Francisco Cesar Augusto da; Hunt, John G.; Ramalho, Adriana; Pinto, Livia M.F. Amalfi

    2002-01-01

    On May 2000, an industrial gamma radiography operator, during a maintenance work of a 60 Co irradiator, has suffered a radiological accident with severe consequences to the left hand. The experts of the High Doses Analysis Group (GADE/IRD/CNEN) initiated the reconstructive dosimetry for the radiation dose estimation, in order to determine the real dose received by the operator, and to help the medical evaluation for prescribing the medical procedures for treatment of the involved victim. This paper presents the reconstructive dosimetry performed through the determination of the radiation doses of the operator, based on theoretical, experimental and computational methods. For the computer methods, a program for the calculation of external doses were used, based on the Monte Carlo method, and a human body simulator composed by voxels. The values of effective and equivalent doses are also presented which has caused severe lesions on the operator hand

  16. Assessment of the radiological risks of road transport accidents involving Type A packages

    International Nuclear Information System (INIS)

    Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; S. Hughes, J.; B. Shaw, K.; Hedberg, B.; Simenstad, P.; Svahn, B.; Heinen, J.F.A. van; Jansma, R.

    2001-01-01

    An assessment and evaluation of the potential radiological risks of transport accidents involving Type A package shipments by road have been performed by five EU Member States, France, Germany, Sweden, The Netherlands, and the UK. The analysis involved collection and analysis of information on a national basis related to the type, volume, and characteristics of Type A package consignments, the associated radioactive traffic, and the expected frequency and consequences of potential vehicular road transport accidents. It was found that the majority of Type A packaged radioactive material shipments by road is related to applications of non-special form radioactive material, i.e. radiopharmaceuticals, radiochemicals etc., in medicine, research, and industry and special form material contained in radiography and other radiation sources, e.g. gauging equipment. The annual volumes of Type A package shipments of radiopharmaceuticals and radiochemicals by road differ considerably between the participating EU Member States from about 12,000 Type A packages in Sweden to about 240,000 in the Netherlands. The broad range reflects to a large extent the supply of radioactive material for the national populations and the production and distribution operations prevailing in the participating EU Member States (some are producer countries, others are not!). Very few standard package designs weighing from about 1-25 kg are predominant in Type A package shipments in all participating countries. Type A packages contain typically a range of radioactivity from a few mega becquerels to a few tens of giga becquerels, the average package activity contents is in terms of fractions of A 2 about 0.01, i.e. about one hundredth of a Type A package contents limits. Based on a probabilistic risk assessment method it has been concluded that the expected frequencies of occurrence of vehicular road transport accidents with the potential to result in an environmental release - including radiologically

  17. Research and managing institutions in Ukraine concerning the radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Nasvit, O.

    1998-01-01

    The paper presents temporal changes of the national organizations in managing the Chernobyl accident and its activities. The National Academy of Sciences of Ukraine started its activity from the first days after the accident. In 1990 a special executive body, the State committee of Chernobyl Affairs was established in Ukraine to manage the whole activity to overcome the Chernobyl problems. In 1991 it was rearranged into the Ministry of Chernobyl Affairs. In 1996 a new Ministry of Ukraine on Emergences and Affairs of Population Protection from the Consequences of Chernobyl Catastrophe(MEA) was founded on the basis of the Min. Chernobyl and Headquarters Staff of Civil Defence. The National Commission on Radiological Protection of Ukraine (NCRPU) belongs to the Parliament structure. NCRPU is responsible for approval of radiological safety standards and derived regulations. Very often the regulation approved are stricter than the international recommendations. There is an essential lack of attention within the Parliament to the activity of NCRPU. Ministry of Health is responsible for all kinds of medical care for the people suffering from the Chernobyl Catastrophe. In order to provide permanent medical service, a nation-wide scheme has been worked out. Scientific Center for Radiation Medicine is the leading scientific institute of the Academy of Medical Sciences. The State scientific Center of Environmental Radio geochemistry was created in 1996 on the basis of the two departments of the Institute of Geochemistry. The Center was created in order to improve coordination and managing of scientific researches on the behavior of artificial and natural radionuclides and chemical substances in the environment etc.. The Chernobyl Scientific-Technical center for International Research was created in March,1996. The Ukrainian Scientific Hygienic Center of Ministry of Health was created in 1989 and included two institutions. The subjects, the direction of research works

  18. Rade-aid a decision support system to evaluate countermeasures after a radiological accident

    International Nuclear Information System (INIS)

    Wagenaar, G.; Van Den Bosch, C.J.H.; Weger, D. de.

    1990-01-01

    After Chernobyl the authorities in many countries were overwhelmed by the enormous amount of information that was being generated by measuring and monitoring programs. In making decisions, this information had to be combined with the results of specific countermeasures, in order to determine the optimal strategy with respect to a large number of consequences. The development of RADE-AID, the Radiological Accident Decision AIDing system, is aimed at providing a powerful tool in the decision-making process. RADE-AID is developed by TNO (The Netherlands) in a joint contract with KfK (FRG) and NRPB (UK). In the first phase a demonstration system will be built, called RADE-AID/D. RADE-AID/D will be used as a decision support system in the intermediate and late phase after a radiological accident. RADE-AID/D will consider countermeasures with respect to external exposure and internal exposure by food ingestion. Countermeasures are evaluated considering reduction in doses and in numbers of health effects, costs, and social effects. The paper covers the structure of the program, presentation of data and results, and the decision analysis technique that is being used. This decision analysis part is an important feature of the system; an advanced decision analysis technique is used, that is able to compare data of varying nature. Furthermore the place of RADE-AID in the decision-making process will be treated. RADE-AID/D is an interactive computer program, that offers the user the possibility to enter relevant data and to have data and results displayed in a variety of ways. Furthermore the system contains an advanced decision analysis technique, that is able to compare data of varying nature. Input data for the decision analysis calculations are provided by models from UFOMOD and MARC-codes

  19. Convention on early notification of a nuclear accident. Convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1990-08-01

    The document refers to the Convention on Early Notification of a Nuclear Accident (IAEA-INFCIRC-335) and to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (IAEA-INFCIRC-336). Part I contains reservations/declarations made upon or following signature and Part II contains reservations/declarations made upon or following deposit of instrument expressing consent to be bound. The status of signature, ratification, acceptance, approval or accession by States or organizations as of 31 July 1990 is presented in two attachments

  20. Convention on early notification of a nuclear accident. Convention on assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1989-08-01

    The document refers to the Convention on early notification of a nuclear accident (INFCIRC-335) and to the Convention on assistance in the case of a nuclear accident or radiological emergency (INFCIRC-336). Part I contains reservations/declarations made upon or following signature and Part II contains reservations/declarations made upon or following deposit of instrument expressing consent to be bound. The status of signature, ratification, acceptance, approval or accession by States or organizations as of 31 July 1989 for the conventions is presented in two attachments

  1. The role of radiology and its pattern in road traffic accidents in Khartoum state

    Energy Technology Data Exchange (ETDEWEB)

    Ibrahim, Khalid Bakri [Faculty of medicine, University of Khartoum, Khartoum (Sudan)

    1998-09-01

    This hospital based study was undertaken to report on the role of radiology and its pattern in road traffic accident. It is a prospective study of 400 patients with R.T. injuries presenting to Khartoum teaching hospital during the first six months of 1998 during the first shift. The affected age group was between (20-50) years and the great majority of them were males (305) (76%). The pedestrians were (109) represent (27.25%) of cases. The commonest causative factor of injury with lower extremities (281) (70.4%), and the commonest causative factor of injury was vehicle pick up (24) represent (37.5%). Multiple injuries (147) (36%) were mostly seen in pedestrians. The injuries of the skull were (69) (17.3%), upper extremities (140) (35%), chest (42) (10.5%), abdomen and spine (20) (5%each) and pelvis (5 patients) represent (1.25%). Plain radiography done to all of the patients (100%). U/S was required in 20 patients (5%) and C.T. was also required in 13 patients (3.3%). I.V.U. urethrogram and Ba examinations were carried out in selective cases. MRI and others radiological modalities were not done in this study. Chronic osteomyelitis was developed in (3 patients) (0.75%), amputation was carried out in (5 patients) (1.25%)

  2. Model to predict radiological consequences of transportation accidents involving dispersal of radioactive material in urban areas

    International Nuclear Information System (INIS)

    Taylor, J.M.; Daniel, S.L.

    1978-01-01

    The analysis of accidental releases of radioactive material which may result from transportation accidents in high-density urban areas is influenced by several urban characteristics which make computer simulation the calculational method of choice. These urban features fall into four categories. Each of these categories contains time- and location-dependent parameters which must be coupled to the actual time and location of the release in the calculation of the anticipated radiological consequences. Due to the large number of dependent parameters a computer model, METRAN, has been developed to quantify these radiological consequences. Rather than attempt to describe an urban area as a single entity, a specific urban area is subdivided into a set of cells of fixed size to permit more detailed characterization. Initially, the study area is subdivided into a set of 2-dimensional cells. A uniform set of time-dependent physical characteristics which describe the land use, population distribution, traffic density, etc., within that cell are then computed from various data sources. The METRAN code incorporates several details of urban areas. A principal limitation of the analysis is the limited availability of accurate information to use as input data. Although the code was originally developed to analyze dispersal of radioactive material, it is currently being evaluated for use in analyzing the effects of dispersal of other hazardous materials in both urban and rural areas

  3. The role of radiology and its pattern in road traffic accidents in Khartoum state

    International Nuclear Information System (INIS)

    Ibrahim, Khalid Bakri

    1998-09-01

    This hospital based study was undertaken to report on the role of radiology and its pattern in road traffic accident. It is a prospective study of 400 patients with R.T. injuries presenting to Khartoum teaching hospital during the first six months of 1998 during the first shift. The affected age group was between (20-50) years and the great majority of them were males (305) (76%). The pedestrians were (109) represent (27.25%) of cases. The commonest causative factor of injury with lower extremities (281) (70.4%), and the commonest causative factor of injury was vehicle pick up (24) represent (37.5%). Multiple injuries (147) (36%) were mostly seen in pedestrians. The injuries of the skull were (69) (17.3%), upper extremities (140) (35%), chest (42) (10.5%), abdomen and spine (20) (5% each) and pelvis (5 patients) represent (1.25%). Plain radiography done to all of the patients (100%). U/S was required in 20 patients (5%) and C.T. was also required in 13 patients (3.3%). I.V.U. urethrogram and Ba examinations were carried out in selective cases. MRI and others radiological modalities were not done in this study. Chronic osteomyelitis was developed in (3 patients) (0.75%), amputation was carried out in (5 patients) (1.25%)

  4. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Elder, J.; Graf, J.M.

    1984-01-01

    DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

  5. A dynamic food-chain model and program for predicting the radiological consequences of nuclear accident

    International Nuclear Information System (INIS)

    Hu Erbang; Gao Zhanrong; Zhang Heyuan; Wei Weiqiang

    1996-12-01

    A dynamic food-chain model and program, DYFOM-95, for predicting the radiological consequences of nuclear accident has been developed, which is not only suitable to the West food-chain but also to Chinese food chain. The following processes, caused by accident release which will make an impact on radionuclide concentration in the edible parts of vegetable are considered: dry and wet deposition interception and initial retention, translocation, percolation, root uptake and tillage. Activity intake rate of animals, effects of processing and activity intake of human through ingestion pathway are also considered in calculations. The effects of leaf area index LAI of vegetable are considered in dry deposition model. A method for calculating the contribution of rain with different period and different intensity to total wet deposition is established. The program contains 1 main code and 5 sub-codes to calculate dry and wet deposition on surface of vegetable and soil, translocation of nuclides in vegetable, nuclide concentration in the edible parts of vegetable and in animal products and activity intake of human and so on. (24 refs., 9 figs., 11 tabs.)

  6. Action to be taken in the event of a radiological accident

    International Nuclear Information System (INIS)

    Bresson, G.; Nenot, J.C.

    1977-01-01

    In the event of a radiological accident affecting people, the measures that have to be taken are the responsibility of a large number of persons whose original disciplines differ widely. In the interest of efficiency, it is obviously essential that these measures should be co-ordinated; this implies smoothly functioning liaison between the persons responsible for action at different levels. These levels of action are numerous and differ very considerably; they include, in the first place, the links between the nuclear facility and the medical authorities, either directly within the hospital framework or through the intermediary of an industrial medicine service; then the links between the hospital sector and the large number of experts concerned with the highly specialized aspects of the diagnostic, therapeutic and prognostic problems of irradiation or contamination by radioisotopes; lastly, the links between these various specialists. In view of the wide variety of the parameters involved in accidents, the organization of the action to be taken cannot be encompassed within a rigid framework, especially as it should be possible to apply this organization at both the national and the international level, taking into account the diversity of the medico-legal aspects. The efficiency of the means applied is therefore governed by the flexibility of the procedure; however, the relative scarcity of accidents, i.e. the absence of any involvement of persons and equipment on a true scale, makes it imperative that a high degree of precision be applied in preparing emergency plans, since the omission of one step or one link may have serious or irreparable consequences which cannot always be offset by improvization. The outline of such an operational organization is presented and discussed in the light of past experience. (author)

  7. The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences

    International Nuclear Information System (INIS)

    2015-08-01

    description of the main aspects of radiation protection related to the accident at the Fukushima Daiichi NPP. Section 4.4 presents a review of post-accident studies of the health of members of the public and workers, including the possible radiation induced health effects and psychological consequences to individuals resulting from the accident. Section 4.5 covers the impact of the radioactive releases from the Fukushima Daiichi NPP on the environment (more specifically on non-human biota). The International Commission on Radiological Protection (ICRP) methodology has been applied to estimate dose and effects to a range of reference animals and plants from the marine, terrestrial and freshwater environments. There are 2 appendices and 12 annexes that provide supplementary information. Appendix I contains maps of levels of radioactivity and radionuclides in the environment. Appendix II provides details of a statistical analysis of individual dose data. The annexes are included on the CD-ROM attached to this volume and provide the following information: – Annex I: Characteristics and measurement of radioactivity and radiation levels. – Annex II: Local and regional meteorological conditions in east Japan during 11–23 March 2011. – Annex III: Levels of radioactivity in the terrestrial environment. – Annex IV: Radioactivity in the marine environment arising from releases following the Fukushima Daiichi accident. – Annex V: UNSCEAR assessment of the dose to the public

  8. Study on Generic Intervention Levels for Protecting the Public in a Nuclear Accident or Radiological Emergency

    International Nuclear Information System (INIS)

    Suzuki, E. F.; Sordi, G. M. A. A.; Rodrigues, D. L.

    2004-01-01

    Large amounts of radioactive material can be released to the environment in a nuclear accident or radiological emergency. In these cases, social and economical factors should be considered in the actions for protecting the public and to recover the environment, as these actions may affect not only the exposed individuals but also the society as a whole, because of the social impact and high costs. In 1994, the International Atomic Energy Agency, IAEA, published the radiological protection principles for intervention criteria in accident situations involving radioactive materials, as well as numeric values for the generic intervention levels, GIL, for the main countermeasures for protecting the public. These GIL values were selected to achieve broadly the maximum net benefit in many accident situations and, nowadays, those principles still represent the international consensus about this matter. On the other hand, the economic differences between countries can lead the optimization process to get GIL values that are quite different from those recommended. In this context, the monetary value of unit collective averted dose, called alpha-value, is a key element for the determination of the GIL. In this work, the method recommended by the IAEA, based on the human capital approach, was used to estimate the alpha-value for Brazil and the value of US$ 3268 per person-sievert was obtained, considering the year 2000 prices. The per capita costs of the countermeasures for protecting the public, as sheltering, evacuation, temporary relocation and permanent resettlement, were estimated and the cost-benefit analysis technique was applied to estimate the respective GIL applicable in the country. Some of the results for the GILs were smaller than those internationally recommended, even the alpha-value being about six times lower than the alpha-value considered by the IAEA. These results were discussed and they were also compared to values estimated by a similar study accomplished

  9. Study of application of protective measures for the public and remediation of contaminated areas in case of nuclear and / or radiological accidents in Brazil; Estudo da aplicacao de medidas de protecao para o publico e de remediacao de areas contaminadas em caso de acidentes nucleares e/ou radiologicos no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2011-07-01

    Since the radiological accident in Goiania in 1987, the IRD (Institute of Radiological Protection and Dosimetry - IRD / CNEN) has been developing tools to support decision-making processes after a nuclear or radiological accident which leads to an environmental contamination and to an exposure of individuals the public These processes include the establishment of a supporting multicriteria model, which involves the application of protective and remediation measures of contaminated areas in tropical environments. In this study, it was performed an evaluation of the efficiency of these measures in order to determine the consequences of their implementation, based on results obtained from the code SIEM (Emergency Integrated System), which constitutes an environmental mode1 developed at IRD to simulate this type of accident. In order to perform this evaluation, it was first developed a database containing descriptions of various protection/remediation measures, which could be applied nationwide. Afterwards, some basic scenarios were established, considering the environmental, housing and food characteristics of the population of the vicinity of the nuclear power plants in Angra dos Reis (state of Rio de Janeiro). Thus, the accident simulations were carried out separately containing releases of {sup 137}Cs, {sup 90}Sr and 131 I. The results showed that the dose reduction varies according to the extent and the timing of the remediation measure applied. Although it is possible to establish some basic guidelines, generic solutions are not recommended, since the resulting doses are highly dependent on the actual situation. Any decision-making process should be made case by case, according to the actual conditions of the affected area and to the occupation characteristics and use of the affected areas, considering the characteristics of the source term of contamination, the time of the year in which the accident occurs, the local agricultural practices and food habits of

  10. Proposed classification scale for radiological incidents and accidents; Elaboration d'une echelle de classement des incidents et accidents radiologiques

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-04-15

    The scale proposed in this report is intended to facilitate communication concerning the severity of incidents and accidents involving the exposure of human beings to ionising radiations. Like the INES, it comprises eight levels of severity and uses the same terms (accident, incident, anomaly, serious and major) for keeping the public and the media informed. In a radiological protection context, the severity of an event is considered as being directly proportional to the risk run by an individual (the probability of developing fatal or non-fatal health effects) following exposure to ionising radiation in an incident or accident situation. However for society, other factors have to be taken into account to determine severity. The severity scale proposed is therefore based on assessment of the individual radiological risk. A severity level corresponding to exposure of a member of the public in an incident or accident situation is determined on the basis of risk assessment concepts and methods derived from international consensus on dose/effect relationships for both stochastic and deterministic effects. The severity of all the possible exposure situations - worker exposure, collective exposure, potential exposure - is determined using a system of weighting in relation to situations involving members of the public. In the case of this scale, to indicate the severity of an event, it is proposed to make use of the most penalizing level of severity, comparing: - the severity associated with the probability of occurrence of deterministic effects and the severity associated with the probability of occurrence of stochastic effects, when the event gives rise to both types of risk; - the severity for members of the public and the severity for exposed workers, when both categories of individuals are involved; - the severity on the proposed radiological protection scale and that obtained using the INES, when radiological protection and nuclear safety aspects are associated with

  11. Radioprotection program to attend of radiation accidents

    International Nuclear Information System (INIS)

    Fajardo, P.W.; Costa Silva, L.H. da; Rosa, R.

    1989-04-01

    The aspects of a radioprotection program to be implanted in hospitals to cases of medical treatment to external and internal contamined people are presented. It is based in the experience acquired in the coordination of radioprotection of the Marcilio Dias Naval Medical Center, Rio de Janeiro, due to accident happened in Goiania in 1987. The infra-structure necessary of a ward and the procedures of radioprotection to acess control, entrance and way out of material area and patients monitoring, decontamination and the activities in the support area such as the control and maintenance of detection equipments and radioactive waste management are described. The radiologic protection materials necessaries and the quantity of radioactive waste generated by patient for day are estimated. (V.R.B.)

  12. Research on classification of nuclear and radiological accident from IAEA threat category with estimation of INES scale

    International Nuclear Information System (INIS)

    Cha, Seok Ki; Kim, Siu

    2017-01-01

    As there is increasing use of nuclear energy and radiation while information on nuclear related accidents are accumulated, international interest in nuclear and radiation incidents is increasing rapidly. Because of the specificity of nuclear energy and radiation, the damage caused by such accidents will be spread to the larger area around the accident point due to the radiation and cause biological damage and mental-psychological damage. The purpose of this study is to categorize historical incidents using the Threat Category concept described in the publication of IAEA Safety Guide GS-G-2.1. In addition to categorizing actual events and accidents into Threat Categories, causes of occurrences, the type of radioactive source which leads to the main threats, the type of radiation exposure, and the type of patient are organized in detail. As a result of the analysis of representative historical cases, most accident cases caused by 'Nuclear Energy-Related Business Operator' correspond to 1 (Anomaly) ~ 4 (Accident with Local Consequences) in the INES Scale by IAEA. From the some accident cases, while the radiological damage can be seen to be local, but it can be seen that the possibility of 6 (Serious Accident) can not be absolutely excluded.

