WorldWideScience

Sample records for accidents involving nuclear

  1. Truck accident involving unirradiated nuclear fuel

    International Nuclear Information System (INIS)

    Carlson, R.W.; Fischer, L.E.

    1992-07-01

    In the early morning of Dec. 16, 1991, a severe accident occurred when a passenger vehicle traveling in the wrong direction collided with a tractor trailer carrying 24 nuclear fuel assemblies in 12 containers on Interstate 1-91 in Springfield, Massachusetts. This paper documents the mechanical circumstances of the accident and the physical environment to which the containers were exposed and the response of the containers and their contents. The accident involved four impacts where the truck was struck by the car, impacted on the center guardrail, impacted on the outer concrete barrier and came to rest against the center guardrail. The impacts were followed by a fire that began in the engine compartment, spread to the.tractor and cab, and eventually spread to the trailer and payload. The fire lasted for about three hours and the packages were involved in the fire for about two hours. As a result of the fire, the tractor-trailer was completely destroyed and the packages were exposed to flames with temperatures between 1300 degrees F and 1800 degrees F. The fuel assemblies remained intact during the accident and there was no release of any radioactive material during the accident. This was a very severe accident; however, the injuries were minor and at no time was the public health and safety at risk

  2. Truck accident involving unirradiated nuclear fuel

    International Nuclear Information System (INIS)

    Carlson, R.W.; Fischer, L.E.

    1993-01-01

    In the early morning of Dec. 16, 1991, a severe accident occurred when a passenger vehicle traveling in the wrong direction collided with a tractor trailer carrying 24 unirradiated nuclear fuel assemblies in 12 containers on Interstate I-91 in Springfield, Massachusetts. This paper documents the mechanical circumstances of the accident and assesses the physical environment to which the containers were exposed and the response of the containers and their contents. The accident involved four impacts where the truck was struck by the car, impacted on the center guardrail, impacted on the outer concrete barrier and came to rest against the center guardrail. The impacts were followed by a fire that began in the engine compartment, spread to the tractor and cab, and eventually spread to the trailer and payload. The fire lasted for about three hours and the packages were involved in the fire for about two hours. As a result of the fire, the tractor-trailer was completely destroyed and the packages were exposed to flames with temperatures between 1,300 F and 1,800 F. The fuel assemblies remained intact during the accident and there was no release of any radioactive material during the accident. This was a very severe accident; however, the injuries were minor and at no time was the public health and safety at risk

  3. Guidance on accidents involving radioactivity

    International Nuclear Information System (INIS)

    1989-01-01

    This annex contains advice to Health Authorities on their response to accidents involving radioactivity. The guidance is in six parts:-(1) planning the response required to nuclear accidents overseas, (2) planning the response required to UK nuclear accidents a) emergency plans for nuclear installations b) nuclear powered satellites, (3) the handling of casualties contaminated with radioactive substances, (4) background information for dealing with queries from the public in the event of an accident, (5) the national arrangements for incident involving radioactivity (NAIR), (6) administrative arrangements. (author)

  4. Concerning the structure of occupational accidents involving construction workers in the erection of nuclear power plants

    International Nuclear Information System (INIS)

    Nowak, B.; Roebenack, K.D.

    1991-01-01

    An investigation of 561 occupational accidents involving construction workers which took place during the construction of nuclear power plants failed to show any significant deviation in comparison with general construction as regards process classification, classification of accidents according to occupation and situation, and accidents severity. Occupational accidents which are typial for nuclear power plant construction are a rare exception. (orig.) [de

  5. Accidents in nuclear ships

    Energy Technology Data Exchange (ETDEWEB)

    Oelgaard, P L [Risoe National Lab., Roskilde (Denmark); [Technical Univ. of Denmark, Lyngby (Denmark)

    1996-12-01

    This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10{sup -3} per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au).

  6. Accidents in nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1996-12-01

    This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10 -3 per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au)

  7. A highway accident involving unirradiated nuclear fuel in Springfield, Massachusetts, on December 16, 1991

    International Nuclear Information System (INIS)

    Carlson, R.W.; Fischer, L.E.

    1992-06-01

    In the early morning of Dec. 16, 1991, a severe accident occurred when a passenger vehicle traveling in the wrong direction collided with a tractor trailer carrying 24 unirradiated nuclear fuel assemblies in 12 containers on Interstate I-91 in Springfield, Massachusetts. The purpose of this report is to document the mechanical circumstances of the severe accident, confirm the nature and quantity of the radioactive materials involved, and assess the physical environment to which the containers were exposed and the response of the containers and their contents. The report consists of five major sections. The first section describes the circumstances and conditions of the accident and the finding of facts. The second describes the containers, the unirradiated nuclear fuel assemblies, and the tie down arrangement used for the trailer. The third describes the damage sustained during the accident to the tractor, trailer, containers, and unirradiated nuclear fuel assemblies. The fourth evaluates the accident environment and its effects on the containers and their contents. The final section gives conclusions derived from the analysis and fact finding investigation. During this severe accident, only minor injuries occurred, and at no time was the public health and safety at risk

  8. Nuclear ship accidents

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-05-01

    In this report available information on 28 nuclear ship accident and incidents is considered. Of these 5 deals with U.S. ships and 23 with USSR ships. The ships are in almost all cases nuclear submarines. Only events that involve the nuclear propulsion plants, radiation exposures, fires/explosions and sea water leaks into the submarines are considered. Comments are made on each of the events, and at the end of the report an attempt is made to point out the weaknesses of the submarine designs which have resulted in the accidents. It is emphasized that much of the available information is of a rather dubious nature. consequently some of the assessments made may not be correct. (au)

  9. 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.

