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)

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

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)

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

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)

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)

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

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)

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)

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

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)

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

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.

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

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

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

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

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

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

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

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)

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

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.)

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

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

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

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

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)

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)

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)

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

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

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)

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

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)

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

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

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

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

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.

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.

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

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)

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

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

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.)

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)

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

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.

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.

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

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

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

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)

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.

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

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.

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)

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)

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

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

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

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

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

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)

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)

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

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

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)

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

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

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)

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)

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).

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

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)

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

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

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)

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)

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

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

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

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.)

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)

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.

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.

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

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

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

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)

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)

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

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

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)

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

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

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

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.)

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

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

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

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

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

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

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)

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)

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

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.

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

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)

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

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.)

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

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

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.

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

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

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

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)

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)

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)

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.

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

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)

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

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

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)

Direct measurements for highly-exposed TEPCO workers and NIRS first responders involved in the Fukushima NPS accident

Energy Technology Data Exchange (ETDEWEB)

Nakano, Takashi; Kim, Eunjoo; Akahane, Keiichi; Tominaga, Takako; Tatsuzaki, Hideo; Kurihara, Osamu; Sugiura, Nobuyuki [National Inst. of Radiological Sciences, Chiba (Japan)

2012-11-15

Direct measurements for internal dose estimates were performed at National Institute of Radiological Sciences (NIRS) on seven highly exposed workers of Tokyo Electric Power Company (TEPCO) and eight NIRS staff members who were first responders to the accident at the TEPCO Fukushima Daiichi Nuclear Power Station. For the TEPCO workers, the measurements were performed by both the whole-body counting and thyroid counting. The average effective half-life values of {sup 131}I in the thyroid and of {sup 134}Cs and {sup 137}Cs in the body were 7.8 days, 92.0 days and 104.3 days, respectively. These values were consistent with biokinetic models proposed by the International Commission on Radiological Protection (ICRP). For the NIRS staff members, the thyroid counting was made on the day when they had returned. The amount of {sup 131}I that was detected in the thyroid of all the eight subjects was small ({approx}100 Bq) even though they went to places near the site of the accident in its early stage. This level was found to be comparable to those of other NIRS staff members who stayed in the Chiba area (about 200 km south of the reactor) during the early stage of the accident. (author)

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

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)

Accidents in radiotherapy: Lack of quality assurance?

International Nuclear Information System (INIS)

Novotny, J.

1997-01-01

About 150 radiological accidents, involving more than 3000 patients with adverse effects, 15 patient's fatalities and about 5000 staff and public exposures have been collected and analysed. Out of 67 analysed accidents in external beam therapy 22% has been caused by wrong calculation of the exposure time or monitor units, 13% by inadequate review of patient's chart, 12% by mistakes in the anatomical area to be treated. The remaining 35% can be attributed to 17 different causes. The most common mistakes in brachytherapy were wrong activities of sources used for treatment (20%), inadequate procedures for placement of sources applicators (14%), mistakes in calculating the treatment time (12%), etc. The direct and contributing causes of radiological accidents have been deduced from each event, when it was possible and categorized into 9 categories: mistakes in procedures (30%), professional mistakes (17%), communication mistakes (15%), lack of training (8.5%), interpretation mistakes (7%), lack of supervision (6%), mistakes in judgement (6%), hardware failures (5%), software and other mistakes (5.5%). Three types of direct and contributing causes responsible for almost 62% of all accidents are directly connected to the quality assurance of treatment. The lessons learnt from the accidents are related to frequencies of direct and contributing factors and show that most of the accident are caused by lack, non-application of quality assurance (QA) procedures or by underestimating of QA procedures. The international system for collection of accidents and dissemination of lessons learnt from the different accidents, proposed by IAEA, can contribute to better practice in many radiotherapy departments. Most of the accidents could have been avoided, had a comprehensive QA programme been established and properly applied in all radiotherapy departments, whatever the size. (author)

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

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

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

International Nuclear Information System (INIS)

2015-08-01

This technical volume describes the consequences associated with radioactivity and radiation from the accident at the Fukushima Daiichi nuclear power plant (NPP) for people and the environment. A number of international organizations have already issued reports on the potential health and environmental consequences of the accident, notably the World Health Organization (WHO) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The intention of the assessments presented in this volume is to build on their work, using more recent data where available. Quantitative information arising from both personal and environmental monitoring has been provided by the Government of Japan. Section 4.1 provides the best estimates of the magnitude and form of radioactive releases during the accident to the atmosphere and directly into the surrounding sea. It also explains the movement of the discharged radionuclides through air and water and the eventual deposition of the atmospheric activity on land in Japan and other countries worldwide, as well as on the open oceans. The goal is to provide a consolidated repository of information on releases to, and levels of radionuclides in, the environment. Some of this information is used in the analyses in subsequent sections of this volume. Section 4.2 gives an overview of exposures to the main groups of emergency workers at the Fukushima Daiichi NPP, to groups of off-site workers and to members of the public. Where sufficient data are available, average effective dose and thyroid equivalent doses derived from personal measurements are compared with the results of previous assessments for specific locations, population groups and time periods. Section 4.3 summarizes relevant aspects of the system of radiation protection in place at the time of the accident. It includes an overview of the legislation and guidance used to implement the radiation protection framework in Japan. This section also provides a

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.

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)

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

not only in form of text but also images or even films. It is however interesting, that the same communication system can stand as a basis for integrating all elements (a)-(d) of the system. An approach of this type has been investigated in a prototype system for a big chemical plant 'Chemical Works Police SA', located in the north-western part of Poland. The main idea lies in the development of central message server, which allows for: bringing up to date Information about radiological situation an numerical maps coming from decision support systems and radiological monitoring; bringing up to date information about current status of emergency action; communication by sending and receiving messages, images, maps etc.; rapid access to all elements of contingency plans, defining responsibilities and possible actions of the key actors of the emergency scene. This is, in a sense, equivalent with building a distributed decision support system. The whole system can be seen a set of tools and a virtual container for these tools to support the management of emergency situations after a radiological accident. The container is called virtual as it will be available, through a web application server, to the users (operators and emergency managers, decision makers, experts, public) independently from the respective geographical locations and from the hardware/software resources used. Software tools useful for developing such a system are usually based an object-oriented methodology and make use of distributed and/or parallel computing. This approach will allow for effective management of crisis situation even in case of more complicated organizational structure as it makes possible to undertake quick and reasonable decision by group of responsible persons. One of the attractive issues of this solution is also a possibility of making quick and reliable analysis of crisis situation by experts not directly present in emergency centres. Their analysis and suggestion for further

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)

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

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)

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)

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

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)

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

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

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

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

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

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

Direct radiological magnification in experimental medicine

International Nuclear Information System (INIS)

Poulsen Nautrup, C.; Berens von Rautenfeld, D.

1991-01-01

Some aspects of direct radiological magnification in experimental medicine are shown by teratological investigations of the fetal rat skeleton and by indirect lymphadenography in rabbits. A combination of microfocal radiography and high-resolution non-screen films or digital image processing allows the evaluation of structures with a minimum size of 5 μm. Pseudo-3D images correlate directly with scanning electron micrographs of equivalent casts. Therefore radiography with direct magnification can make difficult preparations and time-consuming staining processes unnecessary. Besides saving time, the main advantage of this method is the amount of new information it yields. For the first time, for example, the filling mechanism becomes visible even in minute vessels, such as the intranodal sinuses, which measure about 10 μm. Hitherto, we have only been able to infer this mechanism from histological specimens. A further benefit of direct radiological magnification over the conventional microscopical method is the smaller number of experimental animals needed. (orig.) [de

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)

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

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

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.)

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)

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

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

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)

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)

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.

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.

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

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

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.

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.

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

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)

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)

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.

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

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.)

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.

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)

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

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)

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

Radiological assessment and optimization

International Nuclear Information System (INIS)

Zeevaert, T.; Sohier, A.

1998-01-01

The objectives of SCK-CEN's research in the field of radiological assessment and optimization are (1) to implement ALARA principles in activities with radiological consequences; (2) to develop methodologies for radiological optimization in decision-aiding; (3) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (4) to develop methods and programmes to assist decision-makers during a nuclear emergency; (5) to support the policy of radioactive waste management authorities in the field of radiation protection; (6) to investigate computer codes in the area of multi criteria analysis; (7) to organise courses on off-site emergency response to nuclear accidents. Main achievements in these areas for 1997 are summarised

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

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

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

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)

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

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

Management of contaminated territories -- radiological principles and practice

International Nuclear Information System (INIS)

Hedemann-Jensen, P.; Belyaev, S.T.; Demin, V.F.; Rolevich, I.V.; Likhtariov, I.A.; Kovgan, L.N.; Bariakhtar, V.G.

1996-01-01

. The numerical values of these action levels are not directly comparable to international numerical guidance, but they seem not to be in direct conflict. Unresolved issues have been identified to be the interaction between radiological and non-radiological actors in decision-making. Both radiological and non-radiological factors will influence the level of protective actions being introduced. Social-psychological countermeasures are a new category of action, in the sense that social protection philosophy has not yet been developed to fully include their application after a nuclear accident. It has been suggested that the inclusion of such countermeasures into the intervention decision making framework should be as a part of the radiation protection framework. It is argued here that optimization of the overall health protection is not a question of developing radiation protection philosophy to fully include socio-psychological factors. It is rather a question of including these factors - in parallel with the radiological responsibility factors - in cooperation between radiation protection experts and psychological specialists under the responsibility of the decision maker. The overall optimization of the total health protection is thus the responsibility of the decision maker(s) with guidance from radiation protection experts as well as experts in the field of social and psychological sciences

Management of Radioactive Waste after a Nuclear Power Plant Accident

International Nuclear Information System (INIS)

Strand, Per; Laurent, Gerard; Rindo, Hiroshi; Georges, Christine; Ito, Eiichiro; Yamada, Norikazu; Iablokov, Iuri; Kilochytska, Tatiana; Jefferies, Nick; Byrne, Jim; Siemann, Michael; Koganeya, Toshiyuki; Aoki, Hiroomi

2016-01-01

The NEA Expert Group on Fukushima Waste Management and Decommissioning R and D (EGFWMD) was established in 2014 to offer advice to the authorities in Japan on the management of large quantities of on-site waste with complex properties and to share experiences with the international community and NEA member countries on ongoing work at the Fukushima Daiichi site. The group was formed with specialists from around the world who had gained experience in waste management, radiological contamination or decommissioning and waste management R and D after the Three Mile Island and Chernobyl accidents. This report provides technical opinions and ideas from these experts on post-accident waste management and R and D at the Fukushima Daiichi site, as well as information on decommissioning challenges. Chapter 1 provides general descriptions and a short introduction to nuclear accidents or radiological contaminations; for instance the Chernobyl NPP accident, the Three Mile Island Unit 2 accident and the Windscale fire accident. Chapter 2 provides experiences on regulator-implementer interaction in both normal and abnormal situations, including after a nuclear accident. Chapter 3 provides experiences on stakeholder involvement after accidents. These two chapters focus on human aspects after an accident and provide recommendations on how to improve communication between stakeholders so as to resolve issues arising after unexpected nuclear accidents. Chapters 4, 5 and 6 provide information on technical issues related to waste management after accidents. Chapter 4 focuses on the physical and chemical nature of the waste, Chapter 5 on radiological characterisation, and Chapter 6 on waste classification and categorisation. The persons involved in waste management after an accident should address these issues as soon as possible after the accident. Chapters 7 and 8 also focus on technical issues but with a long-term perspective of the waste direction in the future. Chapter 7 relates

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

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)

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

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)

Radiological Dispersion Devices: are we prepared?

Energy Technology Data Exchange (ETDEWEB)

Sohier, Alain [Decision Strategy Research Department (Radiation Protection Division), Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium)]. E-mail: asohier@sckcen.be; Hardeman, Frank [Decision Strategy Research Department (Radiation Protection Division), Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium)

2006-07-01

Already before the events of September 11th 2001 concern was raised about the spread of orphan sources and their potential use in Radiological Dispersion Devices by terrorist groups. Although most of the simulated scenarios foresee a rather limited direct health impact on the population, the affected region would suffer from the indirect consequences such as social disruption, cleanup requirements and economic costs. The nature of such a radiological attack would anyway be different compared to conventional radiological accidents, basically because it can happen anywhere at any time. Part of the response resides in a general preparedness scheme incorporating attacks with Radiological Dispersion Devices. Training of different potential intervention teams is essential. The response would consist of a prioritised list of actions adapted to the circumstances. As the psychosocial dimension of the crisis could be worse than the purely radiological one, an adapted communication strategy with the public aspect would be a key issue.

Radiological Dispersion Devices: are we prepared?

International Nuclear Information System (INIS)

Sohier, Alain; Hardeman, Frank

2006-01-01

Already before the events of September 11th 2001 concern was raised about the spread of orphan sources and their potential use in Radiological Dispersion Devices by terrorist groups. Although most of the simulated scenarios foresee a rather limited direct health impact on the population, the affected region would suffer from the indirect consequences such as social disruption, cleanup requirements and economic costs. The nature of such a radiological attack would anyway be different compared to conventional radiological accidents, basically because it can happen anywhere at any time. Part of the response resides in a general preparedness scheme incorporating attacks with Radiological Dispersion Devices. Training of different potential intervention teams is essential. The response would consist of a prioritised list of actions adapted to the circumstances. As the psychosocial dimension of the crisis could be worse than the purely radiological one, an adapted communication strategy with the public aspect would be a key issue

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

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.)

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.

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

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)

Overview of Brazilian industrial radiography accidents with cutaneous radiation syndrome

International Nuclear Information System (INIS)

Lima, C.M.A.; Silva, F.C.A. da

2017-01-01

It is well documented that industrial radiography is related to radiological accidents, which makes it the highest potential risk for human health. More than 80 radiological accidents happened in the world that includes 6 Brazilian accidents with Cutaneous Radiation Syndrome. Five of them happened with 192 Ir and one with 60 Co radioactive sources. Nineteen members of the public and 8 radiographers were involved. All of them suffered severe hands and fingers injuries. The Brazilian radiological accident happened in 1985 with 16 persons is analyzed showing causes, consequences, radiation doses and lessons learned. (author)

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)

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)

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)

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

Overview of Brazilian industrial radiography accidents with cutaneous radiation syndrome

Energy Technology Data Exchange (ETDEWEB)

Lima, C.M.A.; Silva, F.C.A. da, E-mail: dasilva@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

It is well documented that industrial radiography is related to radiological accidents, which makes it the highest potential risk for human health. More than 80 radiological accidents happened in the world that includes 6 Brazilian accidents with Cutaneous Radiation Syndrome. Five of them happened with {sup 192}Ir and one with {sup 60}Co radioactive sources. Nineteen members of the public and 8 radiographers were involved. All of them suffered severe hands and fingers injuries. The Brazilian radiological accident happened in 1985 with 16 persons is analyzed showing causes, consequences, radiation doses and lessons learned. (author)

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

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)

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

Radiological surveillance in Mexico, derived of the accident of the Fukushima Daiichi nuclear power plant; Vigilancia radiologica en Mexico, derivado del accidente en la central nuclear de Fukushima Daiichi

Energy Technology Data Exchange (ETDEWEB)

Aguirre G, J.; Nohpal J, X., E-mail: jaguirre@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Departamento de Vigilancia Radiologica, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2012-10-15

March 11, 2011 an earthquake of 9.0 grades in the Richter scale, originated in the coast of Tohoku, Japan, in the Pacific Ocean gave origin to a tsunami that caused an accident in the Fukushima Daiichi nuclear power plant. Due to this accident, derived of the loss of the reactor cooling system, as well as of the prolonged absence of alternating and direct current, radiological protection actions were realized without being able to avoid the liberation of radioactive material to the atmosphere and ocean. The radiological impact of these liberations, not only in Japan but around the world, mainly in the north hemisphere of the Earth, was analyzed by means of environmental dose measurements and radionuclide concentrations in soil and water, among others. In the Mexico case, air samples data were obtained, as well as environmental dose celerity and full-length counts of the people coming from Japan near the disaster area. The present work contains the obtained results of the realized measurements in Mexico, same that have been used to make a summary and analysis of the dispersion in the environment in several countries of the world. (Author)

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)

Federal Radiological Monitoring and Assessment Center (FRMAC): Overview of FRMAC operations

International Nuclear Information System (INIS)

1993-09-01

The purpose of this Management Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) is to explain the federal preparation for a radiological accident and to describe the subsequent response activities which provide radiological monitoring and assessment outside the boundaries of the monitoring which support the radiological accident site. In the event of a radiological accident, federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the accident scene under the umbrella of the Federal Radiological Emergency Response Plan (FRERP). This cooperative effort will assure the state(s) and the Lead Federal Agency (LFA) that all federal technical assistance is fully supporting their efforts to protect the public and will provide these monitoring results in a working data center for immediate use by the state(s) and LFA decision makers. The federal agencies do not relinquish their statutory responsibilities. However, the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibility

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)

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

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

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)

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)

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)

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

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)

Massive radiological releases profoundly differ from controlled releases

International Nuclear Information System (INIS)

Pascucci-Cahen, Ludivine; Patrick, Momal

2013-01-01

In this article, the authors report identification and assessment of different types of costs associated with nuclear accidents. They first outline that these cost assessments must be as exhaustive or comprehensive as possible. While referring to past accidents, they define the different categories of costs: on-site costs (decontamination and dismantling, electricity not produced on the site), off-site costs (health costs, psychological costs, farming losses), image-related costs (impact on food and farm product exports, decrease of other exports), costs related to energy production, costs related to contaminated areas (refugees, lands). They give an assessment of a severe nuclear accident (i.e. an accident with important but controlled radiological releases) in France and outline that it would be a national catastrophe which could be however managed. They discuss the possible variations of the estimated costs. Then, they show that a major accident (i.e. an accident with massive radiological releases) in France would be an unmanageable European catastrophe because of the radiological consequences, of high economic costs, and of huge losses

Derived reference levels for prenatal exposure in a radiological emergency

International Nuclear Information System (INIS)

Nuccetelli, C.; Risica, S.; Rogani, A.