  13. Research on classification of nuclear and radiological accident from IAEA threat category with estimation of INES scale

    Energy Technology Data Exchange (ETDEWEB)

    Cha, Seok Ki [Dept. of Nuclear engineering, Univ of SeJong, Seoul (Korea, Republic of); Kim, Siu [Korea Nuclear International Cooperation Foundation, Daejeon (Korea, Republic of)

    2017-04-15

    As there is increasing use of nuclear energy and radiation while information on nuclear related accidents are accumulated, international interest in nuclear and radiation incidents is increasing rapidly. Because of the specificity of nuclear energy and radiation, the damage caused by such accidents will be spread to the larger area around the accident point due to the radiation and cause biological damage and mental-psychological damage. The purpose of this study is to categorize historical incidents using the Threat Category concept described in the publication of IAEA Safety Guide GS-G-2.1. In addition to categorizing actual events and accidents into Threat Categories, causes of occurrences, the type of radioactive source which leads to the main threats, the type of radiation exposure, and the type of patient are organized in detail. As a result of the analysis of representative historical cases, most accident cases caused by 'Nuclear Energy-Related Business Operator' correspond to 1 (Anomaly) ~ 4 (Accident with Local Consequences) in the INES Scale by IAEA. From the some accident cases, while the radiological damage can be seen to be local, but it can be seen that the possibility of 6 (Serious Accident) can not be absolutely excluded.

  14. Analysis of body surface radiological contamination for inbound people from Japan to China during the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Yuan Long; Ma Weidong; Lei Cuiping; Chen Huifang; Li Yuwen; Liu Ying

    2012-01-01

    Objective: To investigate the radiological contamination of body surface for inbound people from Japan to China during Fukushima nuclear accident. Methods: According to The guidance for radiological contamination management for body surface issued by Chinese Center for Disease Control and Prevention, for people evacuated from Japan, the body surface monitoring of radiological contamination was performed by the related agencies in main provinces and cities in China. The monitoring data were collected, analyzed and reported to Ministry of Health. Results: A total of 432 persons were checked. The monitoring results of 429 cases were close to the background level, while those of three persons were higher than the background level. Conclusions: In general,the detected results were as low as the background level. The radiological contamination monitoring of body surface for people from Japan could provide scientific data to relax the horror and panic among them. (authors)

  15. Main radiation protection actions for medical personnel as primary responders front of an event with radiological dispersive device

    International Nuclear Information System (INIS)

    Duque, Hildanielle Ramos

    2015-01-01

    After the terrorist attack in New York, USA, in 2001, there was a worldwide concern about possible attacks using radioactive material in conventional detonators, called as Radiological Dispersal Device (RDD) or 'dirty bomb'. Several studies have been and are being made to form a global knowledge about this type of event. As until now, fortunately, there has not been an event with RDD, the Goiania Radiological Accident in Brazil, 1987, is used as a reference for decision-making. Several teams with technical experts should act in an event with RDD, but the medical staffs who respond quickly to the event must be properly protected from the harmful effects of radiation. Based on the radiological protection experts performance during the Goiania accident and the knowledge from lessons learned of many radiological accidents worldwide, this work presents an adaptation of the radiation protection actions for an event with RDD that helps a medical team as primary responders. The following aspects are presented: the problem of radioactive contamination from the explosion of the device in underground environment, the actions of the first responders and evaluation of health radiation effects. This work was based on specialized articles and papers about radiological accidents and RDD; as well as personal communication and academic information of the Institute of Radiation Protection and Dosimetry. The radiation protection actions, adapted to a terrorist attack event with RDD, have as a scenario a subway station in the capital. The main results are: the use of the basic radiation protection principle of time because there is no condition to take care of a patient keeping distance or using a shielding; the use of full appropriate protection cloths for contaminating materials ensuring the physical safety of professionals, and the medical team monitoring at the end of a medical procedure, checking for surface contamination. The main conclusion is that all medical actions

  16. Radiological accidents potentially important to human health risk in the U.S. Department of Energy waste management program

    International Nuclear Information System (INIS)

    Mueller, C.; Roglans-Ribas, J.; Folga, S.; Nabelssi, B.; Jackson, R.

    1995-01-01

    Human health risks as a consequence of potential radiological releases resulting from plausible accident scenarios constitute an important consideration in the US Department of Energy (DOE) national program to manage the treatment, storage, and disposal of wastes. As part of this program, the Office of Environmental Management (EM) is currently preparing a Programmatic Environmental Impact Statement (PEIS) that evaluates the risks that could result from managing five different waste types. This paper (1) briefly reviews the overall approach used to assess process and facility accidents for the EM PEIS; (2) summarizes the key inventory, storage, and treatment characteristics of the various DOE waste types important to the selection of accidents; (3) discusses in detail the key assumptions in modeling risk-dominant accidents; and (4) relates comparative source term results and sensitivities

  17. Radiological and dosimetric consequences in case of nuclear accident: taking them into account within the security approach and protection challenges

    International Nuclear Information System (INIS)

    Cogez, E.; Herviou, K.; Isnard, O.; Cessac, B.; Reales, N.; Quentric, E.; Quelo, D.

    2010-01-01

    This report first proposes a presentation of the 'defence in depth' concept which comprises five as much as possible independent levels: preventing operation anomalies and system failures, maintaining the installation within the authorized domain, controlling accidents within design hypotheses, preventing the degradation of accidental conditions and limiting consequences of severe accidents, limiting radiological consequences for population in case of important releases. Then, after a description of a release atmospheric dispersion and of its consequences, this report describes the consequences of two accident scenarios. The first accident is a failure of steam generator tubes, and the second a loss of primary coolant. It notably indicates the main released radionuclides, exposure levels at different distance for a given set of dispersion conditions

  18. The radiological consequences of degraded core accidents for the Sizewell PWR The impact of adopting revised frequencies of occurrence

    CERN Document Server

    Kelly, G N

    1983-01-01

    The radiological consequences of degraded core accidents postulated for the Sizewell PWR were assessed in an earlier study and the results published in NRPB-R137. Further analyses have since been made by the Central Electricity Generating Board (CEGB) of degraded core accidents which have led to a revision of their predicted frequencies of occurrence. The implications of these revised frequencies, in terms of the risk to the public from degraded core accidents, are evaluated in this report. Increases, by factors typically within the range of about 1.5 to 7, are predicted in the consequences, compared with those estimated in the earlier study. However, the predicted risk from degraded core accidents, despite these increases, remains exceedingly small.

  19. Radiology

    International Nuclear Information System (INIS)

    Bigot, J.M.; Moreau, J.F.; Nahum, H.; Bellet, M.

    1990-01-01

    The 17th International Congress of Radiology was conducted in two separate scientific sessions, one for radiodiagnosis and one for radiation oncology. Topics covered are: Radiobiology -radioprotection; imaging and data processing; contrast media; MRI; nuclear medicine; radiology and disasters; radiology of tropical diseases; cardiovascular radiology; interventional radiology; imaging of trauma; imaging of chest, gastro-intestinal tract, breast and genito-urinary tract; imaging in gynecology;imaging in oncology; bone and joint radiology; head and neck-radiology; neuro-radiology. (H.W.). refs.; fig.; tabs

  20. An approach for estimating the radiological significance of a hypothetical major nuclear accident over long distance transboundary scales

    Energy Technology Data Exchange (ETDEWEB)

    Mitrakos, D., E-mail: dimitris.mitrakos@eeae.gr; Potiriadis, C.; Housiadas, C.

    2016-04-15

    Highlights: • Actions may be warranted after a major nuclear accident even at long distances. • Distance may not be the decisive parameter for longer term radiological impact. • Remote impact may vary orders of magnitude depending on the meteorological conditions. • The potential impact can be assessed using computationally inexpensive calculations. - Abstract: After the Fukushima accident important initiatives were taken in European level to enhance the nuclear safety level of the existing and planned nuclear reactors, such as the so-called nuclear “stress-tests” and the amendment of the Nuclear Safety Directive. A recent work of HERCA and WENRA focused on the need for a more consistent and harmonized response in a transboundary context in case of a hypothetical major nuclear accident in Europe. Such an accident, although very improbable, cannot be totally excluded and so, should be considered in emergency preparedness arrangements among the various European countries. In case of a hypothetical severe Fukushima-like accident in Europe, the role of the neighboring countries may be important, since the authorities should be able to provide information and advice to the government and the public, but also can contribute to the overall assessment of the situation be their own means. In this work we assess the radiological significance of a hypothetical major nuclear accident for distances longer than 300 km that are not typically covered by the internationally accepted emergency planning zones. The approach is simple and computationally inexpensive, since it is based on the calculation of only a few release scenarios at dates selected within a whole year on the basis of bounding the deposition levels at long distances in relation to the occurrence of precipitation. From the calculated results it is evident that distance is not the only decisive parameter in estimating the potential radiological significance of a severe nuclear accident. The hypothetical

  1. Experience in training of health personnel for response to radiological and nuclear accidents

    International Nuclear Information System (INIS)

    Maurmo, Alexandre M.; Leite, Teresa C.S.B.

    2013-01-01

    Eletronuclear Healthcare Foundation is the Institution responsible for the actions of health response involving ionizing radiation in the area of Nuclear Power Plant Almirante Alvaro Alberto in Angra dos Reis. Because of their specific assignments and references for being in training health manpower in the field of ionizing radiation developed a range of Training Courses for Professionals Area Health to prepare them for Response to Radiological and Nuclear Accidents. Modules are proposed specifically for the professional response of the Technical Level and Higher Level, the level Pre-hospital and hospital. These modules are further divided into specific levels or modules, Basic or Introductory, Intermediate and Advanced. Are applied pretests and post tests to monitor the content of fixing, maintaining a historical series of reviews. Your content is theoretical and practical applications developed in 30 to 48 hours, with simulations (drills) and distribution of educational materials. We already have more than 80 applications training, focusing on internal staff and external to the institution, developing interesting partner with the Armed Forces and Civil Defense. It still maintained a link on the institution seeking access and download over 400 titles on the subject and exchange of information and experiences. For improving the teaching material, the authors launched in 2011 the first manual in Portuguese on the subject with new revised edition in 2013: 'Manual of Medical Actions In Radiological Emergencies'. The results indicate increased knowledge and appropriateness of the themes and the strategy proposed for this activity, demonstrating yet passed that information can be multiplied and meets the growing demand of the country that has hosted and will host international events relevant at QBNRE risk. (author)

  2. Assessment of Radiological and Economic Consequences of a Hypothetical Accident for ETRR-2, Egypt Utilizing COSYMA Code

    International Nuclear Information System (INIS)

    Tawfik, F.S.; Abdel-Aal, M.M.

    2008-01-01

    A comprehensive probabilistic study of an accident consequence assessment (ACA) for loss of coolant accident (LOCA) has accomplished to the second research reactor ETRR-2, located at Inshas Nuclear Research Center, Cairo, Egypt. PC-COSYMA, developed with the support of European Commission, has adopted to assess the radiological and economic consequences of a proposed accident. The consequences of the accident evaluated in case of early and late effects. The effective doses and doses in different organs carried out with and without countermeasures. The force mentioned calculations were required the following studies: the core inventory due to the hypothetical accident, the physical parameters of the source term, the hourly basis meteorological parameters for one complete year, and the population distribution around the plant. The hourly stability conditions and height of atmospheric boundary layers (ABL) of the concerned site were calculated. The results showed that, the nuclides that have short half-lives (few days) give the highest air and ground concentrations after the accident than the others. The area around the reactor requires the early and late countermeasures action after the accident especially in the downwind sectors. Economically, the costs of emergency plan are effectively high in case of applying countermeasures but countermeasures reduce the risk effects

  3. Protocol for therapy of people who suffered wounds from radioactive material in radiological and nuclear accidents

    International Nuclear Information System (INIS)

    Lopes, Amanda Gomes

    2015-01-01

    The handling of glassware in ampoules, containing solution is very common in research or production laboratories. During manipulation, there is a likelihood of occurrence of incidents such as the breaking of ampoules or glass vials containing material in liquid or powdered form which may cause a wound to the possibility of contamination with handled material. When the solution is radioactive there is a concern due to the risk of incorporation of that material. According to NCRP 156, the scientific literature contains over 2100 cases of wounds contaminated with radionuclides and more than 90% of the reported cases occurred in the hands and arms, but mainly on the fingers. Despite having no cases of wounds reported radioactive material in Brazil or a protocol developed by the National Agencies, applications and hence the manipulation of radionuclides is increasing in the country, rising the possibility of wound occurrence contaminated by radionuclides. In this work was proposed a methodology for management of individuals who suffered wounds from radioactive material in cases of nuclear accidents and radiological emergencies that present intake, which consisted of four steps: definition of the accident scenario, individual triage of the public or workers, proper measurements with detectors PRD, IdentiFINDER2 and germanium in different thicknesses material tissue-equivalent, and later adoption of first aid measures consisting of attendance, monitoring of contaminated personnel, evaluation of effective dose and direct to specialized medical center. As an example of results it follows the case of 241 Am where the best performance was obtained by measurements with the shielded HPGe (7%) and the shielded and collimation of 0.5 cm IdentiFINDER2 (10%). While, unshielded PRD, unshielded or shielded side IdentiFINDER2 and unshielded TeCd showed performance ranging from 30 to 70%. In general, the uncertainties obtained had values below 1.5%. In this work a protocol for

  4. Radioactive waste management of the radiological accident in Goianaia, Brazil - Cooperation of Waste Treatment Division

    International Nuclear Information System (INIS)

    Guzella, M.F.R.; Miaw, S.T.W.; Reis, L.C.S.; Santos, P.O.; Silva, E.M.P.; Tello, C.C.O.

    1988-01-01

    Radioactive waste were generated in Goiania by an accidental breakage of Cesium 137 radiotherapie source (A=5,0 x 10 13 Bq) in September 1987. The Waste Treatment Division (DITRR.CN) CDTN/NUCLEBRAS has worked in all critical areas to remove the contamination and carried out the tasks at the interim storage. Experience on the waste management and the results from the R and D works conducted by the Division were applied. The R and D works conducted by the Division were applied. The R and D works conducted by the Division were applied. The R and D works comprise package for storage and transport of radioactive material, the use of selected bentonite for Cesium 137 retention, installation of waste treatment facilities and elaboration of several specific procedures. (author) [pt

  5. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

  6. Steering committee for the management of the post-accidental phase of a nuclear accident or of a radiological situation (CODIRPA) - Work-group nr 4. Response to health challenges after a radiological accident - Final report March 2011

    International Nuclear Information System (INIS)

    2011-03-01

    The first part of this report presents the context of preparation to the response to a radiological accident in France. It proposes a synthetic presentation of scenarios, of the different accident phases, of management principles based on areas and stakes as they are presented in the emergency phase exit guide. It also indicates public health challenges related to the different studied scenarios. The second part proposes a chronological synthesis of actions to be undertaken after an accident in order to face public health stakes. The third part proposes a detailed presentation of the implementation and sequence of actions to be undertaken depending on the studied scenarios: medical and psychological care, census, health risk assessment, health information

  7. Traumatology of the knee joint - radiological and accident surgery aspects. Pt. 1

    International Nuclear Information System (INIS)

    Schild, H.; Ahlers, J.; Mainz Univ.

    1987-01-01

    Lesions of the knee joint are relatively frequent and are on the increase due to the increasing number of sports and traffic accidents. Violent force exercised on the knee can lead basically to two different kinds of injury sequels. As a rule, injuries to the bone do not present diagnostic problems if there is a clear break in continuity. On the other hand, it is often very difficult to detect chondral or osteochondral lesions and also certain types of longitudinal patellar fractures and fractures of the head of the tibia. Their visualisation requires more far-reaching diagnostic measures. Fundamentally more difficult to identify: the second group of lesions, namely, those of the internal structures of the knee, unless there is a marked instability which is usually accessible to clinical examination. Relatively slight osseous tears or ruptures of a ligament often remain unnoticed on the plain X-ray film. Other diagnostic techniques are imperative in such cases. The first part deals specifically with the radiological aspects of knee injuries. The majority of injuries close to the knee region can be visualized by making use of all techniques of roentgenology. However, if the examination methods get too costly and complicated without ensuring an absolutely safe diagnosis other techniques must be employed. An example in this regard are the chondral or osteochondral lesions. It is here that arthroscopy often yields better results while offering at the same time a possibility to remove individual small fragments. (orig.) [de

  8. Radiological preparedness in the case of a terrorist attack or an accident

    International Nuclear Information System (INIS)

    Cizmek, A.

    2005-01-01

    During the Cold War, every information about weapons of mass destruction was treated as top secret, regardless of whether the information concerned friend or foe. The most serious threat in our post Cold War era are terrorist radiological dispersal devices. Dirty nukes are what you may choose to build if you're unable to create a real nuclear bomb, i.e. one whose explosion is based on a nuclear reaction. A dirty bomb is a conventional explosive salted with radioactive isotopes in order to spew out that nuclear material and contaminate a wide area. The military usefulness of such devices have always been in dispute. In fact, the TNT in such a bomb may still be more dangerous than the nuclear material. Its destructive power would really depend on the size of the conventional bomb, and the volume and nature of nuclear material. This paper addresses the possibilities of decontamination and preparedness in the case of a terrorist attack or accident.(author)

  9. Value of lymphocyte cryo-preservation after a radiological or nuclear accident

    International Nuclear Information System (INIS)

    Laroche, P.; Lataillade, J.J.; Chambrette, V.; Voisin, Ph.

    1997-01-01

    The conventional cytogenetic method in biological dosimetry is most useful for the estimation of the received radiation dose. It shows resulting unstable chromosomal aberrations (dicentrics, centric rings and fragments) in peripheral blood lymphocytes. This method has been used over the past 30 years and is used in forensic medicine. Nevertheless, it is long and fastidious. Accordingly, the number of simultaneous analyses of blood samples is limited and depends on the capacity of specialized laboratories. This capacity may be insufficient in the case of large scale radiological or nuclear accidents. Cryo-preservation is the usual method to store cells before analysis or use, for instance for biological dosimetry purposes. Some investigations have shown that thawing following freezing may induce cell injury but few studies have been made on the effect of cryo-preservation on cells containing radiation-induced unstable chromosomal aberrations. In this work, lymphocytes were irradiated with 1 to 4 Gy gamma rays and stored in liquid nitrogen. The dicentric and centric ring yields were analysed after storage periods of 1 week, 1 month, 3 months, and 1 year. No difference in aberration frequency from control, unfrozen samples was observed over this period. Lymphocytes stored at -196 deg C for up to least 1 year may therefore be used for chromosome aberration scoring when overexposure to ionizing radiation is suspected. (author)

  10. Urbapat: External exposure and countermeasures after a radiological accident in the urban environment

    International Nuclear Information System (INIS)

    Martin, J.E.; Gallego, E.

    1992-01-01

    URBAPAT (URBAN PATHWAY) is a computer model, written in FORTRAN 77, for the evaluation of the gamma external exposure, and the adequate countermeasures, after a radiological accident involving dispersion and deposition of radioactive material on different urban surfaces. The code estimates the evolution of radioactive material in the urban environment using a dynamic model consisting on 21 compartments, that simulate five different urban surfaces with their particular retention properties. For the assessment of the gamma external exposure in urban areas, one of then main contributors to the long-term individual dose, the model considers the contribution of each surface to the dose rate delivered by five radionuclides (Cs-137, Cs-134, I-131, Te-132, Ba-140) in different locations outside and inside three types of buildings (semi-detached houses, terrace houses and multi-stored buildings). The population is classified in various groups, attending to their stay time in each location. The model can evaluate the dose avoided by the introduction of countermeasures like decontamination of the urban surfaces or relocation. An assessment of their associated costs will permit to perform the needed cost-benefit analysis of the different countermeasures and alternatives, following IAEA and ICRP recommendations. The capability to perform sensitivity and uncertainty assessment of the more important parameters affecting the results obtained will also be included in the model. (Author)

  11. General situation of the radiological consequences of the Chernobyl accident in Ukraine

    International Nuclear Information System (INIS)

    Grodzinsky, D.M.

    1998-01-01

    Following the Chernobyl Nuclear Accident on April 26, 1986, epidemiological analyses of data point to impressive deterioration of the health of the people affected by radionuclide contamination in the environment. This deterioration of population health embraces a broad spectrum of diseases. Epidemiological prediction of the rate of thyroid cancer in children near Chernobyl seems strikingly compatible with a real increase. But there is a tendency to consider the morbidity augmentation as a result having been associated with the factors of non-radioactive origin (chemical compounds, heavy metals and mainly social-psychological syndrome development). The Chernobyl catastrophe has implied a heavy burden for Ukraine: pollution of air, water, soils and vegetation in all ecosystems, late radiological effects in the health of people, losses of arable land and forest, necessity of mass-evacuation from thousands of settlements in the contaminated regions, severe psychological shock for millions of people, and painful suffering of unexpected life tragedies. Eleven years after, this tragic event with its causes and consequence brings one to very important conclusions concerning moral aspects of human relations within the nuclear society, as well as interactions between the society and the environment. (J.P.N.)

  12. Assessment Of Source Term And Radiological Consequences For Design Basis Accident And Beyond Design Basis Accident Of The Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Luong Ba Vien; Le Vinh Vinh; Huynh Ton Nghiem; Nguyen Kien Cuong; Tran Tri Vien

    2011-01-01

    The paper presents results of the assessment of source terms and radiological consequences for the Design Basis Accident (DBA) and Beyond Design Basis Accident (BDBA) of the Dalat Nuclear Research Reactor. The dropping of one fuel assembly during fuel handling operation leading to the failure of fuel cladding and the release of fission products into the environment was selected as a DBA for the analysis. For the BDBA, the introduction of a step positive reactivity due to the falling of a heavy block from the rotating bridge crane in the reactor hall onto a part of the platform where are disposed the control rod drives is postulated. The result of the radiological consequence analyses shows that doses to members of the public are below annual dose limit for both DBA and BDBA events. However, doses from exposure to operating staff and experimenters working inside the reactor hall are predicted to be very high in case of BDBA and therefore the protective actions should be taken when the accident occurs. (author)

  13. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose.