  10. Examination of offsite radiological emergency measures for nuclear reactor accidents involving core melt

    International Nuclear Information System (INIS)

    Aldrich, D.C.; McGrath, P.E.; Rasmussen, N.C.

    1978-06-01

    Evacuation, sheltering followed by population relocation, and iodine prophylaxis are evaluated as offsite public protective measures in response to nuclear reactor accidents involving core-melt. Evaluations were conducted using a modified version of the Reactor Safety Study consequence model. Models representing each measure were developed and are discussed. Potential PWR core-melt radioactive material releases are separated into two categories, ''Melt-through'' and ''Atmospheric,'' based upon the mode of containment failure. Protective measures are examined and compared for each category in terms of projected doses to the whole body and thyroid. Measures for ''Atmospheric'' accidents are also examined in terms of their influence on the occurrence of public health effects

  11. Stakeholder involvement facilitates decision making for UK nuclear accident recovery.

    Science.gov (United States)

    Alexander, C; Burt, R; Nisbet, A F

    2005-01-01

    The importance of major stakeholders participating in the formulation of strategies for maintaining food safety and agricultural production following a nuclear accident has been successfully demonstrated by the UK 'Agriculture and Food Countermeasures Working Group' (AFCWG). The organisation, membership and terms of reference of the group are described. Details are given of the achievements of the AFCWG and its sub-groups, which include agreeing management options that would be included in a recovery handbook for decision-makers in the UK and tackling the disposal of large volumes of contaminated milk, potentially resulting from a nuclear accident.

  12. Immediate medical consequences of nuclear accidents: lessons from Chernobyl

    International Nuclear Information System (INIS)

    Gale, R.P.

    1987-01-01

    The immediate medical response to the nuclear accident at the Chernobyl nuclear power station involved containment of the radioactivity and evacuation of the nearby population. The next step consisted of assessment of the radiation dose received by individuals, based on biological dosimetry, and treatment of those exposed. Medical care involved treatment of skin burns; measures to support bone marrow failure, gastrointestinal tract injury, and other organ damage (i.e., infection prophylaxis and transfusions) for those with lower radiation dose exposure; and bone marrow transplantation for those exposed to a high dose of radiation. At Chernobyl, two victims died immediately and 29 died of radiation or thermal injuries in the next three months. The remaining victims of the accident are currently well. A nuclear accident anywhere is a nuclear accident everywhere. Prevention and cooperation in response to these accidents are essential goals

  13. Nuclear Liability and Insurance Protection for Nuclear Transport Accidents Involving Non-Contracting EU States: An assessment

    International Nuclear Information System (INIS)

    Horbach, N. L. J. T.

    2006-01-01

    This paper provides an analysis of the possible complications and consequences with respect to nuclear liability and insurance protection applicable in respect of transport activities resulting in damage suffered and/or accidents occurring in EU States that are not party to the Paris Convention. It looks at the different legal aspects (jurisdiction, applicable law, liability amounts, reciprocity) should the revised Vienna and Paris Convention become applicable in comparison with the unrevised Conventions. Within Europe, a large number of States are party to the 1960 Paris Convention and the 1963 Brussels Supplementary Convention, providing liability and insurance protection, in general, up to a limit of 300 million SDRs (or even higher). In principle, such protection is confined to nuclear incidents occurring and nuclear damage suffered in the territory of Contracting Parties, including, as recommended, the high seas, unless the legislation of the Installation State determines otherwise (Article 2). The geographical scope of application of the Paris Convention would thus vary according to the law of the Installation State. However, some EU States never became party to the Paris Convention, and are not bound by its the liability principles (notably, channelling of liability), such as Austria, Luxembourg and Ireland. Transport accidents involving these countries might therefore result in liability claims outside the treaty liability regime against operators, suppliers, carriers or persons involved and for types of damages different from those currently covered by the Paris Convention (e.g., environmental damage). It is uncertain to what extent liability insurance of the installation operators would provide adequate protection and whether related damage claims can be enforceable. In addition, a number of newly entered EU States are party to the Vienna Convention, which, although bound by liability principles basically similar to those of the Paris Convention, will

  14. 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

  15. 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

  16. Nuclear accidents

    International Nuclear Information System (INIS)

    1987-01-01

    On 27 May 1986 the Norwegian government appointed an inter-ministerial committee of senior officials to prepare a report on experiences in connection with the Chernobyl accident. The present second part of the committee's report describes proposals for measures to prevent and deal with similar accidents in the future. The committee's evaluations and proposals are grouped into four main sections: Safety and risk at nuclear power plants; the Norwegian contingency organization for dealing with nuclear accidents; compensation issues; and international cooperation

  17. Nuclear. Convention on early notification of a nuclear accident. Treaty series 1990 no.21

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-31

    The States present at this convention are aware that comprehensive measures have been are being taken to ensure a high level of safety in nuclear activities, aimed at preventing nuclear accidents and minimizing the consequences of any such accident should it occur. The States are convinced of the need to provide relevant information about nuclear accidents as early as possible in order that transboundary radiological consequences can be minimized. In the event of an accident the State involved will notify, through the International Energy Agency the other States which may be physically affected, as to the nature of the accident, the time of occurrence and its exact location.