2002-01-01

After the Chernobyl accident many countries renewed their radiological emergency plans, also considering the possibility of over boundary accidents. This has been set out by the 96/29/Euratom Directive (Council Directive, 1996), which states that E ach Member State shall ensure that account is taken of the fact that radiological emergencies may occur in connection with practices on or outside its territory and affect it . Moreover, after September 11, 2001, the need to prepare emergency plans for possible terroristic attacks became evident and these plans are now being worked out in many countries for intervention in case of biological, chemical and/or radiological risk. In the event of radiological emergency, all decisions to be taken are based on possible doses to critical groups (European Commission, 1997), which are the population groups most at risk. These critical groups are, in most cases, infants or children, given that dose coefficients for these age groups are generally higher than for adults. However, a new ICRP Recommendation (ICRP, 2001) has recently been published that gives dose coefficients for embryo/foetus due to intake by the mother, by inhalation or ingestion, of 31 radionuclides. Also as a result of the revaluation in the last years of the possible health effects of prenatal exposure to ionising radiation (see e.g. the review in P. Fattibene et al., 1999), the consequences for the embryo/foetus of a possible radiological emergency connected to a nuclear plant and to possible dispersion of Depleted Uranium (DU) in the environment are analysed and discussed in this paper. For the former type of accident, Derived Intervention Levels (DILs) are calculated for prenatal exposure due to acute inhalation by the mother (female member of the public) and an assessment is performed of ingestion doses for the offspring resulting from consumption of foodstuffs by the mother of which 10% of the annual consumption is contaminated at the maximum levels

Simulation of LOF accidents with directly electrical heated UO2 pins

International Nuclear Information System (INIS)

Alexas, A.

1976-01-01

The behavior of directly electrical heated UO 2 pins has been investigated under loss of coolant conditions. Two types of hypothetical accidents have been simulated, first, a LOF accident without power excursion (LOF accident) and second, a LOF accident with subsequent power excursion (LOF-TOP accident). A high-speed film shows the sequence of events for two characteristic experiments. In consequence of the high-speed film analysis as well as the metallographical evaluation statements are given in respect to the cladding meltdown process, the fuel melt fraction and the energy input from the beginning of a power transient to the beginning of the molten fuel ejections

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.)

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).

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)

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)

Toward raising the higher level of radiological nursing

International Nuclear Information System (INIS)

Kusama, Tomoko; Ban, Nobuhiko; Ono, Koji

2013-01-01

The role and purpose of nursing in the radiological field are discussed with essentials of radiological nursing for raising its higher level and needed fundamental education. The discussion is from the thought that, at Fukushima Nuclear Power Plant Accident (Mar. 2011), general medical staff including nurses are rather insufficient of radiological knowledge like the exposure, radiation effect and risk. In the medical radiological field, nurses are expected to play roles of arranging the circumstance for patient's ease like explanation about health effect/risk, appropriate nursing of them after radiological diagnosis, radiation protection of nurses themselves, and of environment. At such an emergency as the Accident, care for the acutely exposed victims, their decontamination and responding to patient's concern are necessary. At the later phase, also needed are nursing of victims undergoing health management done by authorities and of radiological workers concerned as well as the third item above. Therefore, fundamentals of radiological knowledge such as physics, exposure, health effects, protection, contamination, legal rules and risk communication are required in the education of nurses. Otherwise, this education can be conducted as a part of safety security and physical assessment. The Accident also gives us the importance of radiological risk communication with its victims. (T.T.)

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.)

Technical support and preparations for the response to radiological emergencies

International Nuclear Information System (INIS)

Cardenas H, J.; Ramos V, E.O.; Fernandez G, I.M.; Capote F, E.; Zerquera J, T.; Garcia L, O.; Lopez B, G.; Molina P, D.; Lamdrid B, A.I.; Benitez N, J.C.; Salgado M, M.; Lopez F, Y.; Jerez V, P.

2006-01-01

The work picks up the efforts directed to elevate the technical capacity of the answer in front of the radiological emergencies. Expressing them by means of the actions carried out as for teaching, research and development and intervention before accidental radiological events. The same one reflects the leading role of the participant institutions in those marks of the answer system to radiological emergencies that for its technical level it satisfies the national and international demands in the matter. In execution of the mentioned goals research projects guided to endow to the national system of methodologies and procedures for the administration of radiological emergencies have been executed that favor the improvement of its technical and organizational capacities. As well as the postulates of the National Plan of Measures for Case of Catastrophes in the corresponding to radiological accidents. (Author)

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)

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

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)

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)

Generic procedures for assessment and response during a radiological emergency

International Nuclear Information System (INIS)

2000-08-01

One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately determine and take actions to protect members of the public and emergency workers. Radiological accident assessment must take account of all critical information available at any time and must be an iterative and dynamic process aimed at reviewing the response as more detailed and complete information becomes available. This manual provides the tools, generic procedures and data needed for an initial response to a non-reactor radiological accident. This manual is one out of a set of IAEA publications on emergency preparedness and response, including Method for the Development of Emergency Response Preparedness for Nuclear or Radiological Accidents (IAEA-TECDOC-953), Generic Assessment Procedures for Determining Protective Actions During a Reactor Accident (IAEA-TECDOC-955) and Intervention Criteria in a Nuclear or Radiation Emergency (Safety Series No. 109)

Planning for a radiological emergency in health care institutions

International Nuclear Information System (INIS)

Jerez Vegueria, S.F.; Jerez Vegueria, P.F.

1998-01-01

The possible occurrence of accidents involving sources of ionizing radiation calls for response plans to mitigate the consequences of radiological accidents. An emergency planning framework is suggested for institutions which use medical applications of ionizing radiation. Bearing in mind that the prevention of accidents is of prime importance in dealing with radioactive materials and other sources of ionizing radiation, it is recommended that emergency instructions and procedures address certain aspects of the causes of these radiological events. Issues such as identification of radiological events in medical practices and their consequences, protective measures, planning for an emergency response and maintenance of emergency capacity are considered. (author)

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

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

Device for direct digitized radiology of small objects

International Nuclear Information System (INIS)

Thomas, G.; Favier, C.; Brebant, C.; Mogavero, R.

1983-06-01

A radiological device has been developed to obtain direct digitized views with a large integration time. A micro computer system with programs specially developed for the automatic materials defects evaluation is used. Some results concerning the weldings of electro-nuclear fuel pins are presented here [fr

Radiologic protection: technical and legal aspects

International Nuclear Information System (INIS)

Pinto, A.V.A.

1987-01-01

Radiologic units are described with the aim to decodify the technical dosimetric language. The legal aspect of radiologic protection in Brazil is reported. Information about help in case of radiation accident is presented. (M.A.C.) [pt

Questionnaire survey report about the criticality accident at a nuclear fuel processing facility

International Nuclear Information System (INIS)

2000-01-01

The Radiation Protection Section of the Japanese Society of Radiological Technology conducted a questionnaire survey on the criticality accident at the nuclear fuel processing facility in Tokai village on September 30, 1999 in order to identify factors related to the accident and consider countermeasures to deal with such accidents. The questionnaire was distributed to 347 members (122 facilities) of the Japanese Society of Radiological Technology who were working or living in Ibaraki Prefecture, and replies were obtained from 104 members (75 facilities). Questions to elicit the opinions of individuals were as following: method of obtaining information about the accident, knowledge about radiation, opinions about the accident, and requests directed to the Society. Questions regarding facilities concerned the following: communication after the accident, requests for dispatch to the accident site, and possession of radiometry devices. In regard to acquisition of information, 91 of the 104 members (87.5%) answered 'television or radios' followed by newspapers. Forty-five of 101 members were questioned about radiation exposure and radiation effects by the public. There were many opinions that accurate news should be provided rapidly, by the mass media. Many members (75%) felt that they lacked knowledge about radiation, reconfirming the importance of education and instruction concerning radiation. Dispatch was requested of 36 of the 75 facilities (48%), and 44 of 83 facilities (53%) owned radiometry instruments. (K.H.)

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.)

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

Overview of core disruptive accidents

International Nuclear Information System (INIS)

Marchaterre, J.F.

1977-01-01

An overview of the analysis of core-disruptive accidents is given. These analyses are for the purpose of understanding and predicting fast reactor behavior in severe low probability accident conditions, to establish the consequences of such conditions and to provide a basis for evaluating consequence limiting design features. The methods are used to analyze core-disruptive accidents from initiating event to complete core disruption, the effects of the accident on reactor structures and the resulting radiological consequences are described

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

REAC/TS radiation accident registry. Update of accidents in the United States

International Nuclear Information System (INIS)

Ricks, R.C.; Berger, M.E.; Holloway, E.C.; Goans, R.E.

2000-01-01

Serious injury due to ionizing radiation is a rare occurrence. From 1944 to the present, 243 US accidents meeting dose criteria for classification as serious are documented in the REAC/TS Registry. Thirty individuals have lost their lives in radiation accidents in the United States. The Registry is part of the overall REAC/TS program providing 24-hour direct or consultative assistance regarding medical and heath physics problems associated with radiation accidents in local, national, and international incidents. The REAC/TS Registry serves as a repository of medically important information documenting the consequences of these accidents. Registry data are gathered from various sources. These include reports from the World Heath Organization (WHO), International Atomic Energy Agency (IAEA), US Nuclear Regulatory Commission (US NRC), state radiological health departments, medical/health physics literature, personal communication, the Internet, and most frequently, from calls for medical assistance to REAC/TS, as part of our 24-hour medical assistance program. The REAC/TS Registry for documentation of radiation accidents serves several useful purposes: 1) weaknesses in design, safety practices, training or control can be identified, and trends noted; 2) information regarding the medical consequences of injuries and the efficacy of treatment protocols is available to the treating physician; and 3) Registry case studies serve as valuable teaching tools. This presentation will review and summarize data on the US radiation accidents including their classification by device, accident circumstances, and frequency by respective states. Data regarding accidents with fatal outcomes will be reviewed. The inclusion of Registry data in the IAEA's International Reporting System of Radiation Events (RADEV) will also be discussed. (author)

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.)

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

Proposed Nuclear Power Plants in the UK-Potential Radiological Implications for Ireland

International Nuclear Information System (INIS)

McMahon, C.; Kelleher, K.; McGinnity, P.; Organo, C.; Smith, K.; Currivan, L.; Ryan, T.

2013-05-01

The UK Government has identified up to eight locations for the construction of new nuclear power plants by 2025. Five of these locations are on the Irish Sea coast. The Radiological Protection Institute of Ireland, RPII was requested by the Minister for the Environment, Community and Local Government to undertake an assessment of the potential radiological impacts on Ireland from this New Build Programme. This report presents the findings of the potential impacts on Ireland of both the anticipated routine radioactive discharges and of a range of postulated nuclear accident scenarios. The following points are the principal findings of the report. Given the prevailing wind direction in Ireland, radioactive contamination in the air, either from routine operation of the proposed nuclear power plants or accidental releases, will most often be transported away from Ireland. The routine operation of the proposed nuclear power plants will have no measurable radiological impact on Ireland or the Irish marine environment. The severe accident scenarios assessed ranged in their estimated frequency of occurrance from 1 in 50,000 to 1 in 33 million per year. The assessment used a weather pattern that maximised the transfer of radioactivity to Ireland. For the severe accident scenarios assessed, food controls or agriculture protective measures would generally be required in Ireland to reduce exposure of the population so as to mitigate potential long-term health effects. In the accident scenario with an estimated 1 in 33 million chance of occurring, short-term measures such as staying indoors would also be advised as a precautionary measure. In general, the accidents with higher potential impact on Ireland are the ones least likely to occur. Regardless of the radiological impact, any accident at the proposed nuclear power plants leading to an increase of radioactivity levels in Ireland would have a socio-economic impact on Ireland. A major accidental release of radioactivity to

Proposed Nuclear Power Plants in the UK-Potential Radiological Implications for Ireland

Energy Technology Data Exchange (ETDEWEB)

McMahon, C.; Kelleher, K.; McGinnity, P.; Organo, C.; Smith, K.; Currivan, L.; Ryan, T.

2013-05-15

The UK Government has identified up to eight locations for the construction of new nuclear power plants by 2025. Five of these locations are on the Irish Sea coast. The Radiological Protection Institute of Ireland, RPII was requested by the Minister for the Environment, Community and Local Government to undertake an assessment of the potential radiological impacts on Ireland from this New Build Programme. This report presents the findings of the potential impacts on Ireland of both the anticipated routine radioactive discharges and of a range of postulated nuclear accident scenarios. The following points are the principal findings of the report. Given the prevailing wind direction in Ireland, radioactive contamination in the air, either from routine operation of the proposed nuclear power plants or accidental releases, will most often be transported away from Ireland. The routine operation of the proposed nuclear power plants will have no measurable radiological impact on Ireland or the Irish marine environment. The severe accident scenarios assessed ranged in their estimated frequency of occurrance from 1 in 50,000 to 1 in 33 million per year. The assessment used a weather pattern that maximised the transfer of radioactivity to Ireland. For the severe accident scenarios assessed, food controls or agriculture protective measures would generally be required in Ireland to reduce exposure of the population so as to mitigate potential long-term health effects. In the accident scenario with an estimated 1 in 33 million chance of occurring, short-term measures such as staying indoors would also be advised as a precautionary measure. In general, the accidents with higher potential impact on Ireland are the ones least likely to occur. Regardless of the radiological impact, any accident at the proposed nuclear power plants leading to an increase of radioactivity levels in Ireland would have a socio-economic impact on Ireland. A major accidental release of radioactivity to

Policy elements for post-accident management in the event of nuclear accident. Document drawn up by the Steering Committee for the Management of the Post-Accident Phase of a Nuclear Accident (CODIRPA). Final version - 5 October 2012

International Nuclear Information System (INIS)

2012-01-01

Pursuant to the Inter-ministerial Directive on the Action of the Public Authorities, dated 7 April 2005, in the face of an event triggering a radiological emergency, the National directorate on nuclear safety and radiation protection (DGSNR), which became the Nuclear safety authority (ASN) in 2006, was tasked with working the relevant Ministerial offices in order to set out the framework and outline, prepare and implement the provisions needed to address post-accident situations arising from a nuclear accident. In June 2005, the ASN set up a Steering committee for the management of the post-accident phase in the event of nuclear accident or a radiological emergency situation (CODIRPA), put in charge of drafting the related policy elements. To carry out its work, CODIRPA set up a number of thematic working groups from 2005 on, involving in total several hundred experts from different backgrounds (local information commissions, associations, elected officials, health agencies, expertise agencies, authorities, etc.). The working groups reports have been published by the ASN. Experiments on the policy elements under construction were carried out at the local level in 2010 across three nuclear sites and several of the neighbouring municipalities, as well as during national crisis drills conducted since 2008. These works gave rise to two international conferences organised by ASN in 2007 and 2011. The policy elements prepared by CODIRPA were drafted in regard to nuclear accidents of medium scale causing short-term radioactive release (less than 24 hours) that might occur at French nuclear facilities equipped with a special intervention plan (PPI). They also apply to actions to be carried out in the event of accidents during the transport of radioactive materials. Following definitions of each stage of a nuclear accident, this document lists the principles selected by CODIRPA to support management efforts subsequent to a nuclear accident. Then, it presents the main

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)

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)

Means to be settled on in case of a nuclear accident

International Nuclear Information System (INIS)

Nenot, J.C.