  14. Potential radiological impacts of upper-bound operational accidents during proposed waste disposal alternatives for Hanford defense waste

    International Nuclear Information System (INIS)

    Mishima, J.; Sutter, S.L.; Hawley, K.A.; Jenkins, C.E.; Napier, B.A.

    1986-02-01

    The Geologic Disposal Alternative, the In-Place Stabilization and Disposal Alternative, and the Reference Disposal Alternative are being evaluated for disposal of Hanford defense high-level, transuranic, and tank wastes. Environmental impacts associated with disposal of these wastes according to the alternatives listed above include potential doses to the downwind population from operation during the application of the handling and processing techniques comprising each disposal alternative. Scenarios for operational accident and abnormal operational events are postulated, on the basis of the currently available information, for the application of the techniques employed for each waste class for each disposal alternative. From these scenarios, an upper-bound airborne release of radioactive material was postulated for each waste class and disposal alternative. Potential downwind radiologic impacts were calculated from these upper-bound events. In all three alternatives, the single postulated event with the largest calculated radiologic impact for any waste class is an explosion of a mixture of ferri/ferro cyanide precipitates during the mechanical retrieval or microwave drying of the salt cake in single shell waste tanks. The anticipated downwind dose (70-year dose commitment) to the maximally exposed individual is 3 rem with a total population dose of 7000 man-rem. The same individual would receive 7 rem from natural background radiation during the same time period, and the same population would receive 3,000,000 man-rem. Radiological impacts to the public from all other postulated accidents would be less than that from this accident; furthermore, the radiological impacts resulting from this accident would be less than one-half that from the natural background radiation dose

  15. Development of a national doctrine for the management of the post-accident phase of a radiological emergency situation

    International Nuclear Information System (INIS)

    Niel, J.Ch.; Godet, J.L.

    2008-01-01

    For several years, public Authorities have defined an organization for the management of emergency situations arising from an accident occurring at a nuclear installation. So far, the management of the risk arising from the post accident phase was, in itself, not explored with the same care. What so ever, no format policy on which the action of public Authority could be based is today available. The nuclear safety Authority (ASN), in relation with the other concerned departments, is now in charge, according to the above mentioned directive, to prepare and implement the necessary provisions to respond to a post accident situation. In dune 2005, ASN established the steering committee for the management of post nuclear or radiological emergency situations (CODIRPA). The definition of a national policy related to the management of the radiological risk during a post event situation having to integrate various organization aspects as: lifting of protection emergency provisions and rehabilitation of buildings, life in contaminated rural territories, agriculture and water, dose and radiological consequences, sanitary surveillance of victims and populations, indemnification, waste management of contaminated crops and soils, organization of public Authorities. During the 2. phase of CODIRPA work (2008-2009), the first elements of policy will be consolidated and new scenarios will be studied (one worsened scenario and one scenario with alpha emitting radionuclide). in parallel, a procedure for local actor's consultation should be elaborated. (authors)

  16. First aid for the public exposed to cesium 137 in Goiania

    International Nuclear Information System (INIS)

    Valverde, N.

    1986-01-01

    The criterias for triage and reference to a third-level center of individuals of the public exposed to sup(137)Cs, in Goiania, State of Goias, Brazil, are described. Triage was hindered by the lack of physical dosimeters, the characteristics of the place where the accident took place, the delay between the casualty and its recognition, cultural mishaps together with a sense of possible legal liability, making the delivered information suspicious and a strike affecting the hospital where the patients were admitted, as well as its sponsoring institution, that made laboratory assistance virtually not available. Triage was exclusively based upon the histories, prodomal manifestations and physical findings. (author)

  17. Research activity about the radiological consequences of the Chernobyl NPS accident and social activity to assist its sufferers

    International Nuclear Information System (INIS)

    Imanaka, Tetsuji; Koide, Hiroaki; Kobayashi, Keiji

    1998-01-01

    Due to the Chernobyl Accident in April 1986, a series of serious radiological consequences were brought in Ukraine, Belarus and Russia. The former Soviet Union and the authorities in the world such as IAEA, however, have been denying serious health consequences among the people around Chernobyl since the beginning of the accident. On the other hand, a lot of works indicating serious health effects of the accident have been reported by scientists in these affected countries although they are not well known in the western countries. Since 1993, under the research grant of the Toyota foundation, we have continued a cooperative program to investigate research activities in these countries about the Chernobyl accident and to look into data and information that were not known so far. The information concerning the social system and activity to assist the sufferers from the accident has been also overviewed, including legal aspects of the Chernobyl problem. Here we are presenting an outline of our cooperation activity and our work concerning dose estimation for the inhabitants around the Chernobyl NPS at the first stage after the accident. The results of our estimation suggest that at least several hundreds of inhabitants received radiation dose exceeding 1 Sv before their evacuation. The whole reports of our cooperation program will be published in English and in Japanese in the next year. (author)

  18. Assumptions used for evaluating the potential radiological consequences of a less of coolant accident for pressurized water reactors - June 1974

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a pressurized water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will be considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

  19. Assumptions used for evaluating the potential radiological consequences of a loss of coolant accident for boiling water reactors - June 1974

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a pressurized water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will be considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

  20. Development of an anthropomorphic model and a Monte Carlo calculation code devoted to the physical reconstruction of a radiological accident

    International Nuclear Information System (INIS)

    Roux, A.

    2001-01-01

    The diversity of radiological accidents makes difficult the medical prognosis and the therapy choice from only clinical observations. To complete this information, it is important to know the global dose received by the organism and the dose distributions in depth in tissues. The dose estimation can be made by a physical reconstruction of the accident with the help of tools based on experimental techniques or on calculation. The software of the geometry construction (M.G.E.D.), associated to the Monte-Carlo code of photons and neutrons transport (M.O.R.S.E.) replies these constraints. An important result of this work is to determine the principal parameters to know in function of the accident type, as well as the precision level required for these parameters. (N.C.)

  1. HYSPLIT's Capability for Radiological Aerial Monitoring in Nuclear Emergencies: Model Validation and Assessment on the Chernobyl Accident

    International Nuclear Information System (INIS)

    Jung, Gunhyo; Kim, Juyoul; Shin, Hyeongki

    2007-01-01

    The Chernobyl accident took place on 25 April 1986 in Ukraine. Consequently large amount of radionuclides were released into the atmosphere. The release was a widespread distribution of radioactivity throughout the northern hemisphere, mainly across Europe. A total of 31 persons died as a consequence of the accident, and about 140 persons suffered various degrees of radiation sickness and health impairment in the acute health impact. The possible increase of cancer incidence has been a real and significant increase of carcinomas of the thyroid among the children living in the contaminated regions as the late health effects. Recently, a variety of atmospheric dispersion models have been developed and used around the world. Among them, HYSPLIT (HYbrid Single-Particle Lagrangian Integrated Trajectory) model developed by NOAA (National Oceanic and Atmospheric Administration)/ARL (Air Resources Laboratory) is being widely used. To verify the HYSPLIT model for radiological aerial monitoring in nuclear emergencies, a case study on the Chernobyl accident is performed

  2. Build-up forces at Military Institute of Medical Radiology and Oncology for emergency medical response to some eventualities of radiological accidents - some suggestions

    International Nuclear Information System (INIS)

    Ho Van Cu; Nguyen Huu Nghia

    2011-01-01

    Nowadays, the use of various nuclear sources in some fields of the life has brought many practical advantages in general; especially in the next several years, our country will begin construction of the first nuclear plant. However, if there were user carelessness or objective disadvantageous factors (earthquake, tsunami, etc.), that disadvantages could lead to a radiation accident or nuclear accident which causes damages not only for economy but also for public health. Therefore, the emergency response to radiation accident, especially the emergency medical response that has a great important position. To satisfy this real demand, in 1996, Vietnam Ministry of Defence made the decision to establish Center for Nuclear Medicine and Radiation Protecting (now becomes Military Institute of Medical Radiology and Oncology) with the main missions are research, applying radiation protecting methods and organizing treatments to radiation injured victims. To fulfill above main missions, with the help of Vietnam Atomic Energy Institute (VAEI), Vietnam Agency for Radiation and Nuclear Safety (VARANS), the doctors and staffs of our Institute have been participated in the international training courses and workshops that organized in Vietnam or in regional countries about emergency medical response to radiation accidents, they get valuable information, knowledge and documents from these courses and workshops. Depending on the principles of radiation emergency medical response to nuclear/ radiation accidents that International Atomic Energy Agency (IAEA) guided, and with the experience learned from other countries in Asia region, our Institute have been gradually improving on organization and curing processes for the radiation victims and also setting the preparedness for emergency medical response to radiation accidents if maybe they could occur. (author)

  3. Convention of early notification of a nuclear accident. Convention of assistance in the case of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1988-05-01

    The document refers to the Convention on early notification of a nuclear accident (INFCIRC-335) and to the Convention on assistance in the case of a nuclear accident or radiological emergency (INFCIRC-336). Part I of the document contains reservations/declarations made upon or following signature made by Algeria, Iraq and Thailand. Part II contains reservations/declarations made upon or following deposit of instrument expressing consent to be bound made by Australia, Bulgaria, China, India, Japan, Malaysia, Mongolia, Poland, South Africa, United Arab Emirates and Socialist Republic of Viet Nam. The status of signature, notification, acceptance, approval or accession of the two conventions as of 13 May 1988 is presented in two attachments

  4. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

    This is a report describing diagnostic techniques used in radiology. It describes the equipment necessary for, and the operation of a radiological department. Also is described the standard methods used in radiodiagnosis. (K.A.E.)

  5. Radiological impact assessment for a severe accident scenario for a CANDU 6 type NPP

    International Nuclear Information System (INIS)

    Penescu, Maria; Mehedinteanu, Stefan; Cruceanu, Amalia; Ispas, Georgeta

    2004-01-01

    There are two main categories of consequences of accidental activity releases, which involve radiological considerations. First, there is the health detriment in the exposed population and its descendants; secondly, there is the economic and social impact from the restrictions generated by the control of that population exposure. A variety of health effects may be predicted to occur in an exposed population, depending on the magnitude and distribution of the exposure. Early effects include both death and varying degrees of health impairment, but these are likely to occur only following extremely large activity releases. The major late effects are cancer, both fatal and nonfatal, in the exposed population and heredity effects in their descendants. A variety of radiological endpoints can be calculated to provide a measure of the overall impact. Those, which are considered to be most useful in context of, risk analysis and in the analyses of siting, emergency planning and design criteria can be summarized as: - the incidence of particular health effects in the exposed population and its descendants; - the number of people who may be affected by the application of the countermeasures; - the areas of land beyond particular levels, especially those in which restrictions may be needed with respect of their use or on foodstuffs derived from them; - the economic cost of introducing countermeasures, particularly restrictions on the use of contaminated land and property. A number of countermeasures could be introduced to reduce doses following an accidental release. Such measures are the evacuation and relocation of population and the banning of contaminated food consumption. Sheltering before evacuation is also considered. The criteria for taking the decision to evacuate are based on the total dose and dose for each organ resulted from the exposure to the plume and inhalation, while the criterion for relocation is based simply on the external dose from deposited activity

  6. Covering techniques for severe burn treatment: lessons for radiological burn accidents

    International Nuclear Information System (INIS)

    Carsin, H.; Stephanazzi, J.; Lambert, F.; Curet, P.M.; Gourmelon, P.

    2002-01-01

    Covering techniques for severe burn treatment: lessons for radiological burn accidents. After a severe burn, the injured person is weakened by a risk of infection and a general inflammation. The necrotic tissues have to be removed because they are toxic for the organism. The injured person also needs to be covered by a cutaneous envelope, which has to be done by a treatment centre for burned people. The different techniques are the following: - auto grafts on limited burned areas; - cutaneous substitutes to cover temporary extended burned areas. Among them: natural substitutes like xenografts (pork skin, sheep skin,..) or allografts (human skin), - treated natural substitutes which only maintain the extracellular matrix. Artificial skins belong to this category and allow the development of high quality scars, - cell cultures in the laboratory: multiplying the individual cells and grafting them onto the patient. This technique is not common but allows one to heal severely injured patients. X-ray burns are still a problem. Their characteristics are analysed: intensive, permanent, antalgic resistant pain. They are difficult to compare with heat burns. In spite of a small number of known cases, we can give some comments and guidance on radio necrosis cures: the importance of the patients comfort, of ending the pain, of preventing infection, and nutritional balance. At the level of epidermic inflammation and phlyctena (skin blisters), the treatment may be completed by the use of growth factors. At the level of necrosis, after a temporary cover, an auto graft can be considered only if a healthy basis is guaranteed. The use of cellular cultures in order to obtain harmonious growth factors can be argued. (author)

  7. Physical reconstruction of the radiological accident of Chilca (Lima - Peru); Reconstruccion fisica del accidente radiologico de Chilca (Lima - Peru)

    Energy Technology Data Exchange (ETDEWEB)

    Lachos, A. [Instituto Nacional de Enfermedades Neoplasicas, Departamento de Radioterapia, Av. Angamos Este 2520, Surquillo, Lima (Peru); Marquez, J. F., E-mail: alachosd1271@yahoo.com [Univesidad Nacional Mayor de San Marcos, Facultad de Ciencias Fisicas, C. German Amezaga 375, Ciudad Univesitaria, Lima (Peru)

    2014-08-15

    The radiological accident happened in the Chilca District, the Canete County at 60 km to the south of Lima-Peru, during the night of January 11 to 12, 2012. The physical reconstruction of the accident was carried out in January 21, 2012, by means of the information gathering administrative and technical of the radioactive source as well as of the installation, the personnel and the involved procedures in the accidental event, information of the space geometry where the event took place. The preliminary information indicates that the source could have been locked in the guide tube of the equipment, next to the collimator in the first takes radiographic. The radiation monitors were not activated on the procedure, impeding this way, not to realize the flaw and causing that the personnel were exposed to the radiation during the whole work period. Their hands and especially their fingers would have been only to some millimeters of the source. With the obtained information and the measurements of the exposure rates of the radioactive source, was carried out the dose calculation to total body, the dose received in the hands and the dose received in the index finger of the left hand. The accident happened by operative procedure breach, by lack of training of the operators. The physical reconstruction of the accident contributes fundamental information for the decisions taking in the medical management of the accidents by radiation. (author)

  8. Development of modified voxel phantoms for the numerical dosimetric reconstruction of radiological accidents involving external sources: implementation in SESAME tool.

    Science.gov (United States)

    Courageot, Estelle; Sayah, Rima; Huet, Christelle

    2010-05-07

    Estimating the dose distribution in a victim's body is a relevant indicator in assessing biological damage from exposure in the event of a radiological accident caused by an external source. When the dose distribution is evaluated with a numerical anthropomorphic model, the posture and morphology of the victim have to be reproduced as realistically as possible. Several years ago, IRSN developed a specific software application, called the simulation of external source accident with medical images (SESAME), for the dosimetric reconstruction of radiological accidents by numerical simulation. This tool combines voxel geometry and the MCNP(X) Monte Carlo computer code for radiation-material interaction. This note presents a new functionality in this software that enables the modelling of a victim's posture and morphology based on non-uniform rational B-spline (NURBS) surfaces. The procedure for constructing the modified voxel phantoms is described, along with a numerical validation of this new functionality using a voxel phantom of the RANDO tissue-equivalent physical model.

  9. The Influence of atmospheric conditions to probabilistic calculation of impact of radiology accident on PWR 1000 MWe

    International Nuclear Information System (INIS)

    Pande Made Udiyani; Sri Kuntjoro

    2015-01-01

    The calculation of the radiological impact of the fission products releases due to potential accidents that may occur in the PWR (Pressurized Water Reactor) is required in a probabilistic. The atmospheric conditions greatly contribute to the dispersion of radionuclides in the environment, so that in this study will be analyzed the influence of atmospheric conditions on probabilistic calculation of the reactor accidents consequences. The objective of this study is to conduct an analysis of the influence of atmospheric conditions based on meteorological input data models on the radiological consequences of PWR 1000 MWe accidents. Simulations using PC-Cosyma code with probabilistic calculations mode, the meteorological data input executed cyclic and stratified, the meteorological input data are executed in the cyclic and stratified, and simulated in Muria Peninsula and Serang Coastal. Meteorological data were taken every hour for the duration of the year. The result showed that the cumulative frequency for the same input models for Serang coastal is higher than the Muria Peninsula. For the same site, cumulative frequency on cyclic input models is higher than stratified models. The cyclic models provide flexibility in determining the level of accuracy of calculations and do not require reference data compared to stratified models. The use of cyclic and stratified models involving large amounts of data and calculation repetition will improve the accuracy of statistical calculation values. (author)

  10. How can interventions for inhabitants be justified after a nuclear accident? An approach based on the radiological protection system of the international commission on radiological protection

    International Nuclear Information System (INIS)

    Takahara, Shogo; Homma, Toshimitsu; Yoneda, Minoru; Shimada, Yoko

    2016-01-01

    Management of radiation-induced risks in areas contaminated by a nuclear accident is characterized by three ethical issues: (1) risk trade-off, (2) paternalistic intervention and (3) individualization of responsibilities. To deal with these issues and to clarify requirements of justification of interventions for the purpose of reduction in radiation-induced risks, we explored the ethical basis of the radiological protection system of the International Commission on Radiological Protection (ICRP). The ICRP's radiological protection system is established based on three normative ethics, i.e. utilitarianism, deontology and virtue ethics. The three ethical issues can be resolved based on the decision-making framework which is constructed in combination with these ethical theories. In addition, the interventions for inhabitants have the possibility to be justified in accordance with two ways. Firstly, when the dangers are severe and far-reaching, interventions could be justified with a sufficient explanation about the nature of harmful effects (or beneficial consequences). Secondly, if autonomy of intervened-individuals can be promoted, those interventions could be justified. (author)

  11. Nanoscopic designs of radiological protection in environmental scale for the Fukushima nuclear accident: Strategy by dispersion, dissolution, and filtration

    International Nuclear Information System (INIS)

    Woo, Tae Ho

    2016-01-01

    Highlights: • New kind of radiological protection concept is introduced. • The shielding concept is accompanied with the water spray system. • The solubility of radioactive material could be used for protection. • Practical method is suggested. • The system is variable by the random number quantities. - Abstract: The environmental defense system in the nuclear power plants (NPPs) is investigated in the aspect of the environmental scale incorporated with atmospheric and marine sectors. The object is to find the radiological protection protocol in the environmental scale which is different from the conventional three kinds of radiological protection principles. Conventional laboratory based principles are not applicable in the mass failure accident such as the case of Fukushima disaster. This newly introduced protocol has many useful applications for the nature treatment oriented methods where the atmospheric protection of dispersion and dissolution is performed first and the filtration of seawater would follow. The maximum and minimum values in fan velocity are about 7.5 m/s and 5.3 m/s respectively. For the spray system, the mole fractions by the water spray are shown where maximum and minimum values are 6.57 × 10 −17 and 8.84 × 10 −19 moles respectively. The maximum and minimum values of discharged values in filtration are 99.4 and 1.3 square velocity (m/s), respectively. The total and general radiological protection concept is suggested in the nanoscopic molecular scale performance.

  12. Medical preparedness and response in nuclear accidents. The health team's experience in joint work with the radiological protection area

    International Nuclear Information System (INIS)

    Maurmo, Alexandre Mesquita

    2007-01-01

    The interaction between the health and the radiological protection areas has proved fundamental, in our work experience, for the quality of response to victims of accidents, involving ionizing radiation. The conceptions and basic needs comprehension of the adequate response, on these two areas, have brought changes to the essential behavior related to the victim's care, the protection response, the environment and waste production. The joint task of health professionals and radiological protection staff, as first responders, demonstrates that it is possible to adjust practices and procedures. The training of professionals of the radiological protection area by health workers, has qualified them on the basic notions of pre-hospital attendance, entitling the immediate response to the victim prior to the health team arrival, as well as the discussion on the basic concepts of radiological protection with the health professionals, along with the understanding of the health area with its specific needs on the quick response to imminent death risk, or even the necessary procedures of decontamination. (author)

  13. Industrial accidents in radiological controlled areas: the importance of radiation protection in the organisation of the emergency aid

    International Nuclear Information System (INIS)

    Fenolland, J.L.; Laporte, E.

    2003-01-01

    After some disappointments when the first French nuclear units were started, it became clear that all the aspects linked to radio-protection needed to be taken into account in the context of emergency aid in the case of an industrial accident in radiological controlled area. In the case of an accident involving people, on-site first aid is provided by permanent services of the power plant. These teams are trained in first aid and fire-fighting. They are well trained in radioprotection. The specificity of an industrial event in controlled zone is that the victims' conventional injuries, whether it be a wound, a burn or a fracture, can be complicated by radioactive contamination. If it is justified, the exterior emergency services (firemen and medical teams) sire immediately called in. These teams are not necessarily trained in radioprotection. (authors)

  14. Rapid and reliable predictions of the radiological consequences of accidents as an aid to decisions on countermeasures

    International Nuclear Information System (INIS)

    Kelly, G.N.