1988-01-01

The emergency plan must be based on a study of radiological consequences of radioactive releases in case of a reference accident. This plan must be flexible and adaptable to the real situations that often difer from the reference accident. The optimal method of the intervention in case of accidents depends on the comparison between the loss caused by the intervention and the advantage offered by the dose reduction. The emergency plans include three levels: The first one concerns the classical accidents, the second concerns the radiological accidents limited inside the nuclear installations site and the third concerns the events that can create a radiological risk outside the site. These emergency plans have been discussed in this paper. The protection population measures are various and numerous. The selection of the most appropriate measures depends on several parameters (demographic, ecological, geographical, socio-economical, meteorological...). So, it is necessary to consider all types of accident and to settle protection measures adaptable to each accidental situation. The essential protection measures have been defined and discussed. A radiological surveillance plan has also to be established. The international and inter-regional cooperation plays a large part in the reduction of the accident consequences. So, it is to be hoped that countries,in a same region, would establish mutual assistance conventions. 3 tabs., 11 refs.(author)

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

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

Radiation accidents

International Nuclear Information System (INIS)

Nenot, J.C.

1996-01-01

Analysis of radiation accidents over a 50 year period shows that simple cases, where the initiating events were immediately recognised, the source identified and under control, the medical input confined to current handling, were exceptional. In many cases, the accidents were only diagnosed when some injuries presented by the victims suggested the radiological nature of the cause. After large-scale accidents, the situation becomes more complicated, either because of management or medical problems, or both. The review of selected accidents which resulted in severe consequences shows that most of them could have been avoided; lack of regulations, contempt for rules, human failure and insufficient training have been identified as frequent initiating parameters. In addition, the situation was worsened because of unpreparedness, insufficient planning, unadapted resources, and underestimation of psychosociological aspects. (author)

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

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

Handling of overexposed persons in radiological emergencies

International Nuclear Information System (INIS)

Estrada, E.

2000-01-01

The purpose of this standard procedure of the criteria in case of radiological emergencies is to describe the standard procedures used to define an radiological accident in terms of the doses received, and to describe the medical procedures for diagnoses and treatment of health hazards caused by external and internal irradiation in radiological emergencies

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

Management of a radiological emergency. Experience feedback and post-accident management; Gestion d'une urgence radiologique. Retour d'experience et gestion post-accidentelle

Energy Technology Data Exchange (ETDEWEB)

Dubiau, Ph. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France)

2007-07-15

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.)

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)

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)

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%)

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%)

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

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.

Role of the RDO in a transportation accident

International Nuclear Information System (INIS)

Goldberg, I.

1974-01-01

The role of the RDO in a radioactive materials transport accident in California is discussed. The California Radiological Emergency Assistance Plan (CREAP) and the Emergency Procedures for Transportation Accidents (EPTA) are mentioned

Health of the population having suffered after the Chernobyl NPP accident

International Nuclear Information System (INIS)

Stozharov, A.N.; Zubovich, V.K.; Lazyuk, G.I.; Stel'makh, V.A.

1997-01-01

Are given the results of researches carried out in Belarus in 1996 on the following directions: study of influence of radiological consequences of the Chernobyl accident on health of the people; development of methods and means of diagnostics, treatment and preventive maintenance of diseases at various categories of victims; development and introduction in practice of effective methods of preventive maintenance and treatment of diseases of both mother and child in conditions of influence of the Chernobyl accident consequences; study of genetic consequences caused by the Chernobyl NPP accident and development of effectual measures of their prevention; creation of effective preventive means and food additives for treatment and rehabilitation of the persons having suffered after the Chernobyl accident; optimization of system of measures for health saving of the having suffered population and development of ways of increase of its efficiency

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

. The consequences of a given accidental release will depend on the values of a number of parameters, in particular, type and nature of the accident, the total amount of radioactive material and different radionuclides involved, the energy with which they are disposed in the environment, the nature of the surrounding environment and the mechanisms of radioactive dispersion and transfer. This paper presents some assessments on the LOCA type accident influence, without the intact loop cooling and ECCS in case of a hypothetical site. The developed assessments resulted in the necessity to evacuate the population up to a distance of about 10 km away from the sectors located in the wind blowing direction. Note that for a real situation of a site, smaller values of the doses are expected, considering other phenomena which may lead to the decrease of the dose values for individuals (the consideration of the meteorologic parameter hourly values, of precipitation, of the actual distribution of population, of the protection measure application, etc)

Basic principles for intervention after a nuclear or radiological emergency

International Nuclear Information System (INIS)

Per Hedemann Jensen

1996-01-01

The current status of internationally agreed principles for intervention after a nuclear accident or radiological emergency and the international development of intervention guidance since the Chernobyl accident are reviewed. The experience gained after the Chernobyl accident indicates that the international advice on intervention existing at the time of the Chernobyl accident was not fully understood by decision makers neither in Western Europe nor in the former USSR and that the guidance failed to address adequately the difficult social problems which can arise after a serious nuclear accident. The radiation protection philosophy of today distinguishes between practices and interventions. The radiological protection system of intervention includes justification of the protective action and optimization of the level of protection achieved by that action. Dose limits do not apply in intervention situations. The inputs to justification and optimization studies include factors that are related to radiological protection, whereas the final decisions on introduction of countermeasures would also depend on other factors. The basic principles for intervention as recommended by international organisations are discussed in detail and the application of the principles on a generic basis is illustrated for long-term protective actions. The concepts of intervention level, operational intervention level and action level are presented and the relation between these quantities is illustrated. The numerical guidance on intervention in a nuclear accident or radiological emergency or a chronic exposure situation given by ICRP, IAEA and in the Basic Safety Standards is presented. (author)

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)

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)

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

Chernobyl accident and Denmark

International Nuclear Information System (INIS)

1986-12-01

The report describes the Chernobyl accident and its consequences for Denmark in particular. It was commissioned by The Secretary of State for the Environment. The event at the accident site, the release and dispersal of radioactive substances into the atmosphere and over Europe, is described. A discussion of the Danish organisation for nuclear emergencies, how it was activated and adapted to the actual situation, is given. A comprehensive description of the radiological contamination in Denmark following the accident and the estimated health effects, is presented. The situation in other European countries is mentioned. (author)

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

The radiological assessment system for consequence analysis - RASCAL

International Nuclear Information System (INIS)

Sjoreen, A.L.; Ramsdell, J.V.; Athey, G.F.

1996-01-01

The Radiological Assessment System for Consequence Analysis, Version 2.1 (RASCAL 2.1) has been developed for use during a response to radiological emergencies. The model estimates doses for comparison with U.S. Environmental Protection Agency (EPA) Protective Action Guides (PAGs) and thresholds for acute health effects. RASCAL was designed to be used by U.S. Nuclear Regulatory Commission (NRC) personnel who report to the site of a nuclear accident to conduct an independent evaluation of dose and consequence projections and personnel who conduct training and drills on emergency responses. It allows consideration of the dominant aspects of the source term, transport, dose, and consequences. RASCAL consists of three computational tools: ST-DOSE, FM-DOSE, and DECAY. ST-DOSE computes source term, atmospheric transport, and dose to man from accidental airborne releases of radionuclides. The source-term calculations are appropriate for accidents at U.S. power reactors. FM-DOSE computes doses from environmental concentrations of radionuclides in the air and on the ground. DECAY computes radiological decay and daughter in-growth. RASCAL 2.1 is a DOS application that can be run under Windows 3.1 and 95. RASCAL has been the starting point for other accident consequence models, notably INTERRAS, an international version of RASCAL, and HASCAL, an expansion of RASCAL that will model radiological, biological, and chemical accidents

Chernobyl reactor accident

International Nuclear Information System (INIS)

1986-05-01

Following the accident at Chernobyl nuclear reactor, WHO organized on 6 May 1986 in Copenhagen a one day consultation of experts with knowledge in the fields of meteorology, radiation protection, biological effects, reactor technology, emergency procedures, public health and psychology in order to analyse the development of events and their consequences and to provide guidance as to the needs for immediate public health action. The present report provides detailed information on the transportation and dispersion of the radioactive material in the atmosphere, especially volatile elements, during the release period 26 April - 5 May. Presented are the calculated directions and locations of the radioactive plume over Europe in the first 5 days after the accident, submitted by the Swedish Meteorological and Hydrological Institute. The calculations have been made for two heights, 1500m and 750m and the plume directions are grouped into five periods, covering five European areas. The consequences of the accident inside the USSR and the radiological consequences outside the USSR are presented including the exposure routes and the biological effects, paying particular attention to iodine-131 effects. Summarized are the first reported measured exposure rates above background, iodine-131 deposition and concentrations in milk and the remedial actions taken in various European countries. Concerning the cesium-137 problem, based on the UNSCEAR assessment of the consequences of the nuclear fallout, one concludes that the cesium contamination outside the USSR is not likely to cause any serious problems. Finally, the conclusions and the recommendations of the meeting, taking into account both the short-term and longer term considerations are presented

The 10 recommendations for prevention of radiation accidents in industrial gamma radiography

International Nuclear Information System (INIS)

Souza, Luana Silva de

2015-01-01

The Industrial Gamma Radiography, as part of Industrial Radiography, stands out as the most widespread and plays an important role in the quality control of different materials and devices. However, IAEA classifies industrial gamma radiography in the Category 2 as very dangerous due to the radiological risk caused by the use of high activity radioactive sources. In March, 2012, a Brazilian Workshop on Prevention of Industrial Gamma Radiography Accident was performed by DIAPI/CNEN with the objective of disseminating knowledge about radiological accidents with radioactive sources in this application. During this Workshop, IRD/CNEN conducted a survey with 75 participants using a form with 22 recommendations to prevent radiological accidents, aiming to select the most voted. This present work aims to perform a detailed statistical study to define the Top 10 Recommendations for industrial gamma radiography operator avoids radiological accidents and to prepare a brochure with these top 10 recommendations to be distributed to all industrial gamma radiography radiation workers. Data analysis was performed using the statistical method 'Frequency Distribution', among the 75 participants categorized as General, RPO, and Other Workers of the area. The results were obtained for each category, accounting for the total of 22 recommendations in its percentage and number of votes, and the top 10 recommendations were defined to prevent radiological accidents. The first place and most important recommendation is 'Always use a personal alarm monitor throughout the work'. One of the conclusions is that the brochure with the Top 10 Recommendations shows to be understandable and useful for dissemination and training of radiation workers to avoid radiological accidents in industrial gamma radiography. (author)

Interventional radiology and undesirable effects

International Nuclear Information System (INIS)

Benderitter, M.

2009-01-01

As some procedures of interventional radiology are complex and long, doses received by patients can be high and cause undesired effects, notably on the skin or in underlying tissues (particularly in the brain as far as interventional neuroradiology is concerned and in lungs in the case of interventional cardiology). The author briefly discusses some deterministic effects in interventional radiology (influence of dose level, delay of appearance of effects, number of accidents). He briefly comments the diagnosis and treatment of severe radiological burns

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)

Radiological optimization

International Nuclear Information System (INIS)

Zeevaert, T.

1998-01-01

Radiological optimization is one of the basic principles in each radiation-protection system and it is a basic requirement in the safety standards for radiation protection in the European Communities. The objectives of the research, performed in this field at the Belgian Nuclear Research Centre SCK-CEN, are: (1) to implement the ALARA principles in activities with radiological consequences; (2) to develop methodologies for optimization techniques in decision-aiding; (3) to optimize radiological assessment models by validation and intercomparison; (4) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (5) to develop methods and programmes to assist decision-makers during a nuclear emergency; (6) to support the policy of radioactive waste management authorities in the field of radiation protection; (7) to investigate existing software programmes in the domain of multi criteria analysis. The main achievements for 1997 are given

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

The implementation of the IAEA accident response plan in Yugoslav practice

International Nuclear Information System (INIS)

Orlic, M.; Pavlovic, R.; Markovic, S.; Pavlovic, S.

1996-01-01

One of the important lessons from the Chernobyl accident is the necessity of existence of operational national emergency response plan. Summarizing consequences and experiences after Chernobyl accident, expert groups from IAEA, ICRP and other international scientific organizations, have been extensively worked on reviewing old ones, and preparing new radiation protection and nuclear safety principals and codes. One of the important issue is national emergency response plan for radiological accident. The nuclear accident response plan in Yugoslavia is presented in this paper. It is essentially based on IAEA model national response plan for radiological accident. This model has to be adjusted to the specificity of member states. The optimum society organization for emergency management in the case of accidents in ionizing radiation sources practices is suggested in this paper. Specific characteriztics of Yugoslav state organization relating to accident response are emphasised. (author)

Cosyma a new programme package for accident consequence assessment

International Nuclear Information System (INIS)

Kelly, G.N.

1991-01-01

This report gives details of a new programme package for accident consequence assessment, prepared under the CEC's Maria programme (Methods for assessing the radiological impact of accidents) initiated in 1982 to review and build on the nuclear accident consequence assessment methods in use within the European Community

Continuing training in radiological protection as an effective means of avoiding radiological accidents; A formação continuada em proteção radiológica como um meio eficaz de evitar acidentes radiológicos

Energy Technology Data Exchange (ETDEWEB)

Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro, RJ (Brazil); Pelegrineli, S.Q.; Martins, G. [Faculdade Casa Branca (FACAB), SP (Brazil); Lima, A.R. [Comissão Nacional de Energia Nuclear (CNEN), 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

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.

The significance of radiological control documentation in litigation

International Nuclear Information System (INIS)

Lodde, G.M.; Murphy, T.D.

1988-01-01

Commercial nuclear facilities accumulate radiological control program data and documents generated and retained pursuant to regulatory, license, and technical specification requirements. During and following the Three Mile Island Unit 2 (TMI-2) accident, many documents were produced that would not normally have been produced. Shortly after the accident, the US Nuclear Regulatory Commission (NRC) issued an order requiring the retention of all data, including documentary material and physical samples relating to the TMI-2 accident (44 Fed. Reg. 30788, May 29, 1979). Three years later, the NRC vacated the requirement to retain catalogued physical samples, provided the radioactivity data had been properly recorded, allowing disposal of many samples. After the TMI-2 accident, GPU Nuclear Corporation (GPU) designed and implemented an effective and efficient record management program for TMI. This Computer-Assisted Records and Information Retrieval System (CARIRS) was developed to assess the official record for TMI, which is maintained as a microform. GPU also retains hard copies of selected radiological control documents for potential litigation. This paper describes the use of radiological control documentation in the postaccident litigation and the magnitude of document production required to support that litigation

Massive radiological releases profoundly differ from controlled releases

International Nuclear Information System (INIS)

Pascucci-Cahen, Ludivine; Patrick, Momal

2012-11-01

Preparing for a nuclear accident implies understanding potential consequences. While many specialized experts have been working on different particular aspects, surprisingly little effort has been dedicated to establishing the big picture and providing a global and balanced image of all major consequences. IRSN has been working on the cost of nuclear accidents, an exercise which must strive to be as comprehensive as possible since any omission obviously underestimates the cost. It therefore provides (ideally) an estimate of all cost components, thus revealing the structure of accident costs, and hence sketching a global picture. On a French PWR, it appears that controlled releases would cause an 'economical' accident with limited radiological consequences when compared to other costs; in contrast, massive releases would trigger a major crisis with strong radiological consequences. The two types of crises would confront managers with different types of challenges. (authors)

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

Medical student knowledge regarding radiology before and after a radiological anatomy module: implications for vertical integration and self-directed learning.

Science.gov (United States)

Murphy, Kevin P; Crush, Lee; O'Malley, Eoin; Daly, Fergus E; O'Tuathaigh, Colm M P; O'Connor, Owen J; Cryan, John F; Maher, Michael M

2014-10-01

To examine the impact that anatomy-focused radiology teaching has on non-examined knowledge regarding radiation safety and radiology as a specialty. First-year undergraduate medical students completed surveys prior to and after undertaking the first-year anatomy programme that incorporates radiological anatomy. Students were asked opinions on preferred learning methodology and tested on understanding of radiology as a specialty and radiation safety. Pre-module and post-module response rates were 93 % (157/168) and 85 % (136/160), respectively. Pre-module and post-module, self-directed learning (SDL) ranked eighth (of 11) for preferred gross-anatomy teaching formats. Correct responses regarding radiologist/radiographer roles varied from 28-94 % on 16 questions with 4/16 significantly improving post-module. Identification of modalities that utilise radiation significantly improved for five of eight modalities post-module but knowledge regarding relative amount of modality-specific radiation use was variable pre-module and post-module. SDL is not favoured as an anatomy teaching method. Exposure of students to a radiological anatomy module delivered by senior clinical radiologists improved basic knowledge regarding ionising radiation use, but there was no improvement in knowledge regarding radiation exposure relative per modality. A possible explanation is that students recall knowledge imparted in didactic lectures but do little reading around the subject when the content is not examined. • Self-directed learning is not favoured as a gross anatomy teaching format amongst medical students. • An imaging anatomy-focused module improved basic knowledge regarding ionising radiation use. • Detailed knowledge of modality-specific radiation exposure remained suboptimal post-module. • Knowledge of roles within a clinical radiology department showed little change post-module.

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)

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

Radiation protection of workers in radiological emergency situation. Proceedings of the technical day

International Nuclear Information System (INIS)

Rannou, Alain; Gosset, Eric; Lahaye, Thierry; Foucher, Laurent; Couasnon, Olivier; Bouchery, Pascal; Gaillard-Lecanu, Emmanuelle; Pectorin, Xavier; Fusil, Laurence; Boudergui, Karim; Adhemar, Bruno; Devin, Patrick; Mace, Jean-Reynald; Chevallier, Michel; Leautaud, Jean-Marc; LANCE, Benoit

2015-03-01

Following the Fukushima-Daichi accident, several actions have been taken in France from the lessons learnt from the accident: the elaboration of a national plan for the management of a major nuclear or radiological accident, and the safety complementary evaluations to be carried out by nuclear operators. As a complement to the measures to be implemented for the protection of the overall population in emergency radiological situation, the protection of workers mobilized for the management of the crisis has also to be taken into account in the framework of these measures. The French Society of Radiation Protection (SFRP) has organized a technical day to take stock of this question. The program comprises 4 topical sessions dealing with: the main actions taken at the national scale after the Fukushima-Daichi accident, the strategies and intervention means of nuclear operators in case of radiological emergency, the radiation protection R and D for the protection of intervenors in case of radiological emergency, and the main actions implemented at the international scale and their perspectives. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - Health status and lessons learnt from the Fukushima accident - workers (Alain RANNOU, IRSN); 2 - National response plan to a major nuclear or radiologic accident (Eric GOSSET, SGDSN); 3 - Legal framework applicable to intervenors (Thierry LAHAYE, DGT); 4 - Prescriptions linked with complementary safety and liability studies (Laurent FOUCHER, ASN); 5 - EDF: radiological risk management in emergency situation (Pascal BOUCHERY, EDF); 6 - CEA: intervention strategy, means and radiation protection (Xavier PECTORIN, Laurence FUSIL - CEA); 7 - AREVA: FINA's Intervention and workers' radiation protection (Bruno ADHEMAR, Patrick DEVIN - AREVA); 8 - Intervention in radiological emergency situation: the INTRA (Robots intervention on accidents) economic

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

Alternative evacuation strategies for nuclear power accidents

International Nuclear Information System (INIS)

Hammond, Gregory D.; Bier, Vicki M.

2015-01-01

In the U.S., current protective-action strategies to safeguard the public following a nuclear power accident have remained largely unchanged since their implementation in the early 1980s. In the past thirty years, new technologies have been introduced, allowing faster computations, better modeling of predicted radiological consequences, and improved accident mapping using geographic information systems (GIS). Utilizing these new technologies, we evaluate the efficacy of alternative strategies, called adaptive protective action zones (APAZs), that use site-specific and event-specific data to dynamically determine evacuation boundaries with simple heuristics in order to better inform protective action decisions (rather than relying on pre-event regulatory bright lines). Several candidate APAZs were developed and then compared to the Nuclear Regulatory Commission’s keyhole evacuation strategy (and full evacuation of the emergency planning zone). Two of the APAZs were better on average than existing NRC strategies at reducing either the radiological exposure, the population evacuated, or both. These APAZs are especially effective for larger radioactive plumes and at high population sites; one of them is better at reducing radiation exposure, while the other is better at reducing the size of the population evacuated. - Highlights: • Developed framework to compare nuclear power accident evacuation strategies. • Evacuation strategies were compared on basis of radiological and evacuation risk. • Current strategies are adequate for smaller scale nuclear power accidents. • New strategies reduced radiation exposure and evacuation size for larger accidents

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2

International Nuclear Information System (INIS)

1996-08-01

Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

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)

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)

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

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.

Nuclear fuel cycle facility accident analysis handbook

International Nuclear Information System (INIS)

Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

1988-05-01

The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

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)

Chernobyl accident: the crisis of the international radiation community

International Nuclear Information System (INIS)

Malko, M.V.

1998-01-01

The information given in the present report about the Chernobyl accident and its radiological consequences indicates a serious crisis of the international radiation community. The following signs of this crises can be discerned: The international radiation community did not recognize the real reasons of the accident for a long time. It could not make a correct assessment of the damage to the thyroid of the affected populations of Belarus, Russia and the Ukraine. Up to present time it rejects the reliable data on hereditary malformations. It is not able to accept reliable data on the increase in the incidence in all categories of people affected by the Chernobyl accident. The international radiation community supported the Soviet authorities in their attempts to play down the radiological consequences of the Chernobyl accident for a long time. (author)

Chernobyl accident. The crisis of the international radiation community

International Nuclear Information System (INIS)

Malko, Mikhail V.

2016-01-01

The information given in the present report about the Chernobyl accident and its radiological consequences indicates a serious crisis of the international radiation community. The following signs of this crises can be discerned: The international radiation community did not recognize the real reasons of the accident for a long time. It could not make a correct assessment of the damage to the thyroid of the affected populations of Belarus, Russia and the Ukraine. Up to present time it rejects the reliable data on hereditary malformations. It is not able to accept reliable data on the increase in the incidence in all categories of people affected by the Chernobyl accident. The international radiation community supported the Soviet authorities in their attempts to play down the radiological consequences of the Chernobyl accident for a long time. (author)

French regulatory requirements for the occupational radiation protection in severe accident situations and post-accident recovery

International Nuclear Information System (INIS)

Couasnon, Olivier

2014-01-01

Workers of the concerned company and other persons and teams called 'intervention personnel' (specialized firemen, first aider, etc.) are to be involved in radiological emergency situations. Radiation protection provisions for workers and for intervention personnel complement one another because they cover persons with different statutes (workers under the responsibility of an employer and persons acting within the framework of agreements with the public authorities or within the framework of the requisitions). Work or operations exposing workers to ionizing radiation in radiological emergency situations can be assigned only to workers satisfying all of the following conditions: classification in category A worker; free of any medical unfitness; on a list drawn up in advance for this purpose; having received appropriate information on the risks and the precautions to take during the work or the operation; not having received, during the preceding twelve months, a dose greater than one of the annual limit values for exposures subject to special authorization. In addition, the worker must be a volunteer to carry out the work or the operations concerned in radiological emergency situations and have individual dosimetry means appropriate for the situation. Intervention personnel are possibly composed of personnel from responding organizations, such as police officers, fire-fighters, medical personnel, drivers and crews of evacuation vehicles, or of workers employed by the head of the damaged plant. In order to determine their selection, training and medical and radiological monitoring conditions, intervention personnel are classified into two groups: personnel forming the special technical, medical and health intervention teams readied in advance to deal with radiological emergency situations and persons not belonging to special teams but intervening as part of the tasks within the scope of their competence. In case of an existing exposure situation (post-accident

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.

The handling of radiation accidents

International Nuclear Information System (INIS)

1977-01-01

The symposium was attended by 204 participants from 39 countries and 5 international organizations. Forty-two papers were presented in 8 sessions. The purpose of the meeting was to foster an exchange of experiences gained in establishing and exercising plans for mitigating the effects of radiation accidents and in the handling of actual accident situations. Only a small number of accidents were reported at the symposium, and this reflects the very high standards of safety that has been achieved by the nuclear industry. No accidents of radiological significance were reported to have occurred at commercial nuclear power plants. Of the accidents reported, industrial radiography continues to be the area in which most of the radiation accidents occur. The experience gained in the reported accident situations served to confirm the crucial importance of the prompt availability of medical and radiological services, particularly in the case of uptake of radioactive material, and emphasized the importance of detailed investigation into the causes of the accident in order to improve preventative measures. One of the principal themes of the symposium involved emergency procedures related to nuclear power plant accidents, and several papers defining the scope, progression and consequences of design base accidents for both thermal and fast reactor systems were presented. These were complemented by papers defining the resultant protection requirements that should be satisfied in the establishment of plans designed to mitigate the effects of the postulated accident situations. Several papers were presented describing existing emergency organizational arrangements relating both to specific nuclear power plants and to comprehensive national schemes, and a particularly informative session was devoted to the topic of training of personnel in the practical conduct of emergency arrangements. The general feeling of the participants was one of studied confidence in the competence and

Planning for spontaneous evacuation during a radiological emergency

International Nuclear Information System (INIS)

Johnson, J.H. Jr.

1984-01-01

The Federal Emergency Management Agency's (FEMA's) radiological emergency preparedness program ignores the potential problem of spontaneous evacuation during a nuclear reactor accident. To show the importance of incorporating the emergency spatial behaviors of the population at risk in radiological emergency preparedness and response plans, this article presents empirical evidence that demonstrates the potential magnitude and geographic extent of spontaneous evacuation in the event of an accident at the Long Island Lighting Company's Shoreham Nuclear Power Station. The results indicate that, on the average, 39% of the population of Long Island is likely to evacuate spontaneously and thus to cast an evacuation shadow extending at least 25 miles beyond the plant. On the basis of these findings, necessary revisions to FEMA's radiological emergency preparedness program are outlined

Recognition difference and improvement direction of the radiological technologists and patient against medical service in department radiology - Inchon area in the object

International Nuclear Information System (INIS)

An, Sung Min; Kim, Sung Chul

2006-01-01

Satisfaction of the patient against the medical service in department of radiology and it evaluated the different recognition of radiological technologist and patient, and investigates it's improvement direction. It sent the reply the above the which is a usual result in question result of the most that, the receipt process it was complicated in the portion which is insufficient. 'The receipt process is complication', 'waiting time is long' and ' don't radiation protection for patient and guardian'. Also these a facts was recognizing patients and radiological technologist all. And the effort of the radiological technologist is necessary with the method which reduces a recognition difference. The periodical medical service satisfaction investigates and must endeavor in reform measure preparation

A comparison of the consequences of the design basis accident of the Greek Research Reactor with those of a serious realistic accident

International Nuclear Information System (INIS)

Kollas, J.G.; Anoussis, J.N.

1985-12-01

An analysis of the radiological consequences of the design basis and the coolant flow blockage accidents of the Greek Research Reactor is presented. The results indicate that the consequences of the coolant flow blockage accident are practically trivial being 1-2 orders of magnitude lower than the corresponding consequences of the design basis accident. (author)

Study on the offsite emergency planning against an accident in NPP

International Nuclear Information System (INIS)

Khang, Byung Oui; Lee, Goan Yup; Wu, Jong Sup; Kim, Joo Hag; Lee, Jong Tai; Lee, Jae Eun; Ahn, Chul Hyun; Ahn, Jae Hyun; Park, Dae Woo

2009-12-01

- Proposing effective local nuclear emergency preparedness system against nuclear/radiological accidents. - Proposing improved preparation/operation scheme on emergency response facilities, installations and equipment. - Establishing protection scheme on the general public against nuclear/radiological accidents. - Proposing effective preparation/operation scheme on local radioactive monitoring system. - Establishing effective training/drill scheme on the nuclear emergency preparedness. - Proposing effective technical administrative system of the local government (Busan metropolitan city)

Chemical and radiological vulnerability assessment in urban areas

Directory of Open Access Journals (Sweden)

Stojanović Božidar

2006-01-01

Full Text Available Cities and towns are faced with various types of threat from the extraordinary events involving chemical and radiological materials as exemplified by major chemical accidents, radiological incidents, fires, explosions, traffic accidents, terrorist attacks, etc. On the other hand, many sensitive or vulnerable assets exist within cities, such as: settlements, infrastructures, hospitals, schools, churches, businesses, government, and others. Besides emergency planning, the land use planning also represents an important tool for prevention or reduction of damages on people and other assets due to unwanted events. This paper considers development of method for inclusion vulnerability assessment in land use planning with objective to assess and limit the consequences in cities of likely accidents involving hazardous materials. We made preliminary assessment of criticality and vulnerability of the assets within Belgrade city area in respect to chemical sites and transportation roads that can be exposed to chemical accidents, or terrorist attacks.

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)

Utility of Interobserver Agreement Statistics in Establishing Radiology Resident Learning Curves During Self-directed Radiologic Anatomy Training.

Science.gov (United States)

Tureli, Derya; Altas, Hilal; Cengic, Ismet; Ekinci, Gazanfer; Baltacioglu, Feyyaz

2015-10-01

The aim of the study was to ascertain the learning curves for the radiology residents when first introduced to an anatomic structure in magnetic resonance images (MRI) to which they have not been previously exposed to. The iliolumbar ligament is a good marker for testing learning curves of radiology residents because the ligament is not part of a routine lumbar MRI reporting and has high variability in detection. Four radiologists, three residents without previous training and one mentor, studied standard axial T1- and T2-weighted images of routine lumbar MRI examinations. Radiologists had to define iliolumbar ligament while blinded to each other's findings. Interobserver agreement analyses, namely Cohen and Fleiss κ statistics, were performed for groups of 20 cases to evaluate the self-learning curve of radiology residents. Mean κ values of resident-mentor pairs were 0.431, 0.608, 0.604, 0.826, and 0.963 in the analysis of successive groups (P 0.8). Therefore, a junior radiology resident can obtain enough experience in identifying a rather ambiguous anatomic structure in routine MRI after a brief instruction of a few minutes by a mentor and studying approximately 80 cases by oneself. Implementing this methodology will help radiology educators obtain more concrete ideas on the optimal time and effort required for supported self-directed visual learning processes in resident education. Copyright © 2015 AUR. Published by Elsevier Inc. All rights reserved.

The prevention of the local nuclear accidents in the Republic of Moldova

International Nuclear Information System (INIS)

Bahnarel, I.