    1990-01-01

    The rapid and reliable assessment of the potential radiological consequences of an accident at a nuclear installation is an essential input to timely decisions on the effective introduction of countermeasures. There have been considerable improvements over the past decade or so in the methods used for such assessments and, in particular, in the development of computerized systems. The need for such systems is described, together with their current state of development and possible future trends. This topic has featured prominently within the CEC's Radiation Protection Research Programme and is likely to do so far the foreseeable future. The main features of this research, its achievements to date and future directions are described

  15. Main radiation protection actions for medical personnel as primary responders front of an event with radiological dispersive device; Principais acoes de protecao radiologica para equipe medica como primeiros respondedores frente a um evento com dispositivo de dispersao radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Duque, Hildanielle Ramos

    2015-07-01

    After the terrorist attack in New York, USA, in 2001, there was a worldwide concern about possible attacks using radioactive material in conventional detonators, called as Radiological Dispersal Device (RDD) or 'dirty bomb'. Several studies have been and are being made to form a global knowledge about this type of event. As until now, fortunately, there has not been an event with RDD, the Goiania Radiological Accident in Brazil, 1987, is used as a reference for decision-making. Several teams with technical experts should act in an event with RDD, but the medical staffs who respond quickly to the event must be properly protected from the harmful effects of radiation. Based on the radiological protection experts performance during the Goiania accident and the knowledge from lessons learned of many radiological accidents worldwide, this work presents an adaptation of the radiation protection actions for an event with RDD that helps a medical team as primary responders. The following aspects are presented: the problem of radioactive contamination from the explosion of the device in underground environment, the actions of the first responders and evaluation of health radiation effects. This work was based on specialized articles and papers about radiological accidents and RDD; as well as personal communication and academic information of the Institute of Radiation Protection and Dosimetry. The radiation protection actions, adapted to a terrorist attack event with RDD, have as a scenario a subway station in the capital. The main results are: the use of the basic radiation protection principle of time because there is no condition to take care of a patient keeping distance or using a shielding; the use of full appropriate protection cloths for contaminating materials ensuring the physical safety of professionals, and the medical team monitoring at the end of a medical procedure, checking for surface contamination. The main conclusion is that all medical actions

  16. A preliminary assessment of the radiological impact of the Chernobyl reactor accident on the population of the European Community

    International Nuclear Information System (INIS)

    Morrey, M.; Brown, J.; Williams, J.A.; Crick, M.J.; Simmonds, J.R.; Hill, M.D.

    1988-01-01

    Following the Chernobyl accident the Commission of the European Communities asked the National Radiological Protection Board to carry out a preliminary assessment of the radiological consequences of the accident on the population of the European Community (EC). The aim of the study was to review information on the environmental contamination measured in member states of the EC; to make a preliminary assessment of individual and population doses for each country; to make an estimate of the resulting health impact and to indicate the effects of the various countermeasures taken by member states in terms of the reductions in both individual and population exposure which they produced. All of the main pathways by which people have been and will be exposed to radiation as a result of the accident were included in the assessment. The impact estimate is based on environmental measurements made during the month after the accident, and on calculations made using mathematical models of radionuclide transfer through the environment. The calculated effective doses to average individuals in EC countries from exposure over the next 50 years range from 0.3 μSv (in Portugal) to between about 300 and 500 μSv (in the FRG, Italy and Greece). The total collective effective dose to the population of EC countries, integrated over all time, is estimated to be about 80 000 man Sv. This may be compared to the collective effective dose from natural background radiation of about 500 000 man Sv every year. In some countries, the restrictions placed on consumption of some foods are estimated to have been effective in reducing doses to the most exposed individuals; the reduction being up to about a factor of 2. The results presented in this paper should therefore be regarded as preliminary

  17. Radioecological studies in Goiania urban area: review

    International Nuclear Information System (INIS)

    Rio, Monica Pires do; Amaral, Eliana

    1997-01-01

    Studies on the behaviour and transport of 137 Cs in urban areas, including, resuspension and deposition experiments, 137 Cs uptake by leafy vegetables and small domestic animals that accidentally ingested contaminated soil, were performed in a house located at 57 t h Street near the main focus of contamination. The resuspension of surface soil did not contribute much to the spreading of the radionuclide in Goiania, but can lead to the local contamination of vegetables, equipment, structures and other environmental surfaces. The mechanism also presented a seasonal effect. The soil is an important medium for the uptake of 137 Cs by small domestic animals. The street dust sampling is a suitable method to assess the dispersion of 137 Cs in urban areas. After 10 years, the radionuclide activity concentration is restricted only to the initially impacted area an it is decreasing with time. (author)

  18. Remediation strategies after nuclear or radiological accidents: part 2 - accident scenarios for assessing effectiveness of cleanup procedures

    International Nuclear Information System (INIS)

    Rochedo, Elaine R.R.

    2009-01-01

    The selection of protective measures and remediation strategies after an accident needs to be based on previously established criteria, to minimize unnecessary stress and the exposures involved in cleanup operations that are not effective in reducing doses to the public. In a first stage, a database describing the countermeasures has been developed including their efficiency on removing contamination from surfaces. However, to assess the effectiveness of cleanup procedures in reducing doses to members of the public, it was necessary to derive specific scenarios in order to simulate the long term behavior of the material in the environment, since the contribution of different surfaces to doses changes with time after contamination. A basic release and exposure scenario was developed to assess the dose reduction due to the mostly used procedures. Exposure scenarios were selected to fit the surroundings of the Brazilian nuclear power plants in Angra dos Reis. Simulations were performed using SIEM, the integrated system for dose assessment after contamination events, developed at IRD. The contamination of urban environments was assessed for Cs-137, as this was found to be the most relevant long term radionuclide to contribute to doses to member of the public. The effects on reducing external exposures were assessed for periods up to 50 years after the contamination. For agricultural areas, the focus was on ingestion doses from contamination with I-131 for periods up to 1 year after contamination. Results will be complemented on the database in order to support multi-criteria decision making processes after accidents. (author)

  19. Remediation strategies after nuclear or radiological accidents: part 2 - accident scenarios for assessing effectiveness of cleanup procedures

    Energy Technology Data Exchange (ETDEWEB)

    Rochedo, Elaine R.R. [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil). Coordenacao de Instalacoes Nucleares], e-mail: erochedo@cnen.gov.br; Silva, Diogo N.G.; Wasserman, Maria A.V.; Conti, Luiz F.C. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)], e-mail: dneves@ird.gov.br, e-mail: angelica@ird.gov.br, e-mail: lfcconti@ird.gov.br

    2009-07-01

    The selection of protective measures and remediation strategies after an accident needs to be based on previously established criteria, to minimize unnecessary stress and the exposures involved in cleanup operations that are not effective in reducing doses to the public. In a first stage, a database describing the countermeasures has been developed including their efficiency on removing contamination from surfaces. However, to assess the effectiveness of cleanup procedures in reducing doses to members of the public, it was necessary to derive specific scenarios in order to simulate the long term behavior of the material in the environment, since the contribution of different surfaces to doses changes with time after contamination. A basic release and exposure scenario was developed to assess the dose reduction due to the mostly used procedures. Exposure scenarios were selected to fit the surroundings of the Brazilian nuclear power plants in Angra dos Reis. Simulations were performed using SIEM, the integrated system for dose assessment after contamination events, developed at IRD. The contamination of urban environments was assessed for Cs-137, as this was found to be the most relevant long term radionuclide to contribute to doses to member of the public. The effects on reducing external exposures were assessed for periods up to 50 years after the contamination. For agricultural areas, the focus was on ingestion doses from contamination with I-131 for periods up to 1 year after contamination. Results will be complemented on the database in order to support multi-criteria decision making processes after accidents. (author)

  20. Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2006-04-01

    In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

  1. Emergency Management and Radiation Moni-toring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD

    Energy Technology Data Exchange (ETDEWEB)

    Lahtinen, J [Radiation and Nuclear Safety Authority (STUK) (Finland)

    2006-04-15

    In order to manage various nuclear or radiological emergencies the authorities must have pre-prepared plans. The purpose of the NKS project EMARAD (Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents) was to produce and gather various data and information that could be useful in drawing up emergency plans and radiation monitoring strategies. One of the specific objectives of the project was to establish a www site that would contain various radiation-threat and radiation-monitoring related data and documents and that could be accessed by all Nordic countries. Other important objectives were discussing various factors affecting measurements in an emergency, efficient use of communication technology and disseminating relevant information on such topics as urban dispersion and illicit use of radiation. The web server is hosted by the Radiation and Nuclear Safety Authority (STUK) of Finland. The data stored include pre-calculated consequence data for nuclear power plant accidents as well as documents and presentations describing e.g. general features of monitoring strategies, the testing of the British urban dispersion model UDM and the scenarios and aspects related to malicious use of radiation sources and radioactive material. As regards the last item mentioned, a special workshop dealing with the subject was arranged in Sweden in 2005 within the framework of the project. (au)

  2. Luminescence properties of common salt (NaCl available in Nigeria for use as accident dosimeter in radiological emergency situation

    Directory of Open Access Journals (Sweden)

    Janet Ayobami Ademola

    2017-04-01

    Full Text Available In the event of a radiological accident or attack, it is important to assess and quantify radiation dose to the population. This could be done using materials in the vicinity that are sensitive to ionizing radiation. Common salt (NaCl is known to be a sensitive thermoluminescence (TL phosphor. Luminescence properties of common salt (NaCl used in Nigeria were investigated using an automated luminescence reader Risø TL/OSL-DA-15, with attention focused more on the Optically Stimulated Luminescence (OSL. Strong radiation-induced TL and OSL signals were observed. The TL peaks occurred at about 100 °C, 240 °C and 280 °C. The dose response of both the TL and OSL signals showed a linear relationship. From the OSL pulse anneal curve with TL curve, a preheat temperature of 190 °C for 10 s was found adequate for the OSL measurements. There was no significant difference in the OSL decay for stimulation temperatures of 100 and 120 °C. Fading experiment over a storage period of 14 days showed about 13 and 3% decrease in the OSL signal of sample 1 and sample 2, respectively. The ratios of measured to given dose for dose recovery test were within ±19% of unity. Within the limit of error the samples could be used as a complementary emergency dosimeter in radiological accident situation.

  3. Atmospheric dispersion modeling and radiological safety analysis for a hypothetical accident of Ghana Research Reactor -1 (GHARR-1)

    International Nuclear Information System (INIS)

    Lunguya, J. M.

    2013-06-01

    This work presents the environmental impact analysis of some selected radionuclides released from the Ghana Research Reactor- 1 (GHARR-1) after a hypothetical postulated accidents scenario. The source term was identified and generated from an inventory of radioisotopes released during the accident. Atmospheric transport model was then applied to calculate the total effective dose and how it would be distributed to different organs of the human body as a function of distance downwind. All accident scenarios were selected from GHARR-1 Safety Analysis Report. After the source term was identified the MCNPX code was used to perform the core burnup/depletion analysis. The assumption was made that the activities were released to the atmosphere under a horse design basis accident scenario. The gaussian dose calculation method was applied, coded in Hotspot, a Healthy Physics computer code. This served as the computational tool to perform the atmospheric dispersion modeling and was used to calculate radionuclide concentration at downwind location. Based upon predominant meteorological conditions at the site, the adopted strategy was to use site-specific meteorological data and dispersion modeling to analyze the hypothetical release to the environment of radionuclides and evaluate to what extent such a release may have radiological effects on the public. Final data were processed and presented as Total Effective Dose Equivalent as a function of time and distance of deposition. The results indicate that all the values of Effective dose obtained are far below the regulatory limits, making the use of the reactor safe, even in the case of worst accident scenario where all the fission products were released into the atmosphere. (au)

  4. Radiology

    International Nuclear Information System (INIS)

    Sykora, A.

    2006-01-01

    In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

  5. The Role of Countermeasures in Mitigating the Radiological Consequences of Nuclear Power Plant Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Tawfik, F. S.; Abdel-Aal, M.M., E-mail: basant572000@yahoo.com [Siting & Environmental Department, Nuclear and Radiological Regulatory Authority, Cairo (Egypt)

    2014-10-15

    During the Fukushima accident the mitigation actions played an important role to decrease the consequences of the accident. The countermeasures are the actions that should be taken after the occurrence of a nuclear accident to protect the public against the associated risk. The actions may be represented by sheltering, evacuation, distribution of stable iodine tablets and/or relocation. This study represents a comprehensive probabilistic study to investigate the role of the adoption of the countermeasures in case of a hypothetical accident of type LOCA for a nuclear power plant of PWR (1000 Mw) type. This work was achieved through running of the PC COSYMA{sup (1)} code. The effective doses in different organs, short and long term health effects, and the associated risks were calculated with and without countermeasures. In addition, the overall costs of the accident and the costs of countermeasures are estimated which represent our first trials to know how much the postulated accident costs. The source term of a hypothetical accident is determined by knowing the activity of the core inventory. The meteorological conditions around the site in addition to the population distribution were utilized as input parameters. The stability conditions and the height of atmospheric boundary layers ABL of the concerned site were determined by developing a computer program utilizing Pasquill-Gifford atmospheric stability conditions. The results showed that, the area around the site requires early and late countermeasures actions after the accident especially in the downwind sectors. For late countermeasures, the duration of relocation ranged from about two to 10 years. The adoption of the countermeasures increases the costs of emergency planning by 40% but reduces the risk associated with the accident. (author)

  6. Learned lessons of the radiological accident occurred in La Ciudadela of El Cementerio, Gran Caracas. September 2005

    International Nuclear Information System (INIS)

    Lea, D.; Cubillan, Y.; Figuera, J.L.; Mora, G.; Pacheco, J.; Yanez, H.; Carrizales, L.

    2006-01-01

    On September 20, 2005 when a mission conformed by five (05) officials: two (02) belonging to the Ministry of Energy and Mines (MEP) and three (03) of the Ministry of Health (MS) it was prepared to carry out a routine inspection in the one temporary warehouse of sources in disuse located in La Ciudadela of El Cementerio, identified administratively as Warehouse Number 5 (MS) Area X, noticed that those armor-plating that kept the radioactive sources of Cs-137 had been violated. Those people that entered to the warehouse were able to extract the armor-plating in whose interior its were found an important number of sources of Cs-137 in disuse, used in the decade of 70 and 80 in treatment of cancer of the uterine neck, by means of the Brachytherapy technique of Differed charge manual, low dose rate, as well as, lead sheets with the apparent intention of selling them as junk. The intruders extracted a total of 58 radioactive sources of Cs-137 of its armor-plating for then to disperse them inside warehouse and in the external areas to this. An important number of the dispersed sources its had lost it integrity what gave place to a combined scenario of exposed dispersed sources in a public area with the danger of radioactive contamination by Cs-137. A task force conformed by the following institutions: Ministry of Health (MS), Ministry of Energy and Petroleum (MENPET), Venezuelan Institute of Scientific Investigations (IVIC), Unit of Dangerous Materials of the Metropolitan Firemen under the coordination of Civil Protection (PC) it was the one in charge of responding to the radiological accident, of conformity to the National Plan for the Answer to Radiological Accidents. All the radioactive sources dispersed in La Ciudadela achieved to be recovered. The experience of the accident and as learned lesson it was the importance of harmonizing the Generic Procedures for the Evaluation and Answer during Radiological Emergencies, IAEA-TECDOC-1162 technical document, Vienna, August

  7. The prevention of radiological accidents (how to avoid or minimize potential exposures)

    International Nuclear Information System (INIS)

    Touzet, Rodolfo E.

    2006-01-01

    A detailed analysis of 7 major accidents occurred in radiotherapy services in different countries is performed. Then a generic analysis of the causes is realized and finally the methodology used to prevent them effectively is described [es

  8. Radiological emergency: road map for radiation accident victim transport; Emergência radiológica: roadmap para o transporte de radioacidentado

    Energy Technology Data Exchange (ETDEWEB)

    Costa, V.S.G.; Alcantara, Y.P. [Faculdade Casa Branca, SP (Brazil); Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro, RJ (Brazil); Silva, F. C. A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    During a radiological or nuclear emergency, a number of necessary actions are taken, both within the radiation protection of individuals and the environment, involving many institutions and highly specialized personnel. Among them it is possible to emphasize the air transportation of radiation accident victims.The procedures and measures for the safe transport of these radiation accident victims are generally the responsibility of the armed forces, specifically the Aeronautics, with the action denominated 'Aeromedical Military Evacuation of Radiation Accident Victims'. The experience with the Radiological Accident of Goiânia demonstrated the importance of adequate preparation and response during a radiological emergency and the need for procedures and measures with regard to the transport of radiation victims are clearly defined and clearly presented for the effectiveness of the actions. This work presents the necessary actions for the transport of radiation accident victim during a radiological emergency, through the road map technique, which has been widely used in scientific technical area to facilitate understanding and show the way to be followed to reach the proposed objectives.

  9. Changes of radiological situation of Polish environment in 10 years period after Chernobyl accident

    International Nuclear Information System (INIS)

    Jagielak, J.; Biernacka, M.; Grabowski, D.; Henschke, J.

    1996-01-01

    The content of natural and artificial radioisotopes in environment in Poland before and after Chernobyl accident was analyzed. The methods used in radiation monitoring in Poland and results of these measurements in the period 1986-1996 were presented. Since the Chernobyl accident changes of contamination of soils, southern Baltic sea water, other surface waters, deposits in Baltic sea, rivers and lakes in Poland were observed. Also concentration of radioisotopes in foodstuffs: mushrooms, fruits, meat, milk, eggs was described

  10. Radiological objectives and severe accident mitigation strategy for the generation II PWRs in France in the framework of PLE

    International Nuclear Information System (INIS)

    Cenerino, G.; Dubreuil, M.; Raimond, E.; Pichereau, F.

    2012-01-01

    In France, EDF is involved in the construction of a first generation III (Gen III) reactor (European Pressurized Reactor - EPR) on Flamanville site next to two PWRs. Plant Life Extension (PLE) of reactors will consequently lead to simultaneous operation of Gen III and Gen II reactors during a long period of time. As a consequence, EDF was requested by the French Nuclear Safety Authority to prepare a PWR life management program including, in addition to an ageing management of Systems, Structures and Components, a consequent reactor safety enhancement program. The objective was stated to EDF by the French Nuclear Safety Authority: 'the safety objectives of the Gen III reactors should be used as a reference for all studies undertaken in the frame of PLE'. One part of the EDF program deals with additional arrangements able to reduce more drastically the consequences of any accident. The relevance, according to IRSN, of the EDF radiological objectives for Design Basis Accidents, of the new EDF objectives for Severe Accidents (SA) and of the EDF potential modifications for SA mitigation are presented. (author)

  11. Monitoring techniques for the impact assessment during nuclear and radiological emergencies: current status and the challenges

    International Nuclear Information System (INIS)

    Pradeepkumar, K.S.; Sharma, D.N.

    2003-01-01

    Preparedness and response capability for Nuclear and Radiological emergencies, existing world over, are mainly based on the requirement of responding to radiation emergency caused by nuclear or radiological accidents. Cosmos satellite accident, plutonium contamination at Polaris, nuclear accidents like Kystium, Windscale, TMI and Chernobyl, radiological accidents at Goiania etc have demonstrated the requirement of improved radiation monitoring techniques. For quick decision making, state of the art monitoring methodology which can support quantitative and qualitative impact assessment is essential. Evaluation of radiological mapping of the area suspected to be contaminated needs ground based as well as aerial based monitoring systems to predict the level of radioactive contamination on ground. This will help in delineating the area and deciding the required countermeasures, based on the quantity and type of radionuclides responsible for it. The response can be successful with the effective use of i) Early Warning System ii) Mobile Monitoring System and iii) Aerial Gamma Spectrometric System. Selection of the monitoring methodology and survey parameters and assessment of situation using available resources etc. are to be optimized depending on the accident scenario. Recently, many countries and agencies like IAEA have expressed the requirement for responding to other types of nuclear/radiological emergencies i.e, man made radiation emergency situations aimed at harming public at large that can also lead to environmental contamination and significant exposure to public. Reports of lost / misplaced / stolen radioactive sources from many countries are alarming as safety and security of these radioactive sources are under challenge. The monitoring methodology has to take into account of the increase in such demands and more periodic monitoring in suspected locations is to be carried out. Detection of orphan sources possible amidst large heap of metallic scraps may pose

  12. Emergency planning lessons learned from a review of past major radiological accidents

    International Nuclear Information System (INIS)

    Stephan, J.G.; Selby, J.M.; Martin, J.B.; Moeller, D.W.; Vallario, E.J.