1998-01-01

Although there are no nuclear reactors in Moldova, there are numerous radiation sources situated in a few waste disposal sites as well as the sources applied in medicine, science, education, industry, agriculture, which demand serious concern from safety and radiation protection point of view. Under cooperation with IAEA national Regulatory Control in the Field of Nuclear Protection and Safety was established since 1993. A number of governmental regulatory bodies supervise the following activities: radiation standardization; radiological supervision of sources storage, exploitation and disposal; radiological monitoring of radioactive substances, food products, building materials; supervision of personnel exposure and environmental exposure; investigation of radiological accidents; etc. In 1998, Moldova has joined The International Convention for early Notification of Nuclear Accidents; The Convention on Nuclear Safety; The Convention on Assistance in Case of Nuclear Accident of Radiological Emergency and The Convention on the Physical protection of Nuclear Material

Radiological protection Program of CDTN

International Nuclear Information System (INIS)

1983-01-01

Radiological protection program of CDTN, its purposes and rules, responsabilities, physical control, monitoring, personnel radiation protection, radiation sources and radioactive wastes control, emergency and accidents and siting are described. (C.M.) [pt

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

Estimation of radiological consequences from accidental iodine releases at nuclear power plants

International Nuclear Information System (INIS)

Drozdovitch, V.V.

2001-01-01

The radiological consequences of a beyond design-basis accident at an NPP for a VVER-1000 reactor are evaluated. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Inhalation and ingestion thyroid doses to different population sub-groups have been calculated. Using modern knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways. Thyroid doses and risk was estimated for populations living at different distances from the NPP. The comparative analysis of exposure pathways and radiological danger of the radionuclides in release during early and intermediate stage of accident has conducted. (author)

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.

Post-accident monitoring systems in Prototype Fast Breeder Reactor

International Nuclear Information System (INIS)

Suriya Murthy, N.; Sivasailanathan, Vidhya; Ananth, Allu; Roy, Kallol

2018-01-01

PFBR is a 500 MW(e) MOX fueled and sodium cooled fast reactor (SFR) under advanced stage of commissioning at Kalpakkam. Currently, the main vessel is preheated and sodium has been charged into two secondary loops that are operated in recirculation mode. In order to characterize the radiation field and contamination, the workplace monitoring is undertaken using installed monitors that are commissioned and made operational. This helps to ensure radiological protection during normal operating conditions. On the other hand, radiological monitoring in emergency conditions is quite different. For undertaking the mitigative accident management, a set of specialized nuclear instruments called post-accident monitoring systems (PAMS) which include radiation monitors are stipulated. The Fukushima Daiichi accident emphasized the importance and need for reliable accident monitoring instrumentation to indicate the safety functions during the progression and aftermath of accident in NPP. In PFBR, the PAMS are integrated with other monitoring systems in design stage itself to manage the measurements and indicating the safety functions for implementing EOP and SAMG

Radiological Emergency Preparedness using Old ORTEC Whole Body Counter

International Nuclear Information System (INIS)

Badawy, W.M.

2012-01-01

During a radiological emergency (RE) a large number of occupational and public may be exposed externally and to a number of radionuclides internally as a result of inhalation or injection. The radiological effect is directly proportional to the time of exposure and the activity of the contaminant materials. The main task of this paper is to show the emergency preparedness capability of using the old ORTEC whole body counter (WBC). In case of a nuclear accident ORTEC WBC is ready for use to estimate the radioactivity which inhaled or digested with food, as well as in case of medical exposure in general and nuclear medicine in particular. The present study showed that the duration time to make analysis for only one individual is about 25 min. Hence 57 individuals are monitored per day. Consequently, old ORTEC WBC is effective tool in field of research and limited use for radiological and nuclear emergencies

Populations protection and territories management in nuclear emergency and post-accident situation

International Nuclear Information System (INIS)

Bourrel, M.; Calmon, Ph.; Calvez, M.; Chambrette, V.; Champion, D.; Devin, P.; Godino, O.; Lombard, J.; Rzepka, J.P.; Schneider, Th.; Verhaeghe, B.; Cogez, E.; Kayser, O.; Guenon, C.; Jourdain, J.R.; Bouchot, E.; Murith, Ch.; Lochard, J.; Cluchier, A.; Vandecasteele, Ch.; Pectorin, X.; Dubiau, Ph.; Gerphagnon, O.; Roche, H.; Cessac, B.; Cochard, A.; Machenaud, G.; Jourdain, J.R.; Pirard, Ph.; Leger, M.; Bouchot, E.; Demet, M.; Charre, J.P.; Poumadere, M.; Cogez, E.

2010-01-01

This document gathers the slides of the available presentations given during these conference days. Twenty seven presentations out of 29 are assembled in the document and deal with: 1 - radiological and dosimetric consequences in nuclear accident situation: impact on the safety approach and protection stakes (E. Cogez); 2 - organisation of public authorities in case of emergency and in post-event situation (in case of nuclear accident or radiological terror attack in France and abroad), (O. Kayser); 3 - ORSEC plan and 'nuclear' particular intervention plan (PPI), (C. Guenon); 4 - thyroid protection by stable iodine ingestion: European perspective (J.R. Jourdain); 5 - preventive distribution of stable iodine: presentation of the 2009/2010 public information campaign (E. Bouchot); 6 - 2009/2010 iodine campaign: presentation and status (O. Godino); 7 - populations protection in emergency and post-accident situation in Switzerland (C. Murith); 8 - CIPR's recommendations on the management of emergency and post-accident situations (J. Lochard); 9 - nuclear exercises in France - status and perspectives (B. Verhaeghe); 10 - the accidental rejection of uranium at the Socatri plant: lessons learnt from crisis management (D. Champion); 11 - IRE's radiological accident of August 22, 2008 (C. Vandecasteele); 12 - presentation of the CEA's crisis national organisation: coordination centre in case of crisis, technical teams, intervention means (X. Pectorin); 13 - coordination and realisation of environmental radioactivity measurement programs, exploitation and presentation of results: status of IRSN's actions and perspectives (P. Dubiau); 14 - M2IRAGE - measurements management in the framework of geographically-assisted radiological interventions in the environment (O. Gerphagnon and H. Roche); 15 - post-accident management of a nuclear accident - the CODIRPA works (I. Mehl-Auget); 16 - nuclear post-accident: new challenges of crisis expertise (D. Champion); 17 - aid guidebooks

Method for the analysis pre and post radiological emergency (MAPPER)

International Nuclear Information System (INIS)

Perez Velazquez, R.S.; Perez Gonzalez, F.; Fornet Rodriguez, O.; Mustelier Echavarria, A.; Miller Clemente, R.A.

1998-01-01

Everything practices associated to the employment he/she gives ionizing radiations it generates a risk, and therefore the possibility exists potentially, he/she gives occurrences he/she gives a radiological accident. Assisting it, all the entities where the nuclear techniques are applied, they should have a method that allows them to evaluate, before y/o after having happened a radiological accident, if the planning and preparation to face emergencies give this it is or it has been effective

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

Methodology used in IRSN nuclear accident cost estimates in France

International Nuclear Information System (INIS)

2015-01-01

This report describes the methodology used by IRSN to estimate the cost of potential nuclear accidents in France. It concerns possible accidents involving pressurized water reactors leading to radioactive releases in the environment. These accidents have been grouped in two accident families called: severe accidents and major accidents. Two model scenarios have been selected to represent each of these families. The report discusses the general methodology of nuclear accident cost estimation. The crucial point is that all cost should be considered: if not, the cost is underestimated which can lead to negative consequences for the value attributed to safety and for crisis preparation. As a result, the overall cost comprises many components: the most well-known is offsite radiological costs, but there are many others. The proposed estimates have thus required using a diversity of methods which are described in this report. Figures are presented at the end of this report. Among other things, they show that purely radiological costs only represent a non-dominant part of foreseeable economic consequences. (authors)

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)

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

Radiological consequence analysis of a repository for radioactive waste

International Nuclear Information System (INIS)

Fitzpatrick, J.; Buchheim, B.; Hoop, F.J.

1982-01-01

One of the methods under consideration for the disposal of radioactive wastes is emplacement in a repository within deep, continental formations. This paper presents the experience gained in developing a methodology to make an assessment of the radiological consequences both for normal operation and for possible accident situations for a specific repository design in a salt dome at Gorleben in Germany , designed to accommodate all categories of radioactive waste. Radionuclide release scenarios were derived from a systematic analysis of the facility design and proposed operational procedure. Where necessary simple numerical models for such topics as direct radiation exposure from waste containers, release and transport of radionuclides, radiolysis, heat transfer, creep and impact were developed to give a first estimate of the radiological consequences due to radionuclide releases. (author)

Comparison of toxicological and radiological aspects of K basins sludge

International Nuclear Information System (INIS)

RITTMANN, P.D.

1999-01-01

The composition of various K Basins sludge is evaluated for its toxicological and radiological impacts downwind from accidents. It is shown that the radiological risk evaluation guidelines are always more limiting than the toxicological risk evaluation guidelines

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)

Psychical and social effects related to post-accident situations: some training of Chernobyl accident

International Nuclear Information System (INIS)

Lochand, J.

1995-01-01

Some preliminary considerations on the psychic and societal dimensions related to post-accident situations connected to large scale and heavy land contamination are presented. This is done with the objective of exploring the role that these dimensions could play in the elaboration of new radiological protection principles and concepts in order to restore confidence among affected populations after a nuclear accident. It is important to facilitate the return to normal or, at least, acceptable living conditions, as soon as reasonably achievable, and to prevent the possible emergence of a post-accident crisis. A scheme is proposed for understanding the dynamics of the various phases after an accident, taking into account the collective response to the consequences as well as, the response to the countermeasures. (Author)

Accident analysis in nuclear power plants

International Nuclear Information System (INIS)

Silva, D.E. da

1981-01-01

The way the philosophy of Safety in Depth can be verified through the analysis of simulated accidents is shown. This can be achieved by verifying that the integrity of the protection barriers against the release of radioactivity to the environment is preserved even during accident conditions. The simulation of LOCA is focalized as an example, including a study about the associated environmental radiological consequences. (Author) [pt

International scaling of nuclear and radiological events

International Nuclear Information System (INIS)

Wang Yuhui; Wang Haidan

2014-01-01

Scales are inherent forms of measurement used in daily life, just like Celsius or Fahrenheit scales for temperature and Richter for scale for earthquakes. Jointly developed by the IAEA and OECD/NEA in 1990, the purpose of International Nuclear and Radiological Event Scale (INES) is to help nuclear and radiation safety authorities and the nuclear industry worldwide to rate nuclear and radiological events and to communicate their safety significance to the general public, the media and the technical community. INES was initially used to classify events at nuclear power plants only. It was subsequently extended to rate events associated with the transport, storage and use of radioactive material and radiation sources, from those occurring at nuclear facilities to those associated with industrial use. Since its inception, it has been adopted in 69 countries. Events are classified on the scale at seven levels: Levels 1-3 are called 'incidents' and Levels 4-7 'accidents'. The scale is designed so that the severity of an event is about ten times greater for each increase in level on the scale. Events without safety significance are called 'deviations' and are classified Below Scale/Level 0. INES classifies nuclear and radiological accidents and incidents by considering three areas of impact: People and the Environment; Radiological Barriers and Control; Defence-in-Depth. By now, two nuclear accidents were on the highest level of the scale: Chernobyl and Fukumashi. (authors)

Estimation of radiological consequences from accidental iodine releases at nuclear power plants

International Nuclear Information System (INIS)

Drozdovich, V.V.

2000-01-01

To evaluate the radiological consequences of a beyond design-basis accident at an NPP for a WWER-1000 reactor, a preliminary investigation was conducted. The scenario of the hypothetical accident was a fast loss of coolant as a result of a rupture in the primary circuit pipeline with diameter of 850 mm and minimum radiation consequences when containment integrity is preserved. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Using modem knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways: (a) extemal exposure from radionuclides in air; (b) extemal exposure from radionuclides deposited on the ground surface; (c) internal exposures from inhalation of radionuclides in air; and (d) internal exposure from ingestion of radionuclides with contaminated foodstuffs. Risk was estimated for populations living at different distances from the source. Preliminary results show that the methodology and models can be applied to the evaluation of radiological danger of an accident at an NPP. Experience from the Chernobyl accident has shown that the damage from a radiation accident can be vast. Expenditures on advanced simulations of the different accident scenarios are worth the cost because they allow radiation protection of populations for these low probability cases, but nevertheless possible accidents at an NPP. (authors)

Socioeconomic consequences of nuclear reactor accidents

International Nuclear Information System (INIS)

Tawil, J.J.; Callaway, J.W.; Coles, B.L.; Cronin, F.J.; Currie, J.W.; Imhoff, K.L.; Lewis, P.M.; Nesse, R.J.; Strenge, D.L.

1984-06-01

This report identifies and characterizes the off-site socioeconomic consequences that would likely result from a severe radiological accident at a nuclear power plant. The types of impacts that are addressed include economic impacts, health impacts, social/psychological impacts and institutional impacts. These impacts are identified for each of several phases of a reactor accident - from the warning phase through the post-resettlement phase. The relative importance of the impact during each accident phase and the degree to which the impact can be predicted are indicated. The report also examines the methods that are currently used for assessing nuclear reactor accidents, including development of accident scenarios and the estimating of socioeconomic accident consequences with various models. Finally, a critical evaluation is made regarding the use of impact analyses in estimating the contribution of socioeconomic consequences to nuclear accident reactor accident risk. 116 references, 7 figures, 15 tables

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.)

Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations

International Nuclear Information System (INIS)

Cowley, W.L.

1996-01-01

The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms

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)

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...

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)

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)

Methodology applied by IRSN for nuclear accident cost estimations in France

International Nuclear Information System (INIS)

2013-01-01

This report describes the methodology used by IRSN to estimate the cost of potential nuclear accidents in France. It concerns possible accidents involving pressurized water reactors leading to radioactive releases in the environment. These accidents have been grouped in two accident families called: severe accidents and major accidents. Two model scenarios have been selected to represent each of these families. The report discusses the general methodology of nuclear accident cost estimation. The crucial point is that all cost should be considered: if not, the cost is underestimated which can lead to negative consequences for the value attributed to safety and for crisis preparation. As a result, the overall cost comprises many components: the most well-known is offsite radiological costs, but there are many others. The proposed estimates have thus required using a diversity of methods which are described in this report. Figures are presented at the end of this report. Among other things, they show that purely radiological costs only represent a non-dominant part of foreseeable economic consequences

French policy for managing the post-accident phase of a nuclear accident.

Science.gov (United States)

Gallay, F; Godet, J L; Niel, J C

2015-06-01

In 2005, at the request of the French Government, the Nuclear Safety Authority (ASN) established a Steering Committee for the Management of the Post-Accident Phase of a Nuclear Accident or a Radiological Emergency, with the objective of establishing a policy framework. Under the supervision of ASN, this Committee, involving several tens of experts from different backgrounds (e.g. relevant ministerial offices, expert agencies, local information commissions around nuclear installations, non-governmental organisations, elected officials, licensees, and international experts), developed a number of recommendations over a 7-year period. First published in November 2012, these recommendations cover the immediate post-emergency situation, and the transition and longer-term periods of the post-accident phase in the case of medium-scale nuclear accidents causing short-term radioactive release (less than 24 h) that might occur at French nuclear facilities. They also apply to actions to be undertaken in the event of accidents during the transportation of radioactive materials. These recommendations are an important first step in preparation for the management of a post-accident situation in France in the case of a nuclear accident. © The Chartered Institution of Building Services Engineers 2014.

Accident progression event tree analysis for postulated severe accidents at N Reactor

International Nuclear Information System (INIS)

Wyss, G.D.; Camp, A.L.; Miller, L.A.; Dingman, S.E.; Kunsman, D.M.; Medford, G.T.

1990-06-01

A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied

United States Department of Energy radiological emergency response programme - a national capability

International Nuclear Information System (INIS)

Gordon-Hagerty, L.E.