    1988-01-01

    In examining a range of nuclear accidents from the 1950s to the present that were reported in the literature, the authors have identified a number of contributing factors which affected human judgement during these events. One common thread found in a large number of accidents is the time of occurrence; a second is the adequacy of emergency training. The data show that events, whether severe accidents or operational incidents, appear to occur more frequently during off-normal hours such as the early morning shift, weekends, or holidays. Accidents seldom occur during the day shift when the full management team and senior operations personnel are present. As a result, those facility employees most expert in coping with the situation may not be available, and the normal chain of command may be disrupted. At several nuclear power plants, it was also observed that new or less experienced technicians are often assigned to night shifts. The lack of experienced human resources and the pressure of an accident situation can have an adverse impact on individuals who are faced with making important decisions

  13. Radiological accidents: methodologies of radio nuclides dis incorporation; Accidentes radiologicos: metodologias de desincorporacion de radionuclidos

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez F, E. A. [Universidad Autonoma del Estado de Mexico, Facultad de Medicina, Paseo Tollocan s/n, 50180 Toluca, Estado de Mexico (Mexico); Paredes G, L. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Cortes, A., E-mail: lydia.paredes@inin.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2014-08-15

    Derived of the radioactive or nuclear material management, exists the risk that accidents can happen where people cases are presented with internal radioactive contamination, who will receive specialized medical care to accelerate the radioactive dis incorporation with the purpose of diminishing the absorbed dose and the associate biological effects. In this work treatments of radioactive dis incorporation were identified, in function of the radionuclide, radiation type, radioactive half life, biological half life, critical organ, ingestion duct and patient type. The factor time is decisive for the effectiveness of the selected treatment in the blockade stage (before the accident) or dis incorporation (after the accident); this factor is related with the radioactive and biological half lives. So to achieve dis incorporation efficiencies of more to 70%, the patient clinical treatment will begin before the first third of the biological half life of the radionuclide that generated the internal contamination. (Author)

  14. The influence of the natural environment on the radiological consequences of a nuclear accident

    International Nuclear Information System (INIS)

    Grauby, A.

    1989-01-01

    Much work has been done in the agri-food field on the evaluation of the health implications of a nuclear accident. Much less has been done on environmental dynamics. Research on the behaviour of radioactive deposits from the Chernobyl accident, however, has revealed the importance of natural conditions for the transfer of radionuclides in the environment. In particular, two phases have been observed. In the first, which lasts until a point of equilibrium is reached in the environment, radionuclides follow the water cycle. The second phase unfolds following the incorporation of ruthenium and cesium in soil and sediment. Certain environmental factors (natural ecosystems, relief, etc.) and the different meteorological conditions (climate and season) should be investigated in more detail. Better understanding of the effect of natural conditions could be used to predict, in time and space, any specific risks arising during nuclear accidents whether located near or far [fr

  15. Proceedings of the first international conference 'The radiological consequences of the Chernobyl accident'

    Energy Technology Data Exchange (ETDEWEB)

    Karaoglou, A; Desmet, G; Kelly, G N; Menzel, H G [European Commission, Brussels (Belgium)

    1996-07-01

    Five main objectives were assigned to the EC/CIS scientific collaborative programme: improvement of the knowledge of the relationship between doses and radiation-induced health effects; updating of the arrangements for off-site emergency management response (shot- and medium term)in the even of a future nuclear accident; assisting the relevant CIS Ministries alleviate the consequences of the Chernobyl accident, in particular in the field of restoration of contaminated territories; elaboration of a scientific basis to definite the content of Community assistance programmes; updating of the local technical infrastructure, and implementation of a large programme of exchange of scientists between both Communities. The topics addressed during the Conference mainly reflect the content of the joint collaborative programme: environmental transfer and decontamination, risk assessment and management, health related issues including dosimetry. The main aims of the Conference are to present the major achievements of the joint EC/CIS collaborative research programme (1992-1995) of the consequences of the Chernobyl accident, and to promote an objective evaluation of them by the international scientific community. The Conference is taking place close to the 10{sup th} anniversary of the accident and we hope it will contribute to more objective communication of the health and environmental consequences of the Chernobyl accident, and how these may be mitigated in future. The Conference is expected to be an important milestone in the series of meetings which will take place internationally around the 10{sup th} anniversary of the nuclear accident. It also provides a major opportunity for all participants to become acquainted with software developed within the framework of the collaborative programme, namely: Geographical Information Systems displaying contamination levels and dose-commitments; Decision Support Systems for the management of contaminated territories; Decision Support

  16. Proceedings of the first international conference 'The radiological consequences of the Chernobyl accident'

    International Nuclear Information System (INIS)

    Karaoglou, A.; Desmet, G.; Kelly, G.N.; Menzel, H.G.

    1996-01-01

    Five main objectives were assigned to the EC/CIS scientific collaborative programme: improvement of the knowledge of the relationship between doses and radiation-induced health effects; updating of the arrangements for off-site emergency management response (shot- and medium term)in the even of a future nuclear accident; assisting the relevant CIS Ministries alleviate the consequences of the Chernobyl accident, in particular in the field of restoration of contaminated territories; elaboration of a scientific basis to definite the content of Community assistance programmes; updating of the local technical infrastructure, and implementation of a large programme of exchange of scientists between both Communities. The topics addressed during the Conference mainly reflect the content of the joint collaborative programme: environmental transfer and decontamination, risk assessment and management, health related issues including dosimetry. The main aims of the Conference are to present the major achievements of the joint EC/CIS collaborative research programme (1992-1995) of the consequences of the Chernobyl accident, and to promote an objective evaluation of them by the international scientific community. The Conference is taking place close to the 10 th anniversary of the accident and we hope it will contribute to more objective communication of the health and environmental consequences of the Chernobyl accident, and how these may be mitigated in future. The Conference is expected to be an important milestone in the series of meetings which will take place internationally around the 10 th anniversary of the nuclear accident. It also provides a major opportunity for all participants to become acquainted with software developed within the framework of the collaborative programme, namely: Geographical Information Systems displaying contamination levels and dose-commitments; Decision Support Systems for the management of contaminated territories; Decision Support Systems

  17. Radiology

    International Nuclear Information System (INIS)

    Meyers, M.A.

    1989-01-01

    This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

  18. Radiological impact of a loss of coolant accident at Angra 2 reactor

    International Nuclear Information System (INIS)

    Dias, W.

    1992-01-01

    A loss of coolant accident is analyzed which comprises a double ended rupture of a main primary system line. The accident sequence is described and the main assumptions as to the activity release are presented. On the basis of site specific meteorological data, the atmospheric dispersion factors are calculated using the Gaussian plume diffusion model and the doses are then determined at the boundary of the low population zone. The resulting values for the effective dose equivalent are more than one order of magnitude below that due to the average background radiation received in one year. (author)

  19. Examination of offsite radiological emergency measures for nuclear reactor accidents involving core melt

    International Nuclear Information System (INIS)

    Aldrich, D.C.; McGrath, P.E.; Rasmussen, N.C.

    1978-06-01

    Evacuation, sheltering followed by population relocation, and iodine prophylaxis are evaluated as offsite public protective measures in response to nuclear reactor accidents involving core-melt. Evaluations were conducted using a modified version of the Reactor Safety Study consequence model. Models representing each measure were developed and are discussed. Potential PWR core-melt radioactive material releases are separated into two categories, ''Melt-through'' and ''Atmospheric,'' based upon the mode of containment failure. Protective measures are examined and compared for each category in terms of projected doses to the whole body and thyroid. Measures for ''Atmospheric'' accidents are also examined in terms of their influence on the occurrence of public health effects

  20. Atmospheric dispersion modelling and the use of radiological data in the event of a nuclear accident overseas

    International Nuclear Information System (INIS)

    ApSimon, H.M.; Simms, K.L.

    1988-02-01

    This report considers what radiological measurements are most useful for use in conjunction with computer simulations based on meteorological data to provide the best possible estimates of areas affected and the likely levels of contamination in the event of a nuclear accident overseas. The context is defined according to the needs at different stages in emergency procedures - before radioactivity reaches the UK, during the period of passage overhead, after passage of the material. The ability to identify localised areas where precipitation has concentrated deposition is emphasized. It is made clear that γ detectors tend to be dominated by local levels of deposited activity and are inadequate to define when radioactivity is passing overhead. Facilities for airborne monitoring are recommended. (author)

  1. Computerized system to perform a general radiological evaluation of the persons that live in areas affected by the nuclear accident of Chernobyl

    International Nuclear Information System (INIS)

    Cruz Suarez, R.; Valdes, M.

    1993-01-01

    A computer program (EVACID) was developed with the purpose of performing a general radiological evaluation. EVACID system allows to automate an important group of dosimetric calculations, as well as to store, codify analyze and relate among them the medical information of the persons affected by the nuclear accident of Chernobyl

  2. Approach to treatment of a patient with burns from a radiological accident

    International Nuclear Information System (INIS)

    Roberto, Maria Angelica

    2009-01-01

    Lesions by exposure to ionizing radiation can result from an atomic bomb blast, an industrial accident such as Chernobyl, or from cancer therapy. The gravity of lesions depends on the exposure time and on the deposited energy. A short review is made on the approach to treatment in the Hospital Sao Jose, Lisbon. (author)

  3. Henri Jammet Memorial lecture: The role of dosimetry in radiation accident response

    International Nuclear Information System (INIS)

    Ricks, Robert C.; Joiner, Eugene; Toohey, Richard E.; Holloway, Elizabeth C.

    1997-01-01

    This document presents a lecture given on the role of dosimetry in radiation accident response, focusing accidents such as: Vinca, occurred on october 15, 1958, Goiania Cs-137, Hanford Am-241 and Juarez Co-60, Chernobyl nuclear power plant. Other accidents are reported as they are registered in the REAC/TS Registry

  4. Psycho-social impact of the cesium-137 accident in the Brazilian society

    International Nuclear Information System (INIS)

    Chaves, E.G.

    1993-01-01

    The author intends to question the assumed current public opinion that the psycho-social impact, resulting from the Goiania accident, is related with the ignorance of those who handled the caesium-137 source capsule, as well as the way media explained the accident. Some important aspects related to social behaviour during and after the accident are also shown. (B.C.A.)

  5. The Chernobyl accident as a source of new radiological knowledge: implications for Fukushima rehabilitation and research programmes

    International Nuclear Information System (INIS)

    Balonov, Mikhail

    2013-01-01

    The accident at the Chernobyl nuclear power plant in Ukraine in 1986 caused a huge release of radionuclides over large areas of Europe. During large scale activities focused on overcoming of its negative consequences for public health, various research programmes in radioecology, dosimetry and radiation medicine were conducted. New knowledge was applied internationally in substantial updating of radiation protection systems for emergency and existing situations of human exposure, for improvement of emergency preparedness and response. Radioecological and dosimetry models were significantly improved and validated with numerous measurement data, guidance on environmental countermeasures and monitoring elaborated and tested. New radiological knowledge can be of use in the planning and implementation of rehabilitation programmes in Japan following the Fukushima nuclear accident. In particular, the following activity areas would benefit from application of the Chernobyl experience: strategy of rehabilitation, and technology of settlement decontamination and of countermeasures applied in agriculture and forestry. The Chernobyl experience could be very helpful in planning research activities initiated by the Fukushima radionuclide fallout, i.e. environmental transfer of radionuclides, effectiveness of site-specific countermeasures, nationwide dose assessment, health effect studies, etc. (paper)

  6. An assessment of the radiological consequences of releases to groundwater following a core-melt accident at the Sizewell PWR

    International Nuclear Information System (INIS)

    Maul, P.R.

    1984-03-01

    In the extremely unlikely event of a degraded core accident at the proposed Sizewell PWR it is theoretically possible for the core to melt through the containment, after which activity could enter groundwater directly or as a result of subsequent leaching of the core in the ground. The radiological consequences of such an event are analysed and compared with the analysis undertaken by the NRPB for the corresponding releases to atmosphere. It is concluded that the risks associated with the groundwater route are much less important than those associated with the atmospheric route. The much longer transport times in the ground compared with those in the atmosphere enable countermeasures to be taken, if necessary, to restrict doses to members of the public to very low levels in the first few years following the accident. The entry of long-lived radionuclides into the sea over very long timescales results in the largest contribution to population doses, but these are delivered at extremely low dose rates which would be negligible compared with background exposure. (author)

  7. Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident.

    Science.gov (United States)

    Sugiyama, Daisuke; Hattori, Takatoshi

    2013-01-01

    In environmental remediation after nuclear accidents, radioactive wastes have to be appropriately managed in existing exposure situations with contamination resulting from the emission of radionuclides by such accidents. In this paper, a framework of radiation protection from radioactive waste management in existing exposure situations for application to the practical and reasonable waste management in contaminated areas, referring to related ICRP recommendations was proposed. In the proposed concept, intermediate reference levels for waste management are adopted gradually according to the progress of the reduction in the existing ambient dose in the environment on the basis of the principles of justification and optimisation by taking into account the practicability of the management of radioactive waste and environmental remediation. It is essential to include the participation of relevant stakeholders living in existing exposure situations in the selection of reference levels for the existing ambient dose and waste management.

  8. Contribution of internal exposures to the radiological consequences of the Chernobyl accident.

    Science.gov (United States)

    Balonov, M I; Anspaugh, L R; Bouville, A; Likhtarev, I A

    2007-01-01

    The main pathways leading to exposure of members of the general public due to the Chernobyl accident were external exposure from radionuclides deposited on the ground and ingestion of contaminated terrestrial food products. The collective dose to the thyroid was nearly 1.5 million man Gy in Belarus, Russia and Ukraine with nearly half received by children and adolescents. The collective effective dose received in 1986-2005 by approximately five million residents living in the affected areas of the three countries was approximately 50,000 man Sv with approximately 40% from ingestion. That contribution might have been larger if countermeasures had not been applied. The main radionuclide contributing to both external and internal effective dose is 137Cs with smaller contributions of 134Cs and 90Sr and negligible contribution of transuranic elements. The major demonstrated radiation-caused health effect of the Chernobyl accident has been an elevated incidence of thyroid cancer in children.

  9. Radiological consequences of a hypothetical ''roof breakdown'' accident of the Chernobyl sarcophagus

    International Nuclear Information System (INIS)

    Pretzsch, G.

    1997-01-01

    On behalf of the German Federal Ministry for Environment, Nature Conservation and Nuclear Safety GRS performed investigations with the aim to improve the safety of the Chernobyl Unit 4 shelter in close connection with the Ministry for Environment and Nuclear Safety of the Ukraina from 1992 to 1995. One of the tasks of the working programme was concerned with the analysis of hypothetical accidents of the present shelter, which comprises the newly built Sarcophagus and the remaining ruins of Unit 4. In close collaboration with Ukrainian and Russian experts the maximum hypothetical accident was defined to be the breakdown of the roof of the Sarcophagus and subsequent release of the radioactive dust which is mainly located in the destroyed reactor hall and the neighboring rooms

  10. Postulated accident conditions for air cleaning systems and radiological dose assessments for containment options

    International Nuclear Information System (INIS)

    Hilliard, R.K.; Postma, A.K.

    1975-01-01

    Ambient conditions and performance requirements for emergency air cleaning systems applicable to commercial LMFBR plants were studied. The focus of this study centered on aerosol removal under hypothetical core disruptive accident conditions. Effort completed includes a review of air cleaning systems related to LMFBR plants, selection of three reference containment system designs, postulation of the EACS design basis accident (EACS-DBA), analysis of thermal conditions resulting from the DBA, analysis of aerosol transport behavior following the DBA, and an estimate of bone dose at the site boundary for each of the reference plant designs. Reference plant concepts were a single containment system (e.g., FFTF), a double containment system (e.g., CRBRP with closed head compartment), and a containment-confinement design in which an inerted, sealed primary volume was located within a ventilated building whose exhaust was filtered. The reference design basis accident selected here involved release to the inner containment system of 1 percent of non-volatile solids and plutonium, 25 percent of core halogens, 25 percent of core volatile solids, 100 percent of core noble gases, 68 lbs of sodium vapor and 5000 lbs of liquid sodium. 13 references. (U.S.)

  11. Source term and radiological consequence evaluation for nuclear accidents using a 'hand type' methodology

    International Nuclear Information System (INIS)

    Margeanu, Sorin; Tatiana, Angelescu

    2005-01-01

    In the last decades, hand type calculations have been replaced by computerized solutions, which are much more accurate, but the preparation of an input to run the code can be a time consuming process and can require a laborious work. This is why, a place for hand calculation based on nomograms still exist in some areas. An example is emergency response to an accidental release of radioactive contaminants when the health of persons close to the accident site might be at risk. In this case, results from computerized accident consequences assessment models may be delayed due to the equipment malfunction or the time required developing minimal input files and performing the calculations (typically more than five minutes). A simple nomogram (developed using computerized dispersion model calculations) can provide dispersion and dose estimates within a minute. The paper presents the methodology used for these 'hand type' calculation and the nomograms, figures and tables used to evaluate the dose to an individual close to the release point. In order to illustrate the use of methodology, a hypothetical severe accident scenario involving 14-MW INR-TRIGA research reactor was considered. (authors)

  12. Risk Communication Strategies: Lessons Learned from Previous Disasters with a Focus on the Fukushima Radiation Accident.

    Science.gov (United States)

    Svendsen, Erik R; Yamaguchi, Ichiro; Tsuda, Toshihide; Guimaraes, Jean Remy Davee; Tondel, Martin

    2016-12-01

    It has been difficult to both mitigate the health consequences and effectively provide health risk information to the public affected by the Fukushima radiological disaster. Often, there are contrasting public health ethics within these activities which complicate risk communication. Although no risk communication strategy is perfect in such disasters, the ethical principles of risk communication provide good practical guidance. These discussions will be made in the context of similar lessons learned after radiation exposures in Goiania, Brazil, in 1987; the Chernobyl nuclear power plant accident, Ukraine, in 1986; and the attack at the World Trade Center, New York, USA, in 2001. Neither of the two strategies is perfect nor fatally flawed. Yet, this discussion and lessons from prior events should assist decision makers with navigating difficult risk communication strategies in similar environmental health disasters.

  13. The GRS Emergency Centre during the Fukushima NPS Accident: Communicating Radiological Information to the Public

    International Nuclear Information System (INIS)

    Sentuc, F.N.; Dokter, S.

    2012-01-01

    During Fukushima 2011, the GRS Emergency Centre continuously analysed the situation and provided detailed information on the current plant status and the radiological consequences, not only for the German government but also for the worried public. The expert team primarily informed the competent authority about on-going developments in Japan via status reports. The status reports provided technical and radiological information promptly and were updated several times a day at the beginning and towards the end twice a week until July 1 2011. Additionally, these reports were translated into English and published on the web-site. In the course of the event, approximately 200 reports were issued by the GRS-EC. It became clear through media and public enquires that information, even at a very basic level, was needed in the field of nuclear technology and radiation protection. Therefore, technical experts and public relation team members worked together to prepare explanatory and background material. Owing to this strong interest, GRS established a special Fukushima portal on its web-site, to meet the need for information. As well as the technical aspects, which dominated the expert's work in the GRS Emergency Centre, one challenge was communicating the radiological information to the public in a comprehensible yet professional way. The media and the public appear to be very interested in getting information about the exposure of workers at the plant, the dose limits, the release of radioactive material in the atmosphere and the long-term effects of the contamination. The article is followed by the slides of the presentation

  14. Method for the development of emergency response preparedness for nuclear or radiological accidents

    International Nuclear Information System (INIS)

    2000-03-01

    This report supplements IAEA emergency preparedness guidance published in the 1980s, and is consistent with the new international guidance. It provides practical advice for the development of an emergency response capability based on the potential nature and magnitude of the risk. In order to apply this method, emergency planners should have a good understanding of the basic radiological emergency response principles. Therefore, other applicable international guidance should be reviewed before using this report. This report provides a practical step-by-step method for developing integrated user, local and national emergency response capabilities. It can also be used as the basis for conducting an audit of an existing emergency response capability

  15. Method for the development of emergency response preparedness for nuclear or radiological accidents

    International Nuclear Information System (INIS)

    1998-04-01

    This report supplements IAEA emergency preparedness guidance published in the 1980s, and is consistent with the new international guidance. It provides practical advice for the development of an emergency response capability based on the potential nature and magnitude of the risk. In order to apply this method, emergency planners should have a good understanding of the basic radiological emergency response principles. Therefore, other applicable international guidance should be reviewed before using this report. This report provides a practical step-by-step method for developing integrated user, local and national emergency response capabilities. It can also be used as the basis for conducting an audit of an existing emergency response capability

  16. Radioecological studies in Goiania urban area: review; Estudos radioecologicos na area urbana de Goiania: revisao

    Energy Technology Data Exchange (ETDEWEB)

    Rio, Monica Pires do; Amaral, Eliana [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    Studies on the behaviour and transport of {sup 137} Cs in urban areas, including, resuspension and deposition experiments, {sup 137} Cs uptake by leafy vegetables and small domestic animals that accidentally ingested contaminated soil, were performed in a house located at 57{sup t}h Street near the main focus of contamination. The resuspension of surface soil did not contribute much to the spreading of the radionuclide in Goiania, but can lead to the local contamination of vegetables, equipment, structures and other environmental surfaces. The mechanism also presented a seasonal effect. The soil is an important medium for the uptake of {sup 137} Cs by small domestic animals. The street dust sampling is a suitable method to assess the dispersion of {sup 137} Cs in urban areas. After 10 years, the radionuclide activity concentration is restricted only to the initially impacted area an it is decreasing with time. (author) 9 refs., 2 figs, 2 tabs.

  17. A proposed warning scheme for Philippine communities in case of severe radiological accidents in neighbor countries

    International Nuclear Information System (INIS)

    de la Paz, L.R.