1993-01-01

In order to respond to a radiological emergency, the United States Department of Energy (USDOE) maintains seven emergency response assets and capabilities in support of a radiological emergency of any proportion within the continental United States and abroad. The seven emergency response assets and capabilities include: Accident Response Group; Aerial Measuring Systems; Atmospheric Release Advisory Capability; Federal Radiological Monitoring and Assessment Center; Nuclear Emergency Search Team; Radiation Emergency Assistance Center/Training Site; and Radiological Assistance Program. Presently, USDOE maintains the most comprehensive national radiological emergency response assets in the United States, capable of dealing with any type of emergency involving nuclear materials. In all, the Department's assets are available to support any type of accident/incident involving radioactive materials in coordination with other United States Federal agencies, as well as state and local governments, as required. (author)

Kyshtym riddle: possible kind of the accident

International Nuclear Information System (INIS)

Ballereau, P.

1988-01-01

It can been postulated from varied rumors, soviet testimonies, analysis of radioecological russian publications that a serious radiological accident occurred in late 1957 - early 1958 in the Oural mountains. Isotopic ratio 90 Sr/ 137 Cs in the environment following the accident was abnormally high. Several types of accidents has been postulated; the more credible event is an explosion in a storage tank containing dried high activity wastes and NH 4 N0 3 , from which 137 Cs had been extracted [fr

Accidents in nuclear facilities: classification, incidence and impact

International Nuclear Information System (INIS)

Galicia A, J.; Paredes G, L. C.

2012-10-01

A general analysis of the 146 accidents reported officially in nuclear facilities from 1945 to 2012 is presented, among them some took place in: power or research nuclear reactors, critical and subcritical nuclear assemblies, handling of nuclear materials inside laboratories belonging to institutes or universities, in radiochemistry industrial plants and nuclear fuel factories. In form graph the incidence of these accidents is illustrated classified for; category, decades, geographical localization, country classification before the OECD, failure type, and the immediate or later victims. On the other hand, the main learned lessons of the nuclear accidents of Three Mile Island, Chernobyl and Fukushima are stood out, among those that highlight; the human factors, the necessity of designs more innovative and major technology for the operation, control and surveillance of the nuclear facilities, to increase the criterions of nuclear, radiological and physics safety applied to these facilities, the necessity to carry out probabilistic analysis of safety more detailed for cases of not very probable accidents and their impact, to revalue the selection criterions of the sites for nuclear locations, the methodology of post-accident sites recovery and major instrumentation for parameters evaluation and the radiological monitoring among others. (Author)

The yellow cake accident at the Ezeiza Airport

International Nuclear Information System (INIS)

Rodriguez, C.E.; Puntarulo, L.J.; Canibano, J.A.

1989-01-01

In January 1987 several drums containing yellow cake fell from about six meters during the loading operation of a Boeing 747 T-100 cargo aircraft. As a result of the accident, about 50% of the 38 drums involved lost their lids and a fraction of the radioactive content was released on an area of about 200 meters squared. Small amounts of yellow cake were dispersed down wind until about 100 meters from the accident place. The shipment was prepared for transport in standard 200 liter steel drums fulfilling the applicable Transport Regulations and the accident was the consequence of an erroneous operation during the cargo associated with a mechanical failure of the cargo lift. In order to avoid human contamination, immediate action was taken by the airport emergency team and in the meantime, the specialized groups of the National Atomic Energy Commission and the Federal Fire Brigades, were convened to take care of the decontamination and radiological evaluation problems. This paper describes the accidental sequences, the accident scenery, the countermeasures taken, the recovery and decontamination actions, and finally, as a conclusion, a brief description of the toxic and radiological aspects of the accident's mode

Accident analysis for transuranic waste management alternatives in the U.S. Department of Energy waste management program

International Nuclear Information System (INIS)

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

1995-01-01

Preliminary accident analyses and radiological source term evaluations have been conducted for transuranic waste (TRUW) as part of the US Department of Energy (DOE) effort to manage storage, treatment, and disposal of radioactive wastes at its various sites. The approach to assessing radiological releases from facility accidents was developed in support of the Office of Environmental Management Programmatic Environmental Impact Statement (EM PEIS). The methodology developed in this work is in accordance with the latest DOE guidelines, which consider the spectrum of possible accident scenarios in the implementation of various actions evaluated in an EIS. The radiological releases from potential risk-dominant accidents in storage and treatment facilities considered in the EM PEIS TRUW alternatives are described in this paper. The results show that significant releases can be predicted for only the most severe and extremely improbable accidents sequences

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)

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

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1994-03-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

The TMI-2 accident

International Nuclear Information System (INIS)

Loureiro, L.A.

1986-01-01

A critical study about the technical and man-related facts in order to establish what is considered the worst commercial nuclear power accident until 1986. Radiological consequences and stress to the public are considered in contrast to antinuclear groups. This descriptive and technical study has the purpose to document written and oral opinions obtained abroad and then explain to the public in an easy language terminology. Preliminary study describing safety related systems fails and the accident itself with minute to minute description, conduct to the consequences and then, to learned lessons

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

The influence of the operating schedule of the Greek Research Reactor on the radiological consequences of the reactor

International Nuclear Information System (INIS)

Kollas, J.G.

1986-04-01

The sensitivity of the radiological consequences of the Greek Research Reactor to the operating schedule of the reactor is assessed in this report. The consequences are due to the occurrence of a postulated accident, a 20% core melt loss of coolant accident. Three different operating schedules are considered: (a) the present 8 hrs/day, 5 days/wk schedule, (b) a 16 hrs/day, 5 days/wk schedule, and (c) a continuous operation schedule. The results of the analysis indicate that there is a direct relation between consequences and duration of operation. (author)

Planning and preparedness for radiological emergencies at nuclear power stations

International Nuclear Information System (INIS)

Thomson, R.; Muzzarelli, J.

1996-01-01

The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

The lessons from the radiation accidents in China over the past 40 years

International Nuclear Information System (INIS)

Zhang, Y.; Ma, J.; Yang, J.

1998-01-01

A brief introduction and analysis of the radiological accidents in China during the past 40 years have been made in this paper. Statistical data provided by the competent authority show that a number of cases of radiological accidents and events happened in China from 1954 to 1994. Quite a few persons received abnormal exposure. Some serious accidents resulted in death of 8 victims. The reasons of these accidents are analyzed and some recommendations for reduction of potential exposure and accidents involving radiation sources and equipment generating ionization radiation have been given, such as perfecting and improving radiation safety infrastructure and system for the control of radiation sources. It is suggested that safety culture shall be fostered, each individual must be suitably trained and qualified and the management of spent sources should be strengthened. (author)

Interactions between multiple organizations responding to a reactor accident in Switzerland

International Nuclear Information System (INIS)

Baggenstos, M.; Isaak, H.P.

1987-01-01

The poster deals with the problems that emerge from the distribution of responsibilities in the case of a nuclear accident. It is demonstrated how clear and simple procedures and good co-ordination between the onsite and offsite emergency organizations are necessary for the smooth handling of such a situation. A good communications network is particularly essential. The special problem of co-ordination between different organizations performing measurements of the contaminated air, ground and food is also discussed. From the experience gained during the Chernobyl accident, it has been established that only those organizations, which are correctly trained and have a perspective over the complete accident situation, can perform valuable work. At the beginning of the accident for example, there was no organization responsible for taking samples covering the whole of Switzerland. A first quick assessment of the radiological situation could therefore only be made on the basis of measurements performed in the direct vicinity of the laboratories or from single samples which had to be transported over large distances

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)

Criticality accidents in solution (CRAC and SILENE programmes) and complementary studies of accidents; radiation dosimetry in human organism during the CRAC programme

International Nuclear Information System (INIS)

Barbry, M.; Dousset, M.

C.R.A.C. (CRiticality occurring ACcidentally) programme is intended to study experimentally the development of a criticality accident as it could occur when handling solutions of fissile material as well as the radiological consequences of such an accident. The fissile matter solutions have been chosen (a) for practical considerations of use and (b) because the probability of an accident occurring seems greater with this type of environment, as the known accidents have shown. The programme is twofold: study of accident physics: form of the evolution (peak, plateau, oscillations, boil up of solutions) the most probable maximum power, minimal power, flux and radiation spectra emitted, freed energy, associated effects, radiolysis, constraints, etc., study of radiological consequences: area dosimetry, individual dosimetry, radiobiological studies, etc. Additional criticality Accident experiments have been and continue to be made on the SILENE reactor in the following principal domains: determination of the emission rate of gaseous fission products and aerosols, area dosimetry and health dosimetry in the presence of shields around the core to vary the neutron and gamma components of the radiation field. Improvement in the knowledge of certain particular aspects of the power excursion, radiolysis gas and pressure wave, experiments of the ''boiling'' type [fr

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)

Main post-accident management stakes: IRSN's point of view

International Nuclear Information System (INIS)

Andre Oudiz

2006-01-01

scrutiny. 2) New governance modes reflection: IRSN is carrying out analysis and implementation of expertise procedures aimed at directly involving the stakeholders. Openness to stakeholders is from now on a strategic orientation of the Institute, hence the implementation of a 'stakeholders' mission within IRSN. In the context of the recovery phase, the EURANOS programme provides the opportunity to work with local actors originating from SNASA in Norway, from Dunkirq, Rouillac and Montbeliard in France, on designing adequate governance modes to handle the social, economical, psychological, cultural consequences of a potential long lasting contamination (radiological or chemical) in a territory. Besides, IRSN is involved in the CORE (Cooperation for Rehabilitation) programme implemented in Belarus, more particularly in the 'Health' and 'Radiological culture, education, memory' projects. These projects allow the IRSN teams working in close cooperation with health professionals, mothers, teachers and local education staff in several Belarus districts which were contaminated by the Chernobyl accident fall out. (author)

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

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

International Nuclear Information System (INIS)

1995-10-01

There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

Radiological consequence evaluation of DBAs with alternative source term method for a Chinese PWR

International Nuclear Information System (INIS)

Li, J.X.; Cao, X.W.; Tong, L.L.; Huang, G.F.

2012-01-01

Highlights: ► Radiological consequence evaluation of DBAs with alternative source term method for a Chinese 900 MWe PWR has been investigated. ► Six typical DBA sequences are analyzed. ► The doses of control room, EAB and outer boundary of LPZ are acceptable. ► The differences between AST method and TID-14844 method are investigated. - Abstract: Since a large amount of fission products may releases into the environment, during the accident progression in nuclear power plants (NPPs), which is a potential hazard to public risk, the radiological consequence should be evaluated for alleviating the hazard. In most Chinese NPPs the method of TID-14844, in which the whole body and thyroid dose criteria is employed as dose criteria, is currently adopted to evaluate the radiological consequences for design-basis accidents (DBAs), but, due to the total effective dose equivalent is employed as dose criteria in alternative radiological source terms (AST) method, it is necessary to evaluate the radiological consequences for DBAs with AST method and to discuss the difference between two methods. By using an integral safety analysis code, an analytical model of the 900 MWe pressurized water reactor (PWR) is built and the radiological consequences in DBAs at control room (CR), exclusion area boundary (EAB), low population zone (LPZ) are analyzed, which includes LOCA and non-LOCA DBAs, such as fuel handling accident (FHA), rod ejection accident (REA), main steam line break (MSLB), steam generator tube rupture (SGTR), locked rotor accident (LRA) by using the guidance of the RG 1.183. The results show that the doses in CR, EAB and LPZ are acceptable compared with dose criteria in RG 1.183 and the differences between AST method and TID-14844 method are also discussed.

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

Operational intervention levels and related requirements on radiation monitoring during pre-release / release phase of an accident

International Nuclear Information System (INIS)

Carny, P.; Cabanekova, H

2003-01-01

In this paper authors discusses required outputs of emergency radiological monitoring in various phases of an accident and rationale of these requirements. In various phases of an accident various intervention levels are important and consequently various radiological quantities should be preferably measured. Distinguished tasks or aims of monitoring in different phases of accident have strong influence on methods of monitoring, instrumentation and capabilities of monitoring groups. Required tasks and outputs of monitoring are discussed

Dose calculation for accident situations at WWR-S type spent nuclear fuel repository

International Nuclear Information System (INIS)

Margeanu, S.; Florescu, G.

2006-01-01

Full text: The Spent Nuclear Fuel Repository at IFIN-HH Bucharest (SNFR IFIN-HH) consists in four pools, repository hall, radiological monitoring system, ventilation system and auxiliary systems. At the moment the remaining activity in the repository is about 3500 Ci. Despite of the small activity, for emergency preparedness purposes, several accident scenarios, with a non zero probability of occurrence during the repository lifetime, have been postulated. Evaluations of radiological consequences to personnel, general public and environment, for each accident scenario have been performed. The radioactive inventory was evaluated with ORIGEN code from SCALE computer code system and radiological consequences were evaluated with COSYMA computer code. Assumptions for the source term determination, meteorological conditions and release, are presented. The calculated values of doses and risk are also presented. The impact of these accident scenarios on population and environment is also discussed. (authors)

Health consequences [of the Chernobyl accident

International Nuclear Information System (INIS)

Ramoutar, S.

1996-01-01

The World Health Organisation Conference on the Health Consequences of the Chernobyl and Other Radiological Accidents, held in Geneva last November, is reported. The lack of representation from the civil nuclear industry led often to one-sided debates instigated by the anti-nuclear lobbies present. Thyroid cancer in children as a result of the Chernobyl accident received particular attention. In Belarus, 400 cases have been noted, 220 in Ukraine and 60 in the Russian Federation. All have been treated with a high degree of success. The incidence of this cancer would be expected to follow the fallout path as the main exposure route was ingestion of contaminated foods and milk products. It was noted that the only way to confirm causality was if those children born since the accident failed to show the same increased incidence. Explanations were offered for the particular susceptibility of children to thyroid cancer following exposure to radiation. Another significant cause of concern was the health consequences to clean-up workers in radiological accidents. The main factor is psychological problems from the stress of knowing that they have received high radiation doses. A dramatic increase in psychological disorders has occurred in the Ukraine over the past ten years and this is attributed to stress generated by the Chernobyl accident, compounded by the inadequacy of the public advice offered at the time and the socio-economic uncertainties accompanying the breakup of the former USSR. (UK)

A methodology for the transfer of probabilities between accident severity categories

International Nuclear Information System (INIS)

Whitlow, J.D.; Neuhauser, K.S.

1992-01-01

Evaluation of the radiological risks of accidents involving vehicles transporting radioactive materials requires consideration of both accident probability and consequences. The probability that an accident will occur may be estimated from historical accident data for the given mode of transport. In addition to an overall accident rate, information regarding accident severity and the resulting package environments across the range of all credible accidents is needed to determine the potential for a release of radioactive material from the package or for an increase in direct radiation from the package caused by damage to packaging shielding. This information is usually obtained from a variety of sources such as historical data, experimental data, analyses of accident and package environments, and expert opinion. The consequences of an accident depend on a number of factors including the type, quantity, and physical form of radioactive material being transported; the response of the package to accident environments; the fraction of material released from the package; and the dispersion of any released material. One approach for the classification and treatment of transportation accidents in risk analysis divides the complete range of critical accident environments resulting from all credible accidents into some number of accident-severity categories. The types of accident environments that a package may be subjected to in transportation are often classified into the following five groups: impact, fire, crush, puncture, and immersion. A open-quotes criticalclose quotes accident environment is one of a type that could present a plausible threat to a package. Each severity category represents a portion of all credible accidents, and the total of all severity categories covers the complete range of critical accident environments. This approach is used in the risk assessment codes RADTRAN (Neuhauser and Kanipe 1992) and INTERTRAN (Ericsson and Elert 1983)

Tchernobyl accident

International Nuclear Information System (INIS)

1986-06-01

First, R.M.B.K type reactors are described. Then, safety problems are dealt with reactor control, behavior during transients, normal loss of power and behavior of the reactor in case of leak. A possible scenario of the accident of Tchernobyl is proposed: events before the explosion, possible initiators, possible scenario and events subsequent to the core meltdown (corium-concrete interaction, interaction with the groundwater table). An estimation of the source term is proposed first from the installation characteristics and the supposed scenario of the accident, and from the measurements in Europe; radiological consequences are also estimated. Radioactivity measurements (Europe, Scandinavia, Western Europe, France) are given in tables (meteorological maps and fallouts in Europe). Finally, a description of the site is given [fr

Chernobyl accident: lessons learned for radiation protection

International Nuclear Information System (INIS)

Kenigsberg, Jacov

2008-01-01

Full text: The long-term nature of the consequences of the accident at the Chernobyl nuclear power plant, which was a major technological catastrophe in terms of its scope and complexity and created humanitarian, environmental, social, economic and health consequences. After more than twenty years we can conclude that Chernobyl accident was requested the big efforts of the national governments and international organisations for improvement new approaches to radiation safety, radiation protection, health care, emergency preparedness and response. During first years after accident some response actions did more harm than good because not based on international radiation protection principles, based on criteria developed during emergency and associated with mistrust, emotions, political pressure. As a result was inappropriate government reaction: unjustified relocation and decontamination - loss jobs, homes, billions of $ cost; unjustified compensation (high portion of annual national budgets). Non-radiological (e.g. detrimental economic, social and psychological) consequences was worse than direct radiological consequences. Psychological effects do not correlate with real exposure but with perception of risk. The affected people believe in threat to their health, doubt what has been reported about accident and resulted doses, got modification in life style, have somatic complains, got substance abuse (alcohol, tranquilizers, sleeping pills). The lack of accurate information and misperception of real radiation risk is believed also to have lead to change in behavior of some affected people. Possible long-term health effect due to the accidental exposure remains an issue. There is no doubt that excess thyroid cancer incidence results from exposure to radioactive iodines, mainly by iodine-131. Radiation induced thyroid cancer could easily be prevented by timely warning, effective thyroid blocking, timely restriction of consumption for contaminated food. The

Return on experience on nuclear accidents

International Nuclear Information System (INIS)

Barre, Bertrand

2015-09-01

After a presentation of the International Nuclear and radiological Events Scale (INES scale), of its levels and criteria, this article proposes brief recalls of some nuclear accidents which occurred in nuclear reactors: Chalk River in Canada (1952), Windscale in England (1957), the universal Canadian reactor (NRU in 1958), the SL1 reactor of the Idaho National Laboratory in the USA (1961), the Swiss Lucens reactor (1969), Saint-Laurent des Eaux in France (1969 and 1980). More detailed descriptions are then given for the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima accident in 2011. The main causes of these accidents are identified: loss of control of chain reaction, cooling defect on a stopped reactor, cooling defect on an operated reactor. Some lessons are drawn from these facts, and some characteristics of the EPR are outlined with respect with problems encountered in these accidents

The consequences of the Chernobyl nuclear accident in Greece

International Nuclear Information System (INIS)

1986-07-01

In this report the radioactive fallout on Greece from the Chernobyl nuclear accident is described. The flow pattern to Greece of the radioactive materials released, the measurements performed on environmental samples and samples of the food chain, as well as some estimations of the population doses and of the expected consequences of the accident are presented. The analysis has shown that the radiological impact of the accident in Greece can be considered minor. (J.K.)

Calculation of health risks from spent-nuclear-fuel transportation accidents

International Nuclear Information System (INIS)

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

1987-01-01

Models developed to analyze potential radiological health risks from various accident scenarios during transportation of spent nuclear fuels are described. The models are designed both for detailed route-specific risk analyses and for use in conducting overall risk analyses for route selection and related decision-making activities. The radiological risks calculated include individual dose commitments, collective dose commitments, and long-term (100-year) environmental dose commitments to a population following release of radioactivity. To facilitate route-specific analysis, a state-level database was developed and incorporated into the model. Route-specific analysis is demonstrated by the calculation of radiological risks resulting from various accident scenarios, as postulated by the recent US Nuclear Regulatory Commission Modal Study, for four representative states selected from various regions of the United States. 10 refs., 3 figs., 3 tabs

Technical support and preparations for the response to radiological emergencies; Soporte tecnico y preparativos para la respuesta a emergencias radiologicas

Energy Technology Data Exchange (ETDEWEB)

Cardenas H, J; Ramos V, E O; Fernandez G, I M; Capote F, E; Zerquera J, T; Garcia L, O; Lopez B, G; Molina P, D; Lamdrid B, A I; Benitez N, J C; Salgado M, M [CPHR, Calle 20 No. 4113, e/41 y 47 Playa, CP 11300, La Habana (Cuba); Lopez F, Y; Jerez V, P [CNSN, Calle 28 e/5ta y 7ta, Playa, La Habana (Cuba)

2006-07-01

The work picks up the efforts directed to elevate the technical capacity of the answer in front of the radiological emergencies. Expressing them by means of the actions carried out as for teaching, research and development and intervention before accidental radiological events. The same one reflects the leading role of the participant institutions in those marks of the answer system to radiological emergencies that for its technical level it satisfies the national and international demands in the matter. In execution of the mentioned goals research projects guided to endow to the national system of methodologies and procedures for the administration of radiological emergencies have been executed that favor the improvement of its technical and organizational capacities. As well as the postulates of the National Plan of Measures for Case of Catastrophes in the corresponding to radiological accidents. (Author)

Dosimetry on the radiological risks prevention in radiotherapy

International Nuclear Information System (INIS)

Fornet R, O. M.; Perez G, F.

2014-08-01

Dosimetry in its various forms plays a determining role on the radiological risks prevention in radiotherapy. To prove this in this paper is shown an analysis based on the risk matrix method, how the dosimetry can influence in each stages of a radiotherapy service; installation and acceptance, operation, maintenance and calibration. For each one of these stages the role that can play is analyzed as either the initiating event of a radiological accident or limiting barrier of these events of the dosimetric processes used for the individual dosimetry, the area monitoring, fixed or portable, for radiation beam dosimetry and of the patients for a radiotherapy service with cobalt-therapy equipment. The result of the study shows that the application of a prospective approach in the role evaluation of dosimetry in the prevention and mitigation of the consequences of a radiological accident in radiotherapy is crucial and should be subject to permanent evaluation at each development stage of these services. (author)

Effect of direct neuroradiologist participation in physician marketing on imaging volumes in outpatient radiology.

Science.gov (United States)

Grignon, L; Keiper, M; Vavricek, J; Horsley, W; Murphy, R; Grignon, A; Yu, F

2014-08-01

Over the past several years, decreased demand for and increased supply of imaging services has increased competition among outpatient imaging centers in the United States. This study hypothesizes that using a radiology sales representative and neuroradiologist as a team in marketing and sales will increase imaging referrals in outpatient imaging. From January to December 2009, baseline monthly physician referral data of CT and MR scans of 19 referring clinicians (neurologists, neurosurgeons, and anesthesiologists) to an outpatient radiology group were collected. During that time, a nonphysician radiology sales representative visited the referring clinicians' offices every 2 weeks. From January to June 2010, the same radiology sales representative visited the referring clinicians' offices every 2 weeks but was accompanied by a neuroradiologist once a month. From July 2010 to June 2011, the same radiology sales representative visited the referring clinicians' offices twice a month without a neuroradiologist. Cross-sectional imaging referral volumes were approximately 2.5 times greater during the 6-month period using the neuroradiologist for direct physician-to-physician marketing when compared with the volumes achieved with the sales representative alone, and continued neuroradiologist involvement in marketing and sales is required to maintain referral volumes over time. The impact on imaging referral volumes during the 6-month use of the neuroradiologist for direct physician-to-physician marketing in this study supports the assertion that neuroradiologist visits are an important element in establishing and maintaining a relationship with the referring clinician's office and thereby maximizing imaging referrals. © 2014 by American Journal of Neuroradiology.

National emergency plan for nuclear accidents

International Nuclear Information System (INIS)

1992-10-01

The national emergency plan for nuclear accidents is a plan of action designed to provide a response to accidents involving the release or potential release of radioactive substances into the environment, which could give rise to radiation exposure to the public. The plan outlines the measures which are in place to assess and mitigate the effects of nuclear accidents which might pose a radiological hazard in ireland. It shows how accident management will operate, how technical information and monitoring data will be collected, how public information will be provided and what measures may be taken for the protection of the public in the short and long term. The plan can be integrated with the Department of Defence arrangements for wartime emergencies

Radiological environmental impacts from transportation of nuclear materials

International Nuclear Information System (INIS)

Shuai Zhengqing

1994-01-01

The author describes radiological impacts from transportation of nuclear materials. RADTRAN 4.0 supplied by IAEA was adopted to evaluate radiological consequence of incident-free transportation as well as the radiological risks from vehicular accidents occurring during transportation. The results of calculation show that the collective effective dose equivalent of incident-free transportation to the public and transportation workers is 7.94 x 10 -4 man·Sv. The calculated data suggest that the environmental impacts under normal and assumed accidental conditions are acceptable

Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

Energy Technology Data Exchange (ETDEWEB)

NSTec Aerial Measurement Systems

2012-07-31

The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

Evolution of regulation related to the Chernobyl accident

International Nuclear Information System (INIS)

Anisimova, L.I.; Belyaev, S.T.; Demin, V.F.; Kutkov, V.A.

1997-01-01

The 'classical' pattern of radiological protection considers mostly the radiation factor. The choice of protective measures is governed by effective doses, both received and projected, also established and adopted intervention levels, respectively. The effectiveness of the countermeasures is measured by the value of an averted dose. The lessons learned from Chernobyl show that the above single-factor pattern of radiological protection is appropriate only at an acute post-accident phase. In that period (days and weeks after an accident) the radiation factor prevails and bas countermeasures are proceeded from prearranged intervention levels. At the next long-term phase (months, years after the accident) there is enough time for a human factor to come fully into force. This factor implies the psychological and social acceptance, by the public, of the countermeasures to be implemented. It implies the response of the public to their implementation, the reflection of the situation by mass media, the reaction of Legislative and Administrative Bodies too

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.

Psychological and social impacts of post-accident situations: lessons from the Chernobyl accident

International Nuclear Information System (INIS)

Lochard, J.

1996-01-01

This paper presents the main features, from the psychological and social points of view, of the post-accident situation in the contaminated areas around Chernobyl. This is based on a series of surveys performed in the concerned territories of the CIS republics. The high level of stress affecting a large segment of the population is related to the perception of the situation by those living in a durably contaminated environment but also to the side-effects of some of the countermeasures adopted to mitigate the radiological consequences or to compensate the affected population. The distinction between the accident and the post-accident phase is enlarged to take into account the various phases characterizing the dynamics of the social response. Although the size of the catastrophe as well as the economic and political conditions that were prevailing at the time and after the accident have resulted in a maximal intensity of the reactions of the population, many lessons can be drawn for the management of potential post-accident situations. (author)

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)

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

Management of a radiological emergency. Organization and operation

International Nuclear Information System (INIS)

Dubiau, Ph.

2007-01-01

After a recall of potential radiological emergency situations and their associated risks, this article describes the organization in France of the crisis management and its operation at the national and international scale: 1 - Nuclear or radiological emergency situations and their associated risks: inventory of ionising radiation sources, accidental situations, hazards; 2 - crisis organization in situation of radiological or nuclear emergency: organization at the local scale, organization at the national scale; 3 - management of emergency situations: accident at a facility, action circle, radiological emergency situations outside nuclear facilities, international management of crisis, situations that do not require the implementation of an emergency plan. (J.S.)

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

Standards and criteria of international organizations concerning agricultural aspects of radiological emergency situations

International Nuclear Information System (INIS)

Richards, J.I.; Hance, R.J.; Crick, M.J.

1997-01-01

The nuclear facilities are not generally located in densely populated zones, but usually in rural rather agricultural environment. The Chernobyl accident has shown that farming activities may be affected over hundreds if not thousands kilometers from the accident site. Emergency plans must be implemented in order to trigger countermeasures aiming at reducing agricultural product contamination even in countries having not nuclear facilities or programmes of their own. In Introduction the paper presents the principal objectives to be taken into account by the governmental authorities (at central and local level) after an agricultural countermeasure strategy has been elaborated. The second section deals with the development of criteria and intervening levels. On the basis of the new Recommendations of International Commission on Radiological Protection and the Guidelines concerning the Intervention Levels for Protecting the Public in the Event of a Nuclear Accident or Radiological Emergency issued by an IAEA Consultative Group, IAEA and FAO have published in 1994 common directives concerning the measures to be taken at agricultural level in case of an accidental release of radioactivity. The section 3 presents the concepts and criteria for selecting efficient and appropriate countermeasures. It discusses the importance of planning and intervention preparations, the management of accidents and the proper protection measures. The generic activity levels requiring intervention for withdraw from market of alimentary products are presented in the Section 4. The paper discusses also specific level s of intervention (for milk and meat for instance adopted in Belarus, Ukraine and Russia) as well as future prospects

Development of a computer program for supporting to the radiological adviser in the management of an emergency situation

International Nuclear Information System (INIS)

Loureiro, E.C.M.; Ferreira F, A.L.; Andrade L, F.R. de

2006-01-01

One of the more important aspects of the handling of a radiological emergency it is the capacity for, in an immediate and appropriate way, to take the actions to protect the public members and the personnel that intervenes in the emergency. The evaluation of the radiological accident should keep in mind the whole available pertinent information in any moment and it should be an iterative and dynamic process directed to examine the answer in the measure that more complete and detailed information is available. This work presents a program in Delphi, with the tools, generic procedures and the necessary data to support to the radiological advisory in the initial answer to a radiological accident. It is based on the IAEA document, Generic Procedures for the Evaluation and Answer during a radiological emergency, the IAEA-TECDOC-1162. These procedures offer clear, concise and predetermined action criteria, based on the current knowledge and in the accumulated experiences, allowing the immediate decision making. The philosophy is to maintain the simple and quick, but effective process. The objective is to toast, through a laptop, practical and quick orientation for the answer to emergencies that of being implemented, it will provide an estimation or basic evaluation of the situation and it will guarantee the capacity of necessary answer to protect the public and the workers in the event of different types of radiological emergencies. Besides the recommendations of actions of appropriate protection, also it will toast, when it is necessary, orientations on the recovery of sources and initial operations of cleaning. (Author)

Estimated consequences from severe spent nuclear fuel transportation accidents

International Nuclear Information System (INIS)

Arnish, J.J.; Monette, F.; LePoire, D.; Biwer, B.M.

1996-01-01

The RISKIND software package is used to estimate radiological consequences of severe accident scenarios involving the transportation of spent nuclear fuel. Radiological risks are estimated for both a collective population and a maximally exposed individual based on representative truck and rail cask designs described in the U.S. Nuclear Regulatory Commission (NRC) modal study. The estimate of collective population risk considers all possible environmental pathways, including acute and long-term exposures, and is presented in terms of the 50-y committed effective dose equivalent. Radiological risks to a maximally exposed individual from acute exposure are estimated and presented in terms of the first year and 50-y committed effective dose equivalent. Consequences are estimated for accidents occurring in rural and urban population areas. The modeled pathways include inhalation during initial passing of the radioactive cloud, external exposure from a reduction of the cask shielding, long-term external exposure. from ground deposition, and ingestion from contaminated food (rural only). The major pathways and contributing radionuclides are identified, and the effects of possible mitigative actions are discussed. The cask accident responses and the radionuclide release fractions are modeled as described in the NRC modal study. Estimates of severe accident probabilities are presented for both truck and rail modes of transport. The assumptions made in this study tend to be conservative; however, a set of multiplicative factors are identified that can be applied to estimate more realistic conditions

Thermal-hydraulic uncertainties affecting severe accident progression

International Nuclear Information System (INIS)

Haskin, F.E.; Behr, V.L.

1984-01-01

To provide the proper technical bases for decisions regarding severe accidents, the US Nuclear Regulatory Commission (NRC) is sponsoring the following activities: (a) a variety of severe accident research programs, combined under the Severe Accident Research Plan; (b) nationwide task forces on containment loading, containment response, and fission product source terms; (c) a review by the American Physical Society of state-of-the-art methods for calculating radiological source terms; and (d) technical exchange meetings with the Industry Degraded Core (IDCOR) program. One of the means for integrating this developing array of technical information is the Severe Accident Risk Reduction Program (SARRP). One of the current SARRP objectives is to utilize insights gained from the activities listed above to characterize the relative likelihoods of competing containment failure modes for core-melt accidents

Determining cutoff distances for assessing risks from transportation accident radiation releases

International Nuclear Information System (INIS)

Sandquist, G.M.; Slaughter, D.M.; Kimura, C.Y.; Brumburgh, G.