    1986-01-01

    The Chernobyl accident in the Ukraine triggered a re-study of the emergency response planning of countries with nuclear power plants as well as those with no plans to put up such plants. As in the Philippines, the proposed early warning system is composed of 1) prompt notification following quidelines established through a bilateral agreement or through an international convention agreed upon by member staes of IAEA, and 2) placement of a continuous radiation monitor in Northern Luzon (Laoag City or Aparri). Early notification network details are given in an illustrated form. The paper also proposes warning classification for the Philippine authorities. (ELC). 3 figs

  18. Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

    International Nuclear Information System (INIS)

    Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

    1985-08-01

    This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs

  19. Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

    1985-08-01

    This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs.

  20. Heath Effects Sequence of Meet Halfa Radiological Accident After Twelve Years

    International Nuclear Information System (INIS)

    Shabon, M.H.

    2013-01-01

    The accident of Meet-Halfa developed consequent upon the loss of an industrial gamma radiography source. The source was found by a farmer resident of Meet-Halfa who took it to his house occupied by his family. The sequence of events developed over a period of seven weeks from the time the source was found on May 5, 2000, till the day of its retrieval from the house by the national authorities on June 26. The protracted exposure patterns of the family members during the period of source possession are not precisely known, however these exposures resulted in two fatalities, clinical forms of bone marrow depression, and several skin burns of different severities. The recent sequences of the accident is as follows:-The three survived siblings married and get good children. That mean there is no hereditary stochastic effects. The sister died at 2007 with 72 years old with senility and no specific disease. The youngest daughter amputate the left thumb and index fingers at 2001. The elder son amputate the terminal phalanx of the right thumb at 2009. The youngest daughter amputate the right index finger at 2009. The elder son graft the burn at the lower right quadrant of the abdomen for more than 20 times (3 of them were in the Mansheat Al-Bakry Millitary Hospital), but there is residual of burn untill now. Sever abdominal hernia in the elder son due to necroses in the right quadrant abdominal muscles. Grafting for these muscles occur but failed.

  1. Use of radiological accident experience in establishing appropriate perspectives in emergency planning

    International Nuclear Information System (INIS)

    Selby, J.M.; Vallario, E.J.; Moeller, D.W.; Stephan, J.G.

    1987-08-01

    Within a nuclear facility, an emergency can range from a situation that only involves the employees of that facility to a series of events that have both onsite and offsite consequences. Analyses of nuclear and non-nuclear emergencies can provide valuable information on the causes of, as well as the problems encountered during emergencies. Reports on facility emergencies indicate that up to 90% involve human error. Such events occur more frequently during the night shifts or on weekends. These occurrences may result from the absence of experienced personnel as well as the reduced alertness of onsite personnel. Therefore, this paper emphasizes the human element in a review of accidents that have occurred at nuclear facilities including Windscale, SL-1, the Recuplex criticality, the Wood River Junction criticality, the Browns Ferry fire, Three Mile Island, and Chernobyl. These accidents are described, and their consequences are evaluated. The information obtained from these evaluations may be useful for inclusion in nuclear plant operating and testing procedures. 21 refs

  2. Radiology

    International Nuclear Information System (INIS)

    Lissner, J.

    1985-01-01

    Diagnostic radiology is still the foremost of all innovative medical disciplines. This has many advantages but also some handicaps, e.g. the siting problem of medical equipment whose clinical potential is not fully known. This applies in particular to nuclear spin tomography, where the Laender governments and the Scientific Council seen to agree that all universities should have the appropriate equipment as soon as possible in order to intensify interdisciplinary research. Formerly, in the case of computerized tomography, there was less readiness. As a result, the siting of CT equipment is less organically structured. A special handicap of innovative fields is the problem of training and advanced training. The Chamber of Medicine and the Association of Doctors Participating in the Health Insurance Plan have issued regulations aimed at a better standardisation in this field. (orig.) [de

  3. Method for the development of emergency response preparedness for nuclear or radiological accidents

    International Nuclear Information System (INIS)

    1997-07-01

    This report supplements IAEA emergency preparedness guidance published in the 1980s, and is consistent with the new international guidance. It provides practical advice for the development of an emergency response capability based on the potential nature and magnitude of the risk. In order to apply this method, emergency planners should have a good understanding of the basic radiological emergency response principles. Therefore, other applicable international guidance should be reviewed before using this report. This report provides a practical step-by-step method for developing integrated user, local and national emergency response capabilities. It can also be used as the basis for conducting an audit of an existing emergency response capability. 14 refs, 4 figs, 4 tabs

  4. The radiological consequences in the USSR from the Chernobyl accident: Description of the scheme of implementation

    International Nuclear Information System (INIS)

    Dreicer, Mona

    2004-01-01

    After October 1989 the Government of the USSR requested the IAEA to organize an international assessment of the 'concept which the USSR has evolved to enable the population to live safely in areas affected by radioactive contamination following the Chernobyl accident, and an evaluation of the effectiveness of the steps taken in these areas to safeguard the health of the population'. The IAEA responded positively to this request for special assistance. The IAEA is carried out an extensive international project involving over 100 experts who assessed the human health and environmental consequences in the affected areas of Byelorussia, the Ukraine, and the Russian Federation, and evaluate measures taken by Soviet authorities to protect the population and the environment

  5. Radiological accident with Iodine-131 in the Radioisotope Division at IPEN-CNEN/SP (Brazil)

    International Nuclear Information System (INIS)

    Sanches, Matias Puga; Rodrigues, Demerval Leonidas

    1997-01-01

    The accident occurred in the first week of May 1995, in the Radioisotope Division-TPI, involving two tubes containing a total volume of 3 ml, aqueous solution of N Al 1 31, with 370 MBq and 1480 MBq activity is reported. Part of installation and six workers involved in the distribution process were contaminated with 131 I, but there were no contamination outside the building. The workers were decontaminated and the received radiation doses were evaluated by the Radiotoxicological Laboratory of IPEN-CNEN/SP together with IRD-CNEN/RJ. The building involved was closed and the activities stopped until the complete decontamination by the Radioprotection experts of IPEN-CNEN/SP. (author)

  6. Radiological health effects models for nuclear power plant accident consequence analysis

    International Nuclear Information System (INIS)

    Evans, J.S.; Moeller, D.W.

    1989-01-01

    Improved health effects models have been developed for assessing the early effects, late somatic effects and genetic effects that might result from low-LET radiation exposures to populations following a major accident in a nuclear power plant. All the models have been developed in such a way that the dynamics of population risks can be analyzed. Estimates of life years lost and the duration of illnesses were generated and a framework recommended for summarizing health impacts. Uncertainty is addressed by providing models for upper, central and lower estimates of most effects. The models are believed to be a significant improvement over the models used in the U.S. Nuclear Regulatory Commission's Reactor Safety Study, and they can easily be modified to reflect advances in scientific understanding of the health effects of ionizing radiation

  7. Health effects models for off-site radiological consequence analysis of nuclear reactor accidents

    International Nuclear Information System (INIS)

    Togawa, Orihiko; Homma, Toshimitsu; Matsuzuru, Hideo; Kobayashi, Sadayoshi

    1991-02-01

    A first version of models has been developed for predicting the number of occurrences of health effects induced by radiation exposure in nuclear reactor accidents. The models are based on the health effects models developed originally by Harvard University (NUREG/CR-4214). These models are revised on the basis of the new information on risk estimates by the reassessment of the radiation dosimetry in Hiroshima and Nagasaki. The models deal with the following effects: (1) early effects models for bone marrow, lungs, gastrointestinal tract, central nervous system, thyroid, skin and reproductive organs, using the Weibull function, (2) late somatic effects models including leukemia and cancers of breast, lungs, thyroid, gastrointestinal tract and so forth, on the basis of the information derived from epidemiological studies on the atomic bomb survivors of Hiroshima and Nagasaki, (3) models for late and developmental effects due to exposure in utero. (author)

  8. Investigation of the radiological impact of reactor accidents under probabilistic aspects

    International Nuclear Information System (INIS)

    Huebschmann, W.; Vogt, S.

    1977-01-01

    An analysis and conceptional investigation have been performed for the accident consequence model of the German reactor risk study. A dynamic atmospheric diffusion model is developed, which is applied in the first stage of the study to all distance ranges, and will be restricted finally to the long distance range. The wind direction and its variations are not taken into account in this model. The program set UFO-BAS calculates the time integrated nuclide concentration in air at any location downwind of the source. A further model which takes into account wind direction variations is being developed. On the basis of the proposals for the calculation of the health effects in the German risk study considerations on the storage requirements were accomplished. By means of these assessments a revised grid of parameters was evaluated. Furthermore, considerations were made for the implementation of an evaluation model, which will be developed by the Institut fuer Unfallforschung. (orig./RW) [de

  9. Assessment of the radiological risks of road transport accidents involving type A-packages

    International Nuclear Information System (INIS)

    Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; Hughes, J.S.; Shaw, K.B.; Hedberg, B.; Simenstad, P.; Svahn, B.; Van Hienen, J.F.A.; Jansma, R.

    1998-10-01

    This document, prepared in the framework of a study for the European Commission, presents the evaluation of the risks of accidents associated to the road transport of type A-packages (primarily packages of radio-pharmaceutic or radiography products) for five countries of the European Union. The annual transport of type A-packages varies considerably from one country to another, some countries being producers of radio-pharmaceutic products, others not. These packages are also very different one from each another: the weight varies generally from 1 to 25 kg and the activity from some Mega-Becquerels to few tens of Giga-Becquerels, the average activity expressed in A 2 is 0,01. (A.L.B.)

  10. Organization of the French emergency teams in the event of a radiological accident

    Energy Technology Data Exchange (ETDEWEB)

    Dumon, F. [Faculte de Pharmacie, 13 - Marseille (France); Pizzocaro, Y. [CSP, Risques Technologiques, 83 - Toulon (France)

    2001-07-01

    Nowadays, the intervention in ionizing environment is increasingly probable. It is still rare, but with the development of the nuclear programme of electricity production which was held in the french past and the significant rise in the use of the radioelements, as well in the medical field as industrial, the radioactive risk cannot be neglected. Technical and human resources, brought by mobile emergency teams called CMIR, were thus implemented to ensure either the safety of only hard-working exposed to the ionizing radiations, but also that of the population. In France, the organization of the public authorities in the event of nuclear accident, fixed by Directives of the Prime Minister which relate to nuclear safety, protection against radiation, the law and order and the civil safety, is described in Particular Plan for Intervention (PPI). (author)

  11. Organization of the French emergency teams in the event of a radiological accident

    International Nuclear Information System (INIS)

    Dumon, F.; Pizzocaro, Y.

    2001-01-01

    Nowadays, the intervention in ionizing environment is increasingly probable. It is still rare, but with the development of the nuclear programme of electricity production which was held in the french past and the significant rise in the use of the radioelements, as well in the medical field as industrial, the radioactive risk cannot be neglected. Technical and human resources, brought by mobile emergency teams called CMIR, were thus implemented to ensure either the safety of only hard-working exposed to the ionizing radiations, but also that of the population. In France, the organization of the public authorities in the event of nuclear accident, fixed by Directives of the Prime Minister which relate to nuclear safety, protection against radiation, the law and order and the civil safety, is described in Particular Plan for Intervention (PPI). (author)

  12. Development of a multi-criteria decision tool for remediation after a nuclear or radiological accident

    Energy Technology Data Exchange (ETDEWEB)

    Luca, Christiano de; Rochedo, Elaine R.R.; Ferreira, Nadya M.P.D., E-mail: christiano_luca@hotmail.com, E-mail: elainerochedo@gmail.com, E-mail: nadya@ime.eb.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The review of accidents involving Nuclear Power Plants or facilities that use or process radioactive sources have raised issues related to the decision-making processes and to the procedures used to reestablish the normal living conditions in the affected areas. Due to the large complexity of the decision processes after accidents, a multi-criteria approach has been recommended to support the choice among the several procedures that may improve the environmental conditions. As part of the process of developing a multi-criteria decision support tool, a questionnaire was created to be fulfilled by experts to derive the relevance of the technical criteria to be considered in the model. At this stage, only the technical criteria related to radiation protection of the public will be focused; legal aspects, costs and public opinion, although relevant in the decision-making process, are beyond the scope of this work. The questionnaire contains 12 questions, each containing 5 degrees of importance. The answers are statically analyzed to generate a multiplicative factor to be included in the multicriteria model. To facilitate the process of distributing the questionnaire to the selected experts and then for a better processing and ordering of the information gathered, a program based on the Hypertext Preprocessor language (PHP) was created; this methodology has been chosen because of its compatibility and security in existing operating systems. The relevance rank showed the long-term dose reduction and the generation of wastes as the most relevant aspects to be considered in selecting remediation strategies for a contaminated area. (author)

  13. Development of a multi-criteria decision tool for remediation after a nuclear or radiological accident

    International Nuclear Information System (INIS)

    Luca, Christiano de; Rochedo, Elaine R.R.; Ferreira, Nadya M.P.D.

    2013-01-01

    The review of accidents involving Nuclear Power Plants or facilities that use or process radioactive sources have raised issues related to the decision-making processes and to the procedures used to reestablish the normal living conditions in the affected areas. Due to the large complexity of the decision processes after accidents, a multi-criteria approach has been recommended to support the choice among the several procedures that may improve the environmental conditions. As part of the process of developing a multi-criteria decision support tool, a questionnaire was created to be fulfilled by experts to derive the relevance of the technical criteria to be considered in the model. At this stage, only the technical criteria related to radiation protection of the public will be focused; legal aspects, costs and public opinion, although relevant in the decision-making process, are beyond the scope of this work. The questionnaire contains 12 questions, each containing 5 degrees of importance. The answers are statically analyzed to generate a multiplicative factor to be included in the multicriteria model. To facilitate the process of distributing the questionnaire to the selected experts and then for a better processing and ordering of the information gathered, a program based on the Hypertext Preprocessor language (PHP) was created; this methodology has been chosen because of its compatibility and security in existing operating systems. The relevance rank showed the long-term dose reduction and the generation of wastes as the most relevant aspects to be considered in selecting remediation strategies for a contaminated area. (author)

  14. Evaluation of release amount of radioactivity from Chernobyl accident and of resulting radiological consequence in China

    International Nuclear Information System (INIS)

    Zhang Yongxing

    1987-01-01

    Three kinds of methods are used to evaluate the release amount from Chernoby1 RBMK-1000 reactor accident, i.e. (1) estimation by comparison with Windscale accident; (2) estimation in terms of the stock in the core; and (3) estimation according to the available monitoring data form adjacent countries such as Poland and Finland. The results obtained are as follows: the release of I-131 was 0.1-1.5 EBq, which is approximately 4-50% of the stock in the core; the release amount of Ru-103 was comparable to that of Cs-137, both approximately 5-10% of that of I-131; the volatile nuclides such as Mo-99, Ru-103, Te-132, Cs-137 etc., were in the order of 0.4 EBq; involatile nuclides were 0.2 EBq; noble gases and other fission products 10 EBq; and the total amount released was about 20 EBq, which taken together 8% of the stock in the core. The radioactive cloud cluster passed through over the area of China in the beginning of May. It was estimated that the total amount of I-131 in air over China area was about 1.6 PB q , Cs-137 about 0.3 PB q , Ru-103 about 0.2 PB q ; the total fallout in the area of China was about 3 PB q for I-131, about 0.1 PB q for Cs-137, about 0.3 PB q for Ru-103. The resulting effective dose equavalent commitment to critical group individual was about 60 μSv, collective effective dose equavalent commitment received by the population of China was about 1 x 10 4 man.Sv

  15. Activities of the Radiological Environmental Division related to the Fukushima accident; Actuaciones de la Division de Medio Ambiente Radiologico derivadas del accidente de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Navarro, T.; Gasco, C.; Robles, B.; Montero, M.

    2011-07-01

    The recent Fukushima accident has shown that the scientific community and the general public is very much interested in and concerned about knowing the possible current and future consequences that an accident of this nature can have in both the local population and the rest of the world. It also reveals that society, even though it is not directly affected, feels that it is affected and demands not only fast, effective responses from national authorities, but also a greater involvement of all international bodies related to Nuclear Safety and to Radiological Protection of the public and the environment and a better coordination between them. (Author)

  16. Thirty years after the radiation accident in Goiânia: the IRD and the learning in the face of tragedy

    International Nuclear Information System (INIS)

    Jansen, L.C.; Razuck, F.B.

    2017-01-01

    The objective of the article is to present some contributions to the learning in the radioprotection area from Goiania accident. A thematic workshop was held, together with the students of the Specialization Course in Radiological Protection and Security of Radioactive Sources, offered by the Institute of Radioprotection and Dosimetry (IRD) and the International Atomic Energy Agency (IAEA), focusing on the IRD action during the accident. Some teachers of the course gave a testimony on what was the greatest legacy of the accident for the radioprotection area. From the analysis of the speeches, a workshop was held to discuss the relevance of the accident. It was sought to evidence the radiological accident as a learning tool in the field of nuclear science, opening space for discussions of a wider knowledge about ionizing radiation. Thus, it is not possible to deny the technological advance and the learning originated from this tragedy in Brazilian soil, understanding that the investigations related to historical aspects of science end up leading to new implications in the teaching of sciences

  17. Legislation in Ukraine about the radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Nasvit, O.

    1998-01-01

    The paper describes the status and consequences of the principal laws of Ukraine concerning the problem of the Chernobyl catastrophe. The Ukrainian authorities have been giving a series of the laws after February, 1991. The system of Chernobyl Laws in Ukraine reflects the rather good intention of the Ukrainian authorities to help the people who suffered from the Chernobyl catastrophe. The system of the Laws includes more than that justified by the scientific base, that is, the combined effect of radioactive exposure and factors of non-radioactive synergism. However, after the Soviet Union collapse, it was found that the Laws were overloaded with social payments and compensations. A number of changes and additions to the Laws caused political struggles. In this situation, the radiological aspect of the problems stepped aside. The radiological survey system in Ukraine provides necessary information on annual doses to the population in the contaminated areas. Despite of the clearly observed reduction of the doses, allocation on the categories of contaminated zones has not been reviewed since 1991. According to the monitoring data, the level of radiation doses of about 50 % of all settlements does not correspond to their present status. What is very important in the present situation is to stop compulsory resettlement. It is necessary to stop to pay compensations for contaminated food products, and introduce a system of benefit to those who produce pure products on contaminated areas. It is expected that on approval of the Ukrainian Parliament it will became a new basis for reviewing of the Chernobyl Laws. The Laws and regulations of Ukraine on radiation protection are on the way to meet international basic safety standards. But there is no experience in the world of dealing with the consequences of such a wide-scale radiation catastrophe. Taking into account the fact that a certain part of the Ukrainian population have to live permanently on the radioactively

  18. Some lessons on radiological protection learnt from the accident at the Fukushima Dai-ichi nuclear power plant

    International Nuclear Information System (INIS)

    Kai, M

    2012-01-01

    The accident at the Fukushima Dai-ichi nuclear power plant released a large quantity of radioactive iodine and caesium into the environment. In terms of radiological protection, the evacuation and food restrictions that were adopted in a timely manner by the authorities effectively reduced the dose received by people living in the affected area. Since late March, the transition from an emergency to an existing exposure situation has been in progress. In selecting the reference exposure levels in some areas under an existing exposure situation, the authorities tried to follow the situation-based approach recommended by the ICRP. However, a mixture of emergency and post-emergency approaches confused the people living in the contaminated areas because the reactor conditions continued to be not completely stable. In deriving the criteria in an existing exposure situation, the regulatory authority selected 20 mSv y −1 . The mothers in the affected area believed that a dose of 20 mSv y −1 was unacceptably high for children since 1 mSv y −1 is the dose limit for the public under normal conditions. Internet information accelerated concern about the internal exposure to children and the related health effects. From some experiences after the accident the following lessons could be learned. The selection of reference doses in existing exposure situations after an accident must be openly communicated with the public using a risk-informed approach. The detriment-adjusted nominal risk coefficient was misused for calculating the hypothetical number of cancer deaths by some non-radiation experts. It would not be possible to resolve this problem unless the ICRP addressed an alternative risk assessment to convey the meaning and associated uncertainty of the risk to an exposed population. A situation-based approach in addition to a risk-informed approach needs to be disseminated properly in order to select the level of protection that would be the best possible under the

  19. A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident

    Energy Technology Data Exchange (ETDEWEB)

    Kereszturi, Andras; Brolly, Aron; Panka, Istvan; Pazmandi, Tamas; Trosztel, Istvan [Hungarian Academy of Sciences, Budapest (Hungary). MTA EK, Centre for Energy Research

    2017-09-15

    For calculation of the radiological consequences of Large Break Loss of Coolant (LBLOCA) events, a set of various computer codes modeling the corresponding physical processes, disciplines and their appropriate subsequent data exchange are necessary. For demonstrating the methodology applied in MTA EK, a LBLOCA event at shut down reactor state - when only limited configuration of the Emergency Core Cooling System (ECCS) is available - was selected. In this special case, fission gas release from a number of fuel pins is obtained from the analyses. This paper describes the initiating event and the corresponding thermal hydraulic calculations and the further physical processes, the necessary models and computer codes and their connections. Additionally the applied conservative assumptions and the Best Estimate Plus Uncertainty (B+U) evaluation applied for characterizing the pin power and burnup distribution in the core are presented. Also, the fuel behavior processes. Finally, the newly developed methodology to predict whether the fuel pins are getting in-hermetic or not is described and the the results of the activity transport and dose calculations are shown.