1995-01-01

The transportation of radioactive materials throughout the United States and the world is a ubiquitous and sometimes controversial activity. Almost universally, these transportation activities have been performed without major incident, and the safety record for transportation of radioactive material is outstanding compared with the transportation of other hazardous materials. Nevertheless, concerns still exist regarding adequate regulation of radioactive material transportation and accurate assessment of the health risks associated with accidents. These concerns are addressed through certification by the cognizant regulatory authority over the transportation container or the performance of a transportation risk assessment. In a transportation risk assessment, accident situations are examined, frequencies are estimated, and consequences resulting from the accident are analyzed and evaluated for acceptance. A universal question with any transportation risk assessment that examines the radiological consequences from release accidents is, At what distance may the dispersion analysis be terminated? This paper examines cutoff distances and their consequences for assessing health risks from radiological transportation releases

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)

Radiological monitoring of food in Cuba

International Nuclear Information System (INIS)

Jerez V, S.F.

1996-01-01

The appearing of the problem for protecting the environment from radioactive contamination is not an accidental matter. The introduction into the earth crust of radioactive material coming from nuclear weapons, accidents, wastes, etc, has caused, as a consequence, the contamination of the biosphere. The extensive trade of food in our country has made necessary the establishment of radiological monitoring in food, which was organized by the Department of Public Health. The structure, functions, characteristics and aspects related to radiological monitoring of food in Cuba are shown in the present paper. The organization and resources for performing the monitoring program, both for normal conditions and for nuclear and/or radiological emergency cases, are detailed. (author). 12 refs., 2 figs

Atmospheric Direct Uptake and Long-term Fate of Radiocesium in Trees after the Fukushima Nuclear Accident

Science.gov (United States)

Mahara, Yasunori; Ohta, Tomoko; Ogawa, Hideki; Kumata, Atsushi

2014-11-01

Large areas of forests were radioactively contaminated by the Fukushima nuclear accident of 2011, and forest decontamination is now an important problem in Japan. However, whether trees absorb radioactive fallout from soil via the roots or directly from the atmosphere through the bark and leaves is unclear. We measured the uptake of radiocesium by trees in forests heavily contaminated by the Fukushima nuclear accident. The radiocesium concentrations in sapwood of two tree species, the deciduous broadleaved konara (Quercus serrata) and the evergreen coniferous sugi (Cryptomeria japonica), were higher than that in heartwood. The concentration profiles showed anomalous directionality in konara and non-directionality in sugi, indicating that most radiocesium in the tree rings was directly absorbed from the atmosphere via bark and leaves rather than via roots. Numerical modelling shows that the maximum 137Cs concentration in the xylem of konara will be achieved 28 years after the accident. Conversely, the values for sugi will monotonously decrease because of the small transfer factor in this species. Overall, xylem 137Cs concentrations will not be affected by root uptake if active root systems occur 10 cm below the soil.

Civil liability for nuclear and radiological damage

International Nuclear Information System (INIS)

Puig, D.

2001-10-01

The present work gives details of the nuclear damage, the accidents of Chernobil, three Mile Inland and Tokaimura with their respective legal consequences, the nature of the responsibility and bases for their establishment, conventions about civil responsibility for nuclear damages to regional and world level as well as other condition of conventions of the Ibero-American countries with regard to the approval of the conventions it has more than enough civil responsibility for nuclear and radiological accident damages

Radiological emergencies the first response

International Nuclear Information System (INIS)

2011-11-01

This national training course about radiological emergencies first answer include: Targets and preparation for emergency response in case of a nuclear or radiological accident. Operations center, action guide for fire fighting, medical coverage, forensic test, first aid, basic instrumentation for radiation, safety equipment, monitoring radiation, gamma rays, personnel exposed protection , radiation exposure rate, injury and illness for radiation, cancer risk, contamination, decontamination and treatment, markers, personnel dosimetry, training, medical and equipment transportation, shielded and tools. Psychological, physical (health and illness), economical (agriculture and industry) and environment impacts. Terrorist attacks, security belts. Support and international agreements (IAEA)

Emergency preparedness and response in case of a fire accident with (UF6) packages tracking Suez Canal

International Nuclear Information System (INIS)

Salama, M.

2004-01-01

Egypt has a unique problem - the Suez Canal. Radioactive cargo passing regularly through the canal carrying new and spent reactor fuel. Moreover there are also about 1000 metric tons of uranium hexaflouride (UF6) passing through the canal every year. In spite of all precautions taken in the transportation, accidents with packages containing (UF 6 ) and shipped through the Suez Canal, accidents may arise even though the probability is minimal. These accidents, may be accompanied by injuries or death of persons and damage to property. Due to the radiation and criticality hazards of (UF 6 ) and its high risk of chemical toxicity. The probability of a fire accident with a cargo carrying (UF 6 ) during its crossing the Suez Canal can cause serious chemical toxic and radiological hazards, particularly if the accident occurred close or near to one of the three densely populated cities (Port-Said, Ismailia, and Suez), which are located along the Suez Canal, west bank. The government of Egypt has elaborated a national radiological emergency plan inorder to face probable radiological accidents, which may be arised inside the country. Arrangements have been also elaborated for the medical care of any persons who, might be injured or contaminated, or who, have been exposed to severe radiation doses. The motivation of the present paper was undertaken to visualize a fire accident scenario occurring in industrial packages containing UF6 on board of a Cargo crossing the Suez Canal near Port-Said City. The accident scenario and emergency response actions taken during the different phases of the accident are going to be presented and discussed. The proposed emergency response actions taken to face the accident are going to be also presented. The work presented had revealed the importance of public awareness will be needed for populations located in densely populated areas along Suez Canal bank inorder to react timely and effectively to avoid the toxic and radiological hazards

Radiological impact to the population of the three major accidents happened in the civil nuclear industry; Impacto radiologico a la poblacion de los tres mayores accidentes ocurridos en la industria nuclear civil

Energy Technology Data Exchange (ETDEWEB)

Ortiz M, J. R., E-mail: Acamb33@hotmail.com [Sociedad Nuclear Mexicana, Mexico D. F. (Mexico)

2013-10-15

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)

Agricultural production as a source of irradiation of populations in radiation accidents

International Nuclear Information System (INIS)

Alexakhin, R.M.

2000-01-01

Radioactive contamination of the agricultural production sphere in case of a radiation accident with radionuclide release is one of the most important sources of additional irradiation for population. As a result, realisation of the measures for mitigating the consequences of the accident in agro-industrial complex assumes the leading role in total system of measures providing radiation safety. The possibility to obtain agricultural production meeting the radiological standards is one of the main indications of effectiveness of liquidation of the accident consequences. First, obtaining of agricultural production meeting the radiological standards provides decreasing of the total radiation dose. The evidence is obtained in the 8-year experience of liquidation of the Chernobyl NPP accident that the 70% decrease of the internal dose for population became possible through a complex of protection measures in agriculture (during the first year after the accident, the contribution of internal dose into the total one amounted to 45%, and that of external irradiation - 52%; for the 70-year period these values are 39% and 60%, respectively). Second, the possibility to obtain 'pure' agricultural production is one of the most important factors of psychological stability for population. Third, obtaining of consumable (as to radionuclide content) agricultural production in private small holdings is one of the guarantees of stability of demographic sector in the accident-affected zone. From the point of view of organization of agricultural production in liquidation of the consequences of accidents with radioactive releases into environment, some periods can be distinguished: (i) the first (early) period takes 10-12 days after the accident. The main measures in the field of agricultural production are in operative assessment of the radiological situation, organization of radiation survey, express classification of agricultural products ready to consumption. If radionuclide content

WWER-1000/320 steam generator collector rupture. Radiological consequences

Energy Technology Data Exchange (ETDEWEB)

Ivanova, A; Sartmadzhiev, A; Balabanov, E [Energoproekt, Sofia (Bulgaria)

1996-12-31

A model describing a hypothetical accident with direct release of primary coolant to the atmosphere is proposed. Cover lifting of the primary collector due to a rupture of the fixing bolts leads to a coolant release. The initial and boundary conditions of the accident scenario have been selected to provide for the most unfavorable conditions. The total release of primary coolant during the first 15 min of transient are estimated to 50.8 tons, of these 48.5 t with the initial activity in the primary coolant circuit. Without evacuation or sheltering, after 7 days of exposure, the expected dose at the boundary of the restricted zone is 0.0182 Sv for the whole body and 0.184 Sv for the thyroid gland. The effective equivalent dose on the site would be 0.0521 Sv. As a result of the analysis it is concluded that the steam generator collector rupture is not jeopardizing the core heat removal even with a minimum configuration of ECCS as the cooling is accomplished through the steam generators. The radiological consequences of the accident would be relatively small if an emergency procedure is applied at the 15-th minute of the transient. 1 ref.

Human factors review for nuclear power plant severe accident sequence analysis

International Nuclear Information System (INIS)

Krois, P.A.; Haas, P.M.

1985-01-01

The paper discusses work conducted to: (1) support the severe accident sequence analysis of a nuclear power plant transient based on an assessment of operator actions, and (2) develop a descriptive model of operator severe accident management. Operator actions during the transient are assessed using qualitative and quantitative methods. A function-oriented accident management model provides a structure for developing technical operator guidance on mitigating core damage preventing radiological release

Aspects of accident management in Cernavoda NPP

International Nuclear Information System (INIS)

Dascalu, N.

1999-01-01

As a general conclusion, the accident management system as implemented at Cerna voda NPP is expected to be appropriate for handling a severe accident, should it occur, in such a way that the environmental radiological consequences would be insignificant and radiation exposure of the personnel be within recommendations. It is recognized, however, that continued development and verification of the system as well as effective personnel training programs are essential to maintain the safety level achieved. (author)

Environmental measurements during the TMI-2 accident

International Nuclear Information System (INIS)

Hull, A.P.

1988-01-01

Although the environmental consequences of the TMI accident were relatively insignificant, it was a major test of the ability of the involved state and federal radiological agencies to make a coordinated environmental monitoring response. This was accomplished largely on an ad hoc basis under the leadership of DOE. With some fine tuning, it is the basis for today's integrated FRMAP monitoring plan, which would be put into operation should another major accident occur at a US nuclear facility

Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.

1993-01-01

This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

Radiological Source Terms for Tank Farms Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

COWLEY, W.L.

2000-06-27

This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

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

Medical intervention in radiological emergencies, formation and training

International Nuclear Information System (INIS)

Cardenas H, J.

2006-01-01

The work exposes the national experience in the development of training programs in medical aspects of the radiological emergencies. Implemented after valuing the existent situation, identified the necessities and the reach of the training, additionally it was elaborated the content of the training program whose purpose is guided to the invigoration of the medical answer capacity in radiological emergencies The content of the modular program it approaches theoretical- practical aspects on preparation and medical answer in radiological emergencies. The program includes an exercise that simulates a radiological accident, to evaluate during the same one, the answer capacity before this situation. The training concludes with the design of a strategy for the preparation and answer in radiological emergencies in correspondence with the potential accidental scenarios that the participants can face. (Author)

Distinguishing human responses to radiological emergencies

International Nuclear Information System (INIS)

Johnson, J.H. Jr.; Ziegler, D.J.

1983-01-01

Inherent in the revised emergency planning regulations recently issued by the federal government is the assumption that people will follow official protective action advisories during a nuclear reactor accident. In this paper the authors argue that this is an unrealistic assumption and present empirical evidence which supports the proposition that a radiological emergency in likely to give rise to a high degree of extreme public behavior. Their analyses indicate that less than one-third of the households on Long Island are likely to follow instructions in the event of an accident at the Shoreham Nuclear Power Station. Among the families who would not follow instructions, some would underreact but most would overreact. Perceived distance from the plant and age of household head appear to be the strongest discriminators among those who are most likely to follow orders, those most likely to underreact, and those most likely to overreact. Implications for radiological emergency preparedness and response planning are discussed. 71 references, 3 figures, 8 tables

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)

Generic procedures for monitoring in a nuclear or radiological emergency

International Nuclear Information System (INIS)

1999-06-01

One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately assess the need for protective actions. Protective action accident management must make use of the key relevant information available. Decision-making and accident assessment will be an iterative and dynamic process aimed at refining the initial evaluation as more detailed and complete information becomes available. Emergency monitoring is one of the main sources for obtaining needed information. This publication is in the scope of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Legal Series No. 14) under which the IAEA is authorized to assist a State Party or a Member State among other matters in developing appropriate radiation monitoring programmes, procedures and standards (Article 5). The scope of this manual is restricted to practical guidance for environmental and source monitoring during a nuclear or other radiological emergency. It does not address emergency response preparedness, nor does it cover the emergency management aspects of accident assessment. This manual is organised into sections relating to measurements in order of priority of a major reactor accident, namely: ambient gamma/beta dose rates from plume, ground deposition or source; radionuclide concentrations in air; deposition maps for 131 I and 137 Cs and other important radionuclides; radionuclide mix in deposition and radionuclide concentrations in food, drinking water and other samples. The introductory section provides an overview of the design of emergency monitoring and sampling programmes, monitoring teams and their qualifications and training, monitoring equipment and instrumentation, protective actions for emergency monitoring teams and quality assurance and quality control checks

Accidents, disasters and crisis: contribution of epidemiology in the nuclear field

International Nuclear Information System (INIS)

Verger, P.; Bard, D.; Hubert, P.

1995-01-01

The experience of the Chernobyl accident has shown the necessity of being prepared for epidemiological assessment of the health consequences of a nuclear or a radiological accident. We discuss the contribution of epidemiology in such situations, in addition to the existing tools designed to assess or manage radiological risks. From a decisional point of view, three issues are distinguished: the protection of the different population groups against ionizing radiations, the achievement of health care and the communication with the public and media. We discuss the input of epidemiological tools in both perspectives. Epidemiology may also contribute to the analysis of health events that may be observed after an accident, i.e. to assess whether these events are not statistical artifacts, whether they are an effect of the exposure to ionizing radiations or a non specific consequence of any accident. Finally, epidemiological studies should be carried out to improve our knowledge on ionizing radiations effects with a special consideration given to the dose-effect relationships. Examples of past nuclear accidents are used to discuss these issues. The last part of this paper is focused on different research issues that should be developed for preparing epidemiological plans for nuclear accidents. (Author). 48 refs., 1 fig., 3 tabs

Accident management strategy in Sweden - implementation and verification

International Nuclear Information System (INIS)

Loewenhielm, Gustaf; Engqvist, Alf; Espefaelt, Ralf

1994-01-01

A comprehensive program for severe accident mitigation was completed in Sweden by the end of 1988. As described in this paper, this program included plant modifications such as the introduction of filtered containment venting, and an accident management system comprising emergency operating strategies and procedures, training and emergency drills. The accident management system at Vattenfall has been further developed since 1988 and some results and experience from this development are reported in this paper. The main aspects covered concern the emergency organization and the supporting tools developed for use by the emergency response teams, the radiological implications such as accessibility to various locations and the long-term aspects of accident management. ((orig.))

REAC/TS Radiation Accident Registry: An Overview

Energy Technology Data Exchange (ETDEWEB)

Doran M. Christensen, DO, REAC/TS Associate Director and Staff Physician Becky Murdock, REAC/TS Registry and Health Physics Technician

2012-12-12

Over the past four years, REAC/TS has presented a number of case reports from its Radiation Accident Registry. Victims of radiological or nuclear incidents must meet certain dose criteria for an incident to be categorized as an “accident” and be included in the registry. Although the greatest numbers of “accidents” in the United States that have been entered into the registry involve radiation devices, the greater percentage of serious accidents have involved sealed sources of one kind or another. But if one looks at the kinds of accident scenarios that have resulted in extreme consequence, i.e., death, the greater share of deaths has occurred in medical settings.

Implementation of a radiological safety management system in a hospital of Mexico City

International Nuclear Information System (INIS)