  20. Canadian Cytogenetic Emergency network (CEN) for biological dosimetry following radiological/nuclear accidents.

    Science.gov (United States)

    Miller, Susan M; Ferrarotto, Catherine L; Vlahovich, Slavica; Wilkins, Ruth C; Boreham, Douglas R; Dolling, Jo-Anna

    2007-07-01

    To test the ability of the cytogenetic emergency network (CEN) of laboratories, currently under development across Canada, to provide rapid biological dosimetry using the dicentric assay for triage assessment, that could be implemented in the event of a large-scale radiation/nuclear emergency. A workshop was held in May 2004 in Toronto, Canada, to introduce the concept of CEN and recruit clinical cytogenetic laboratories at hospitals across the country. Slides were prepared for dicentric assay analysis following in vitro irradiation of blood to a range of gamma-ray doses. A minimum of 50 metaphases per slide were analyzed by 41 people at 22 different laboratories to estimate the exposure level. Dose estimates were calculated based on a dose response curve generated at Health Canada. There were a total of 104 dose estimates and 96 (92.3%) of them fell within the expected range using triage scoring criteria. Half of the laboratories analyzed 50 metaphases in radiological/nuclear emergencies by providing triage quality biological dosimetry for a large number of samples. This network represents an alternate expansion of existing international emergency biological dosimetry cytogenetic networks.

  1. Assessment of radiological impact due to a hypothetical core disruptive accident for PFBR using an advanced atmospheric dispersion system

    International Nuclear Information System (INIS)

    Srinivas, C.V.; Venkatesan, R.; Natarajan, A.

    2004-01-01

    Radiological impact due to air borne effluent dispersion from a hypothetical Core Disruptive Accident (CDA) scenario for Prototype Fast Breeder Reactor (PFBR) at Kalpakkam coastal site is estimated using an advanced system consisting of a 3-d meso-scale atmospheric model and a random walk particle dispersion model. A simulation of dispersion for CDA carried out for a typical summer day on 24th May 2003 predicted development of land-sea breeze circulation and Thermal Internal Boundary Layer (TIBL) at Kalpakkam site, which have been confirmed by observations. Analysis of dose distribution corresponding to predicted atmospheric conditions shows maximum dose from stack releases beyond the site boundary at about 4 km during TIBL fumigation and stable conditions respectively. A multi mode spatial concentration distribution has been noticed with diurnal meandering of wind under land sea breeze circulation. Over a meso-scale range of 25 km, turning of plume under sea breeze and maximum concentration along plume centerline at distances of 3 to 10 km have been noticed. The study has enabled to simulate the more complex meteorological situation that is actually present at the site. (author)

  2. Use of COSYMA in the design of epidemiological studies in case of radiological accidents

    International Nuclear Information System (INIS)

    Mansoux, H.; Verger, P.; Thomassin, A.

    1996-01-01

    COSYMA is a powerful code for the assessment of a wide range of accident consequences. It has been satisfactory because of the possibility to get access to the code itself and to change options like release duration or outputs. COSYMA is a probabilistic code, but, in this application, it has been used in a deterministic way by extracting the results for one weather sequence only. PWR source terms were constructed using the inventory of the COSYMA users intercomparison exercise and release fractions for French nuclear reactors S1, S2, S3. For the reprocessing plant, two source terms were chosen arbitrarily, based on the actual radioactive materials present in the plant and on the radioactive decay of reprocessed PWR fuel (1g Plutonium and 0.01g Curium releases). For the transportation scenarios, several source terms still need to be defined, according to the materials transported, the modes of transportation, and the types of packaging. The post-accidental scenario has identical main options for all installations and source terms. The ingestion pathway was not treated in this study because of its unsatisfactory modeling in COSYMA. The intervention levels for the various countermeasures were drawn from ICRP 40 recommendations Both low and high levels were used for evacuation, sheltering and stable iodine prophylaxis For long term actions, only the low intervention level was applied. (author)

  3. Statutory Instrument No 144 of 1992. Convention on assistance in the case of a nuclear accident or radiological emergency (privileges and immunities) order, 1992

    International Nuclear Information System (INIS)

    1992-02-01

    This Order is made by the power conferred on the Government by Section 42A of the Diplomatic Relations and Immunities Acts, 1967 and 1976. It enables the Government to afford immunity from legal action and exemption from taxes to foreign rescue workers as required under Article 8 of the Convention on Assistance in the case of a Nuclear Accident or Radiological Emergency to which the State is a party

  4. Medical emergency protection in case of radiologic or nuclear accidents in Germany; Medizinischer Notfallschutz bei radiologischen oder nuklearen Notfaellen in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    Port, Matthias [Ulm Univ. (Germany); Institut fuer Radiobiologie der Bundeswehr, Muenchen (Germany)

    2017-07-01

    Radiological or nuclear accidents with an overexposure of ionizing radiation are extremely seldom events in Germany. Even physicians in nuclear medicine working with high-dose radiotherapy will very probably never be confronted with real radiation injuries. This is also true for authorized physicians in the medical care for persons with occupational exposures. A smart radiation protection system provides a comprehensive protection even in accidental and unplanned situations.

  5. Synthesis of public authorities organisation in case of emergency and in a post-event situation (following a nuclear accident or a radiological attack) in France and abroad

    International Nuclear Information System (INIS)

    Kayser, O.

    2010-01-01

    After having briefly recalled how an emergency situation (notably in case of nuclear accident or radiological attack) is taken into account in the organisation of public authorities through specific plans (PPI or plans particuliers d'intervention, intervention specific plans), this report also describes how the situation is handled by these authorities after the end of the emergency situation (i.e. when the risk of new radioactive releases is over). This post-event stage is split into two phases: a transition phase which lasts several weeks or months, and a long term consequence management phase (over months or years). The author first describes the specificities of a nuclear or radiological event (accident or attack). He recalls the global public organisation and the involved actors. For the post-event period, he indicates the various actions, describes the interdepartmental coordination and the various aspects of the program designed to manage accident consequences on the long term. He also describes the roles of permanent bodies, agencies and institutes (ASN, ASND, MSNR, IRSN, INVS, ADEME, AFSSA, Meteo France, CEA, ANDRA, AREVA, EDF, ministries). The last part describes the action of public authorities in case of a nuclear accident occurring abroad. This includes relationship with European and international bodies

  6. Considerations about house decontamination in Goiania: limits and consequences

    International Nuclear Information System (INIS)

    Silva, C.J. da; Delgado, J.U.; Luiz, M.T.B.; Cunha, P.G.; Barros, P.D. de

    1988-01-01

    We are considering some aspects related to the decontamination activities about 50 houses affected by Cs-137 in Goiania city. We described the way these contaminations occurred, the instruments used and the procedures. We also discuss the dose limits establised in the decontamination and the consequences resulting from this action. We call attention to the fact that not only the technical aspects in such activities bu also the psycho-social implications resulting from them are specially important. (author) [pt

  7. Review of Cytogenetic analysis of restoration workers for Fukushima Daiichi nuclear power station accident

    International Nuclear Information System (INIS)

    Suto, Yumiko

    2016-01-01

    Japan faced with the nuclear accident of the Fukushima Daiichi Nuclear Power Station (NPS) caused by the combined disaster of the Great East Japan Earthquake and the subsequent tsunamis on 11 March 2011. National Institute of Radiological Sciences received all nuclear workers who were engaged in emergency response tasks at the NPS and suspected of being overexposed to acute radiation. Biological dosimetry by dicentric chromosome assay was helpful for medical triage and management of the workers. When an unplanned radiation exposure occurs, biological dosimetry based on cytogenetic assays has been used to estimate the absorbed dose in the exposed individual to get useful information for the medical management of radiological casualties with suspected acute radiation syndrome (ARS). Nowadays, more cytogenetic assays to measure chromosomal aberrations, such as micronuclei in bi-nucleated cells, prematurely condensed chromosomes (PCCs) and inter-chromosomal exchanges detected by fluorescence in situ hybridization (FISH) techniques, are available. However, the dicentric chromosome assay (DCA) using peripheral blood lymphocytes is still considered to be the 'gold standard' of biological dosimetry for the radiation emergency medicine. Experimental protocols of DCA has been standardized and shared among laboratories all over the world. In fact, DCA was useful in previous radiation accidents, e.g. the Chernobyl accident in 1986, the Goiania accident in 1987, the JCO criticality accident in 1999 and the Tokyo electric power company (TEPCO) Fukushima Daiichi Nuclear Power Station (NPS) accident in 2011. The recent development of microscopic image analysis system with automatic metaphase finding and capturing functions was helpful for rapid detection of dicentric chromosomes to perform DCA for the Fukushima NPS restoration workers. (author)

  8. EPR Study of Free Radicals in Cotton Fiber for Its Potential Use as a Fortuitous Dosimeter in Radiological Accidents

    International Nuclear Information System (INIS)

    Sudprasert, W.; Insuan, P.; Khamkhrongmee, S.

    2014-01-01

    Electron paramagnetic resonance (EPR) spectroscopy was applied to characterize radiation- induced free radicals in cotton fiber in order to determine the possibility for using cotton as a fortuitous dosimeter in accidental exposures to radiation. Cotton fabrics were irradiated at 0.1, 0.5, 1, 2, 10, 50 and 500 Gy using a 60Co gamma source. The irradiated samples were then stored in the dark under controlled environmental conditions for 1, 15, 35 and 60 days. The EPR spectra were observed in samples using a Bruker EMX X-band spectrometer equipped with a TE102 rectangular cavity. The EPR signal intensities of irradiated samples were determined from peak-to-peak amplitudes of EPR spectra and compared to unirradiated samples. The following optimum parameters were used: modulation frequency,100 kHz; microwave frequency, 9.84 GHz; modulation amplitude, 1.8 mT; microwave power,1.0 mW; time constant, 665 ms; conversion time, 41 ms; and sweep time, 41.98 s. The EPR spectra of unirradiated samples show a singlet line with g = 2.006 due to stable organic radicals pre-existing in the cotton fibers, whereas those of irradiated samples show the same pattern with different signal intensities according to the doses. Irradiation increased the signal intensity in a dose dependent manner. The signal intensity exhibited an exponential decay with storage time from 1 to 60 days. Obviously, the degree of fading of EPR intensity did not depend on the absorbed dose from 0.1-50 Gy. The maximum fading was about 60% at 60 days storage of irradiated samples at all doses. However the post-irradiation signal appeared to be detectable up to 60 days after irradiation. The results indicate the potential of using cotton as a fortuitous dosimeter in radiological accidents.

  9. Simulation of ¹³⁷Cs transport and deposition after the Chernobyl Nuclear Power Plant accident and radiological doses over the Anatolian peninsula.

    Science.gov (United States)

    Simsek, V; Pozzoli, L; Unal, A; Kindap, T; Karaca, M

    2014-11-15

    The Chernobyl Nuclear Power Plant (CNPP) accident occurred on April 26 of 1986, it is still an episode of interest, due to the large amount of radionuclides dispersed in the atmosphere. Caesium-137 ((137)Cs) is one of the main radionuclides emitted during the Chernobyl accident, with a half-life of 30years, which can be accumulated in humans and animals, and for this reason the impacts on population are still monitored today. One of the main parameters in order to estimate the exposure of population to (137)Cs is the concentration in the air, during the days after the accident, and the deposition at surface. The transport and deposition of (137)Cs over Europe occurred after the CNPP accident has been simulated using the WRF-HYSPLIT modeling system. Four different vertical and temporal emission rate profiles have been simulated, as well as two different dry deposition velocities. The model simulations could reproduce fairly well the observations of (137)Cs concentrations and deposition, which were used to generate the 'Atlas of Caesium deposition on Europe after the Chernobyl accident' and published in 1998. An additional focus was given on (137)Cs deposition and air concentrations over Turkey, which was one of the main affected countries, but not included in the results of the Atlas. We estimated a total deposition of 2-3.5 PBq over Turkey, with 2 main regions affected, East Turkey and Central Black Sea coast until Central Anatolia, with values between 10 kBq m(-2) and 100 kBq m(-2). Mean radiological effective doses from simulated air concentrations and deposition has been estimated for Turkey reaching 0.15 mSv/year in the North Eastern part of Turkey, even if the contribution from ingestion of contaminated food and water is not considered, the estimated levels are largely below the 1 mSv limit indicated by the International Commission on Radiological Protection. Copyright © 2014 Elsevier B.V. All rights reserved.

  10. Methodology of radionuclides dis incorporation in people related to nuclear and radiological accidents; Metodologia de desincorporacion de radinuclidos en personas relacionadas con accidentes nucleares y radiologicos

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez F, E. A.

    2014-07-01

    In this paper a classification of the radiological and nuclear accidents is presented, describing which the activities are, where they have occurred, their incidence and the learned lessons in these successes. The radiological accidents in which radioactive materials intervene can occur anywhere, and they are related to no controlled dangerous sources (abandoned, lost, stolen, or found sources), improper use of dangerous industrial and medical sources, exposition and contamination of people in general by an unknown origin, serious over expositions, menaces and willful misconduct, emergencies during transportation of radioactive material. A person can receive a dose of radiation from an external source, because of radioactive material placed on skin or on equipment, or because of ingestion or inhalation of radiological particles. The ingestion or the inhalation of radioactive material can cause an internal dose to the whole body or to a specific organ during a period of time. That is why a description of the processes of incorporation, the stages of incorporation and a description of the biokinetic models are also realized to understand the ingestion, transference and the excretion of the radioactive elements. In order to offer help to a victim of internal contamination, the dosimetric and medical diagnosis is very important. The most important techniques of dosimetric diagnosis are the dosimetry in vivo (cytogenetics and the counting in vivo of the whole body) and the bioassays. These techniques allow obtain data such as the radionuclide, the target organ, the absorbed dose, etc. At the same time, the doctor in charge must be attentive to the patients symptoms and their manifestation time, since they are an indicator, first, the patient suffered an irradiation, and second, of the range esteem of the received radiation dose. These are the parameters that are useful as criterion to decide if a person has to receive some treatment and select the methodologies that

  11. Lessons learned from radiological accidents at medical exposures in radiotherapy; Lições aprendidas com acidentes radiológicos nas exposições médicas em radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Fagundes, J.S.; Ferreira, A.F. [Faculdade Casa Branca, SP (Brazil); Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro, RJ (Brazil); Silva, F.C.A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    An exposure is considered accidental in radiotherapy when there is a substantial deviation in the prescription of treatment. In this work, an analysis of published radiological accidents, both in Brazil and internationally, was performed during medical exposures in radiotherapy treatments, removing the main lessons learned. Of the research carried out, we highlight Brazil with four radiological accidents and one death in the period between 2011 and 2014; the United States of America with 169 accidents with two deaths from 2000 to 2010 and France from 2001 to 2014 had 569 deaths without patients. Lessons learned have been described, for example, that maintenance personnel training should specify limitations or restrictions on the handling or adjustment of critical parts on the accelerator. It is recommended to apply the 10 main lessons learned due to radiological accidents during medical exposures in radiotherapy treatments to avoid future events.

  12. Emergency monitoring strategy and radiation measurements document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    Energy Technology Data Exchange (ETDEWEB)

    Lahtinen, J. [Radiation and Nuclear Safety Authority (STUK) (Finland)

    2006-04-15

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  13. Emergency monitoring strategy and radiation measurements. Working document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2006-04-01

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  14. NOTE: Development of modified voxel phantoms for the numerical dosimetric reconstruction of radiological accidents involving external sources: implementation in SESAME tool

    Science.gov (United States)

    Courageot, Estelle; Sayah, Rima; Huet, Christelle

    2010-05-01

    Estimating the dose distribution in a victim's body is a relevant indicator in assessing biological damage from exposure in the event of a radiological accident caused by an external source. When the dose distribution is evaluated with a numerical anthropomorphic model, the posture and morphology of the victim have to be reproduced as realistically as possible. Several years ago, IRSN developed a specific software application, called the simulation of external source accident with medical images (SESAME), for the dosimetric reconstruction of radiological accidents by numerical simulation. This tool combines voxel geometry and the MCNP(X) Monte Carlo computer code for radiation-material interaction. This note presents a new functionality in this software that enables the modelling of a victim's posture and morphology based on non-uniform rational B-spline (NURBS) surfaces. The procedure for constructing the modified voxel phantoms is described, along with a numerical validation of this new functionality using a voxel phantom of the RANDO tissue-equivalent physical model.

  15. RaCon: a software tool serving to predict radiological consequences of various types of accident in support of emergency management and radiation monitoring management

    International Nuclear Information System (INIS)

    Svanda, J.; Hustakova, H.; Fiser, V.

    2008-01-01

    The RaCon software system, developed by the Nuclear Research Institute Rez, is described and its application when addressing various tasks in the domain of radiation accidents and nuclear safety (accidents at nuclear facilities, transport of radioactive material, terrorist attacks) are outlined. RaCon is intended for the prediction and evaluation of radiological consequences to population and rescue teams and for optimization of monitoring actions. The system provides support to emergency management when evaluating and devising actions to mitigate the consequences of radiation accidents. The deployment of RaCon within the system of radiation monitoring by mobile emergency teams or remote controlled UAV is an important application. Based on a prediction of the radiological situation, RaCon facilitates decision-making and control of the radiation monitoring system, and in turn, refines the prediction based on observed values. Furthermore, the system can perform simulations of evacuation patterns at the Dukovany NPP and at schools in the vicinity of the power plant and can provide support to emergency management should any such situation arise. (orig.)

  16. Steering committee for the management of the post-accidental phase of a nuclear accident or of a radiological situation (CODIRPA). Work group nr 4. Response to health challenges after a radiological accident - Stage report issue nr 2 of 2007 November 5; Synthesis of doctrinal elements and recommendations; Consultative meeting - February 2009; Final report March 2011; Report synthesis

    International Nuclear Information System (INIS)

    Bernier, Marie-Odile; Challeton-de Vathaire, Cecile; Catelinois, Olivier; Pirard, Philippe; Collignon, Albert; Corblet, Sibylle; Empereur Bissonnet, Pascal; Fite, Johanna; Mehl Auget, Isabelle; Fleutot, Jean-Baptiste; Gavel, Yves; Geis-Bonnemains, Nathalie; Geneau, Christian; Guagniere, Bertrand; Janin, Claire; Lang, Thierry; Marielle, Schmitt; N'Diaye, Bakhao; Raoul, Christophe; Ricoux, Christine; Schwoebel, Valerie; Telion, Caroline; Tillier, Claude; Verger, Pierre; Volant, Philippe

    2007-01-01

    A first report describes effects of radiological accidents on health, and possible scenarios (dose assessments, exposed population, health challenges), gives an overview of methods and arrangements used to count exposed populations and to assess received doses, and presents the foreseen reception centres. It describes the health management organisation (medical and psychological care of exposed population, public information), and reports an analysis of health risks associated with the accident. The next document contains a synthesis of doctrinal elements and recommendations regarding information acquisition, the management of health consequences of the accident, the assessment of the health impact. Propositions made by the work group to face health challenges are presented in a Power Point presentation. The final report addresses the context of preparation of the response to a radiological accident in France (studied accidents and scenarios, public health challenges), proposes a chronological synthesis of actions to be undertaken during a preparation phase, an emergency phase, a transition phase, and a long term phase), and a detailed presentation of main actions to be undertaken (medical and psychological care, reception centres, counting, health risk analysis, health information)

  17. Draft bill relating to the IAEA convention of September 26, 1986, on early notification of nuclear accident, and on mutual assistance in care of nuclear accident or radiological emergency (IAEA Conventions on notification and on assistance)

    International Nuclear Information System (INIS)

    1989-01-01

    The purpose of the two Conventions signed in Vienna on Sept. 26, 1986, is to support and improve international cooperation in case of a nuclear accident or a radiological emergency probably involving transfrontier contamination, and to provide the necessary legal framework for cooperation and assistance, as well as a basis for an information system. The bill presented by the Federal Government creates the legal basis for ratification of the Conventions in compliance with Art. 59, paragraph 2, first sentence of the Basic Law. Majority decision. (orig./HP) [de

  18. Recommendations guide in radiological accidents for first respondents, firemen and policemen; Guia de recomendaciones en accidentes radiologicos para primeros respondedores, bomberos y policias

    Energy Technology Data Exchange (ETDEWEB)

    Astudillo, A. J.; Ambriz, J. J. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, 09340 Mexico D. F. (Mexico); Paredes, L. C., E-mail: ajav_x@yahoo.com.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-10-15

    The action guides for the primary task forces of the Firemen Corps and the Public Security Elements, before the presence of radiological accidents are presented. The objective of these guides is to give the recommendations for the initial response to the emergency that fulfills the following criterions: to to Apply with readiness all the reasonable measures to protect the victims and the public, in order to minimizing the radiological and non radiological effects to the health; b) to Retrieve the control of the situation and to mitigate the consequences; c) to Protect the emergency personnel during the response operations; d) to Compile and to protect the information that can be useful to treat the effects to the health, of the victims and public in general, and to prevent that emergencies seemed are repeat in the future; e) to Create and to maintain the public's trust in the response; f) to Establish a base for an action of lingering response, and to Suggest evaluation criterions of the radiological emergency, the organization criterions, operation and surrounding of the emergency area. (Author)

  19. Recommendations guide in radiological accidents for first respondents, paramedical personnel; Guia de recomendaciones en accidentes radiologicos para primeros respondedores, personal paramedico

    Energy Technology Data Exchange (ETDEWEB)

    Astudillo, A. J.; Ambriz, J. J. [Universidad Autonoma Metropolinata, Unidad Iztapalapa, Av. San Rafael Atlixco 186, 09340 Mexico D. F. (Mexico); Paredes, L. C., E-mail: ajav_x@yahoo.com.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2011-10-15

    The lenders of medical services hope to provide the appropriate attention to the patients due to the great variety of scenarios that are presented. One of these involves the patient that has been exposed or contaminated with radioactive materials. Due to this situation the recommendations guide for the primary task forces are presented. Elements of medical response before the radiological accidents presence. The objective of these guides is to give the guidelines for the initial response to the emergency that fulfills the following criterions: a) to Apply with readiness all the reasonable measures to protect the victims and the public, in order to minimizing the radiological and not radiological effects to the health; b) to Save lives and to develop the procedures required in the medical emergency; c) to Treat the injuries caused by the radiation and the resulting injuries of the emergency; d) to Compile and to protect the information that can be useful to treat the effects to the health, of the victims and public in general, and to impede that emergencies seemed are repeat in the future; e) to Create and to maintain the public's trust in the response; f) to Establish a base for an action of lingering response and g) to Suggest evaluation criterions of the radiological emergency, the organization criterions, operation and surrounding of the emergency area. (Author)

  20. Non-radiological consequences to the aquatic biota and fisheries of the Susquehanna River from the 1979 accident at Three Mile Island Nuclear Station

    International Nuclear Information System (INIS)

    Hickey, C.R. Jr.; Samworth, R.B.

    1979-11-01

    The non-radiological consequences to the aquatic biota and fishes of the Susquehanna River from the March 28, 1979 accident at Three Mile Island Nuclear Station were assessed through the post-accident period of July 1979. Thermal and chemical discharges during the period did not exceed required effluent limitations. Several million gallons of treated industrial waste effluents were released into the river which were not of unusual volumes compared with normal operation and were a very small proportion of the seasonally high river flows. The extent and relative location of the effluent plume were defined and the fisheries known to have been under its immediate influence were identified, including rough, forage, and predator/sport fishery species

  1. Use of radiological evaluation system from the Instituto de Radioprotecao e Dosimetria in the analysis of recent radiation accidents

    International Nuclear Information System (INIS)

    Silva, Rodolfo Julio da

    2013-01-01

    The response to an emergency situation involving ionizing radiation requires the joint participation of professionals from various kind of knowledge, belonging to public and private organizations (in the local, state and federal levels). The theme radiation tends to be an additional challenging factor - considering that it's, usually, remembered for its macabre and ominous aspect, in spite of the benefits provided by it - which makes the implementation of actions to protect the public, emergency professionals, the environment and property, very difficult. To this, we can add the complicating factor that, in most cases, the technician (holder of basic or advanced on the subject) is far !Tom the place where this action unfolds. The accident/incident takes the form of a radioactive source (sometimes orphaned, one that gone astray or even stolen) that is found by a person unaware of the risks to which they are being exposed or, let not forget about it, the non-observance of safety standards in industries and workplaces, by their own operators. Thus, before integrating emergency response plans with conventional plans specific to the prompt response to radiological emergencies, it is necessary that some measures had been anticipated and that some actions had, already, been planned - with the intention of mitigate health, psychological and economical damage, in ali of kind. To do this, since in the course of the second decade of the second millennium, and since you own a portable personal computer (Note or Netbook), or even with a mobile device (cellular) with a bit more resources, both of them previously updated, a responder (or even a qualified technician that is next to that fact) may already guide, at least, about a safety distances !Tom the source. Since he had knowledge about some characteristics of the source (its individual data), he can plan ahead about the possible serious situation that unfolds itself and emergency responders will find, when it get to the site

  2. Monte Carlo dose reconstruction in case of a radiological accident: application to the accident in Chile in December 2005; Reconstitution de dose par calcul Monte Carlo en cas d'accident radiologique: application a l'accident du Chili de decembre 2005

    Energy Technology Data Exchange (ETDEWEB)

    Huet, C.; Clairand, I.; Trompier, F.; Bottollier-Depois, J.F. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Dir. de la Radioprotection de l' Homme, 92 - Fontenay aux Roses (France); Bey, E. [Hopital d' Instruction des Armees Percy, 92 - Clamart (France)

    2007-10-15

    Following a radiological accident caused by a gamma-graphy source in Chile in December 2005 involving one victim, I.R.S.N. was contacted to perform the dosimetric reconstruction of the accident using numerical simulation. Tools developed in the laboratory, associating anthropomorphic mathematic or voxel phantoms with the Monte Carlo calculation code m.c.n.p.x., were used in order to determine the dose distribution on the left buttock and absorbed doses to critical organs. The dosimetric mapping show that the absorbed at the skin surface is very high (1900 Gy) but drops rapidly at deep. At a depth of 5 cm, it is 20 Gy. Calculations performed with a mathematical phantom indicate that average doses to the critical organs are relatively low. Moreover, possible bone marrow sites for puncture are identified. Based on the dosimetric mapping, an excision measuring 5 cm in depth by 10 cm in diameter was performed on the left buttock of the victim. (authors)

  3. Transport of radioactive wastes to the planned final waste repository Konrad: Radiation exposure resulting from normal transport and radiological risks from transport accidents

    International Nuclear Information System (INIS)

    Lange, F.; Fett, H.J.; Gruendler, D.; Schwarz, G.

    1993-01-01

    Radiation exposures of members of critical groups of the general population and of transport personnel resulting from normal transport of radioactive wastes to the planned final waste repository Konrad have been evaluated in detail. By applying probabilistic safety assessment techniques radiological risks from transport accidents have been analysed by quantifying potential radiation exposures and contaminations of the biosphere in connection with their expected frequencies of occurrence. The Konrad transport study concentrates on the local region of the waste repository, where all transports converge. (orig.) [de

  4. An assessment of the radiological consequences of the Greek Research Reactor's design basis accident with the use of low enriched uranium

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1985-09-01

    An analysis of the radiological consequences of the design basis accident in the low enriched uranium fueled 5 MW Greek Research Reactor is presented. For the source term thirty-five isotopes are taken into consideration and conservative figures of fission product release are adopted. To estimate the reactor's consequences for Athens population a CRAC2 consequence model version is used. The results indicate that limiting dose and effects are respectively the thyroid dose and the thyroid effects induced in the 3,081,000 inhabitants of Athens region. (author)

  5. Principles for establishing intervention levels for the protection of the public in the event of a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    1985-01-01

    This Safety Guide is based on the report of an Advisory Group which met in Vienna in October 1984 in order to develop guidance on the radiation protection principles concerning emergency response planning and the establishment of intervention levels to be applied for the protection of the public in the event of a nuclear accident or radiological emergency. It considers the relationship between emergency response planning and various accident sequences, examines the pathways for radiation exposure and the sources of advice to decision makers during each of the three main accident phases, and specifies the dosimetric quantities that apply. The relevant pathological effects that must be protected against are summarized and the measures that may need to be implemented to provide protection with respect to each of the exposure pathways are discussed. It sets out the principles which underline decisions on intervention planning for each of the accident phases, gives guidance on dose values for the introduction of relevant protective measures and considers the application of cost-benefit analysis and the determination of the optimum dose level at which to withdraw protective measures

  6. Simulation of {sup 137}Cs transport and deposition after the Chernobyl Nuclear Power Plant accident and radiological doses over the Anatolian Peninsula

    Energy Technology Data Exchange (ETDEWEB)

    Simsek, V.; Pozzoli, L.; Unal, A.; Kindap, T., E-mail: kindap@itu.edu.tr; Karaca, M.

    2014-11-15

    The Chernobyl Nuclear Power Plant (CNPP) accident occurred on April 26 of 1986, it is still an episode of interest, due to the large amount of radionuclides dispersed in the atmosphere. Caesium-137 ({sup 137}Cs) is one of the main radionuclides emitted during the Chernobyl accident, with a half-life of 30 years, which can be accumulated in humans and animals, and for this reason the impacts on population are still monitored today. One of the main parameters in order to estimate the exposure of population to {sup 137}Cs is the concentration in the air, during the days after the accident, and the deposition at surface. The transport and deposition of {sup 137}Cs over Europe occurred after the CNPP accident has been simulated using the WRF-HYSPLIT modeling system. Four different vertical and temporal emission rate profiles have been simulated, as well as two different dry deposition velocities. The model simulations could reproduce fairly well the observations of {sup 137}Cs concentrations and deposition, which were used to generate the ‘Atlas of Caesium deposition on Europe after the Chernobyl accident’ and published in 1998. An additional focus was given on {sup 137}Cs deposition and air concentrations over Turkey, which was one of the main affected countries, but not included in the results of the Atlas. We estimated a total deposition of 2–3.5 PBq over Turkey, with 2 main regions affected, East Turkey and Central Black Sea coast until Central Anatolia, with values between 10 kBq m{sup −2} and 100 kBq m{sup −2}. Mean radiological effective doses from simulated air concentrations and deposition has been estimated for Turkey reaching 0.15 mSv/year in the North Eastern part of Turkey, even if the contribution from ingestion of contaminated food and water is not considered, the estimated levels are largely below the 1 mSv limit indicated by the International Commission on Radiological Protection. - Highlights: • Chernobyl Nuclear Power Plant accident

  7. Behaviour of {sup 137} Cs in oxysoils and Goiania soil

    Energy Technology Data Exchange (ETDEWEB)

    Wassermann, Maria Angelica [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    {sup 137} Cs soil-to-plant transfer factor obtained in oxy soils accidentally contaminated in Goiania and artificially contaminated shows that these soils present higher transfer when compared with data obtained under temperate climates. These differences were discussed in the light of pedology and geochemical partitioning. Some tropical soil characteristics as acidity, low available nutritive elements and low content of 2:1 clay type seems determine high availability for {sup 137} Cs. Results of sequential extraction showed {sup 137} Cs weakly bound to soil components and underline the importance of Fe oxides in the control of {sup 137} Cs availability in tropical climates. (author) 25 refs., 2 figs., 2 tabs.

  8. The IAEA Conventions on Early Notification of a Nuclear Accident and on Assistance in the Case of a Nuclear Accident or Radiological Emergency

    International Nuclear Information System (INIS)

    Moser, B.

    1989-01-01

    This article provides a comprehensive analysis of the provisions of both IAEA Conventions. Special attention is paid to the rules of the Convention on Early Notification which identify the events subject to notification and the content and addresses of the information to be provided with regard to a nuclear accident, as well as to the provisions of the Convention on Assistance concerning the request and grant of international assistance with regard to a nuclear accident and the duties attributed in this field to the IAEA. The author also considers the liability questions raised by that Convention. (NEA) [fr

  9. Thirty years after the radiation accident in Goiânia: the IRD and the learning in the face of tragedy; Trinta anos do acidente de Goiânia: a atuação do IRD e o aprendizado diante da tragédia

    Energy Technology Data Exchange (ETDEWEB)

    Jansen, L.C.; Razuck, F.B., E-mail: fernandor@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Divisão de Ensino

    2017-07-01

    The objective of the article is to present some contributions to the learning in the radioprotection area from Goiania accident. A thematic workshop was held, together with the students of the Specialization Course in Radiological Protection and Security of Radioactive Sources, offered by the Institute of Radioprotection and Dosimetry (IRD) and the International Atomic Energy Agency (IAEA), focusing on the IRD action during the accident. Some teachers of the course gave a testimony on what was the greatest legacy of the accident for the radioprotection area. From the analysis of the speeches, a workshop was held to discuss the relevance of the accident. It was sought to evidence the radiological accident as a learning tool in the field of nuclear science, opening space for discussions of a wider knowledge about ionizing radiation. Thus, it is not possible to deny the technological advance and the learning originated from this tragedy in Brazilian soil, understanding that the investigations related to historical aspects of science end up leading to new implications in the teaching of sciences.

  10. Spreading of 137 C in the Goiania urban area by resuspension and transport of surface soil

    International Nuclear Information System (INIS)

    Rio, Monica Pires do; Amaral, Eliana

    2002-01-01

    The resuspension of surface soil was considered the mechanism responsible by the spreading of 137 Cs after the Goiania accident, which affected an urban area of about 1 km 2 . Studies on the transport of 137 Cs associated to the surface soil were performed in a house located at 57 th Street, close to the main focus of contamination, from 05/89 to 07/00. Periodically, samples of surface soil and soil profile were collected at the house yards and street dust sampling at representative locations was performed in order to know the extension of the contamination in the city. The soil profile samples have shown the low mobility of 137 Cs in deep layers of the soil, although a slight long-term decrease of the 137 Cs activity concentration in the surface soil were observed. The 137 Cs activity concentration in the street dust samples also decrease with time, suggesting a natural dilution of the contamination in those samples; higher values were only found in few locations close to the foci of primary deposition and no additional spreading of the radionuclide is expected to occur from that area. Street dust sampling is a suitable method to assess the spreading of caesium in urban environment. (author)

  11. Status of the Real-time On-line Decision Support (RODOS) system for off-site emergency management after nuclear and radiological accidents

    International Nuclear Information System (INIS)

    Raskov, W.; Ehrhardt, J.; Landman, C.; Pasler-Sauer, J.

    2006-01-01

    Under the auspices of its EURATOM Research Framework Programmes, the European Commission (EC) has supported the development of the comprehensive decision support system RODOS (Real-time On-line Decision Support) for off-site emergency management after nuclear accidents for more than a decade. Many national research programmes, research institutes and industrial collaborators contributed to the project, in particular the German Ministry of Environment, Nature Conservation and Reactor Safety (B MU). The RODOS system can be applied to accidental releases into the atmosphere and various aquatic environments within and across Europe. It provides coherent support before, during and after such a release to assist analysis of the situation and decision making about short and long-term countermeasures for mitigating the consequences with respect to health, the environment, and the economy. Appropriate interfaces exist with local and national radiological monitoring data systems, meteorological measurements and forecasts, and for the adaptation to local, regional and national conditions in Europe. Within the European Integrated Project EURANOS of the sixth Framework Programme, the RODOS system is being enhanced, among others, for radiological emergencies such as dirty bombs attacks, transport accidents and satellite crashes by extensions of the nuclide list, the source term characteristics and the atmospheric dispersion model

  12. Radiological hazards

    International Nuclear Information System (INIS)

    Hamilton, M.

    1984-01-01

    The work of the (United Kingdom) National Radiological Protection Board is discussed. The following topics are mentioned: relative contributions to genetically significant doses of radiation from various sources; radon gas in non-coal mines and in dwelling houses; effects of radiation accidents; radioactive waste disposal; radiological protection of the patient in medicine; microwaves, infrared radiation and cataracts; guidance notes for use with forthcoming Ionising Radiations Regulations; training courses; personal dosimetry service; work related to European Communities. (U.K.)

  13. Radiological aspects of nuclear accident scenarios. Volume 2 the Rade-Aid system post-Chernobyl action

    International Nuclear Information System (INIS)

    Sinnaeve, J.

    1991-01-01

    In the event of a nuclear accident, there is a need for a rapid assessment of the resulting levels of environmental contamination in order to facilitate decisions on possible countermeasures. Volume 2 describes the RADE-AID project to develop a computer system which can be used to support the formulation of decisions on countermeasures following an accidental release of radionuclides. The system is intended as an aid following an actual accident and a tool for assistance in planning and training

  14. 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)

  15. PREPARE. Innovative integrated tools and platforms for radiological emergency preparedness and post-accident response in Europe

    International Nuclear Information System (INIS)

    Duranova, T.; Bohunova, J.; Raskob, W.; Schneider, T.; Gering, F.; Charron, S.; Zhelezniak, M.; Andronopoulo, S.; Heriard-Dubreuil, G.; Camps, J.

    2014-01-01

    The PREPARE project that started February 2013 and will end beginning of 2016, aims to close gaps that have been identified in nuclear and radiological preparedness in Europe following the first evaluation of the Fukushima disaster. In this abstract the PREPARE project is described. (authors)

  16. Reconstructive dosimetry of radiological accidents - study of a brazilian case of industrial gamma radiography; Dosimetria reconstrutiva de acidentes radiologicos - estudo de um caso brasileiro de gamagrafia industrial

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Francisco Cesar Augusto da; Hunt, John G.; Ramalho, Adriana [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Pinto, Livia M.F. Amalfi [ARCtest - Servicos Tecnicos de Inspecao e Manutencao Industrial Ltda., Paulinia, SP (Brazil)]. E-mail: protecao@arctest.com.br

    2002-07-01

    On May 2000, an industrial gamma radiography operator, during a maintenance work of a {sup 60}Co irradiator, has suffered a radiological accident with severe consequences to the left hand. The experts of the High Doses Analysis Group (GADE/IRD/CNEN) initiated the reconstructive dosimetry for the radiation dose estimation, in order to determine the real dose received by the operator, and to help the medical evaluation for prescribing the medical procedures for treatment of the involved victim. This paper presents the reconstructive dosimetry performed through the determination of the radiation doses of the operator, based on theoretical, experimental and computational methods. For the computer methods, a program for the calculation of external doses were used, based on the Monte Carlo method, and a human body simulator composed by voxels. The values of effective and equivalent doses are also presented which has caused severe lesions on the operator hand.

  17. Ten years of work in Cuban Program to children from areas affected of Chernobyl accidents

    International Nuclear Information System (INIS)

    Garcia, Omar; Medina J, Julio

    2001-01-01

    In April of 2000 the Cuban program for specialised medical attention to children from areas affected by the radioactive contamination from the Chernobyl accident completed 10 years of work. In the program had been assisted more than 18 000 children and adults, among them 50 Brazilians related with the Goiania accident. A group of medical procedures and dosimetric, biomedical and psychological investigations have been carried out in the program. The main significant medical attention activities are the treatment of haematological disorders, among them, 120 leukaemia, the realisation of bone marrow transplants and the treatment of endocrinological and neoplasic illnesses. The dosimetric studies has allowed to create a database that accumulates information about internal contamination for 137Cs, internal, external, and total doses, of 7000 children. The analysis of the behaviour of all the medical information that is generated in the program in function of the contamination of the land and of the internal contamination of the children is also performed. The program has accumulated an experience of interest for physicians, psychologists and radiological emergencies experts.(author)

  18. Radiological aspects of nuclear accident scenarios. Volume 1 real-time emergency response systems post-Chernobyl action

    International Nuclear Information System (INIS)

    Sinnaeve, J.

    1991-01-01

    In the event of a nuclear accident, there is a need for a rapid assessment of the resulting levels of environmental contamination in order to facilitate decisions on possible countermeasures. Volume 1 of this report covers the development of numerical models, in the form of software packages, to simulate atmospheric transport and deposition over various distances, and techniques for estimation of the resulting doses

  19. Radiation risk perception by radiation professionals. Survey results just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant

    International Nuclear Information System (INIS)

    Miura, Miwa; Hayashida, Rika; Takao, Hideaki; Matsuda, Naoki; Ono, Koji

    2013-01-01

    From October to December 2010, just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant, 71 radiation professionals belonging to the radiation facilities in Japan were asked what they consider as a 'safe' dose of radiation for themselves, their spouse, parents, children, brothers and friends. Although the 'safe' dose varied widely from less than 1 mSv/y to higher than 100 mSv/y, the average dose was 35.6 mSv/y that was around the middle point between the exposure dose limits for annual average (20 mSv/y) and for any single year (50 mSv/y). Similar results were obtained from another surveys for the members of Japan Radioisotope Association (36.9 mSv/y) and for the Oita Prefectural Hospital (36.8 mSv/y). Among the family members and friends, the minimum average 'safe' dose was 8.5 mSv/y for children, to whom 50% of responders claimed the 'safe' dose less than 1 mSv. Gender, age and specialty of the responder also affected the 'safe' dose. These findings suggest that the perception of radiation risk varies widely and that the legal exposure dose limit derived from the regulatory science may act as an anchor of safety even in radiation professionals. The different level of risk perception for different target groups in radiation professionals appears similar to those in non-professional whole population. The gap between these characteristics of real radiation professionals and the generally accepted picture of radiation professionals might take a part in a state of confusion after the radiological accident. (author)

  20. WSPEEDI (worldwide version of SPEEDI): A computer code system for the prediction of radiological impacts on Japanese due to a nuclear accident in foreign countries

    Energy Technology Data Exchange (ETDEWEB)

    Chino, Masamichi; Yamazawa, Hiromi; Nagai, Haruyasu; Moriuchi, Shigeru [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Ishikawa, Hirohiko

    1995-09-01

    A computer code system has been developed for near real-time dose assessment during radiological emergencies. The system WSPEEDI, the worldwide version of SPEEDI (System for Prediction of Environmental Emergency Dose Information) aims at predicting the radiological impact on Japanese due to a nuclear accident in foreign countries. WSPEEDI consists of a mass-consistent wind model WSYNOP for large-scale wind fields and a particle random walk model GEARN for atmospheric dispersion and dry and wet deposition of radioactivity. The models are integrated into a computer code system together with a system control software, worldwide geographic database, meteorological data processor and graphic software. The performance of the models has been evaluated using the Chernobyl case with reliable source terms, well-established meteorological data and a comprehensive monitoring database. Furthermore, the response of the system has been examined by near real-time simulations of the European Tracer Experiment (ETEX), carried out over about 2,000 km area in Europe. (author).