  18. Nuclear. Convention on early notification of a nuclear accident. Treaty series 1990 no.21

    International Nuclear Information System (INIS)

    1991-01-01

    The States present at this convention are aware that comprehensive measures have been are being taken to ensure a high level of safety in nuclear activities, aimed at preventing nuclear accidents and minimizing the consequences of any such accident should it occur. The States are convinced of the need to provide relevant information about nuclear accidents as early as possible in order that transboundary radiological consequences can be minimized. In the event of an accident the State involved will notify, through the International Energy Agency the other States which may be physically affected, as to the nature of the accident, the time of occurrence and its exact location

  19. Big nuclear accidents

    International Nuclear Information System (INIS)

    Marshall, W.; Billingon, D.E.; Cameron, R.F.; Curl, S.J.

    1983-09-01

    Much of the debate on the safety of nuclear power focuses on the large number of fatalities that could, in theory, be caused by extremely unlikely but just imaginable reactor accidents. This, along with the nuclear industry's inappropriate use of vocabulary during public debate, has given the general public a distorted impression of the risks of nuclear power. The paper reviews the way in which the probability and consequences of big nuclear accidents have been presented in the past and makes recommendations for the future, including the presentation of the long-term consequences of such accidents in terms of 'loss of life expectancy', 'increased chance of fatal cancer' and 'equivalent pattern of compulsory cigarette smoking'. The paper presents mathematical arguments, which show the derivation and validity of the proposed methods of presenting the consequences of imaginable big nuclear accidents. (author)

  20. The victim of the nuclear accident

    International Nuclear Information System (INIS)

    Carvalho, A.B. de.

    1990-01-01

    This paper shows the effects of the nuclear accident in the victims, in their lives, changes in the behaviour, neurosis including all the psychological aspects. The author compare the victims with nuclear accident like AIDS patients, in terms of people's discrimination. There is another kind of victims. They are the people who gave helpness, for example physicians, firemen and everybody involved with the first aids that suffer together with the victims trying to safe them and to diminish their suffering, combating the danger, the discrimination and the no information. (L.M.J.)

  1. Nuclear accident evacuee bullying and structural violence

    International Nuclear Information System (INIS)

    Tsujiuchi, Takuya

    2018-01-01

    Nuclear accident sufferers should be now referred to as nuclear accident victims. The authors discuss why nuclear accident victims receive not only psychological bullying where no peculiar causes exist, but also corporal and physical bullying and mental suffering, based on the results of questionnaire survey conducted by the authors from January to February 2017, the 'survey on bullying problems related to evacuation from the nuclear accident.' The reasons why the nuclear power evacuation bullying has become a problem at present can be largely classified to the following three categories: (1) opinion that 'bullying' that originally existed just after the nuclear accident became surfaced recently, (2) opinion that latent problems exist as background, and (3) opinion that socially underlying issues are involved in the generation of bullying. Thus, various factors existing under nuclear power evacuation bullying were structurally clarified. In the background of children's nuclear evacuation bullying, adult nuclear power evacuation bullying exists, and there are 'lack of understanding, prejudice, and discrimination against nuclear power and Fukushima' under that. The author thought that 'structural violence' to create the disparity, discrimination, inequality, and injustice of society exists as the basis of such lack of understanding, prejudice, and discrimination, and discussed the 'structural violence' as the basis of bullying. As the upper structure of structural violence associated with nuclear accidents, there are two big phenomena: (1) setting of evacuation/return area not based on reasonable radiation dose standards and (2) fabricated safety and carefreeness myth. The Ministry of Education, Culture, Sports, Science and Technology's report on nuclear bullying could give an impression that 'nuclear power evacuation bullying' is 'not so big problem'. (A.O.)

  2. Big nuclear accidents

    International Nuclear Information System (INIS)

    Marshall, W.

    1983-01-01

    Much of the debate on the safety of nuclear power focuses on the large number of fatalities that could, in theory, be caused by extremely unlikely but imaginable reactor accidents. This, along with the nuclear industry's inappropriate use of vocabulary during public debate, has given the general public a distorted impression of the safety of nuclear power. The way in which the probability and consequences of big nuclear accidents have been presented in the past is reviewed and recommendations for the future are made including the presentation of the long-term consequences of such accidents in terms of 'reduction in life expectancy', 'increased chance of fatal cancer' and the equivalent pattern of compulsory cigarette smoking. (author)

  3. Nuclear accidents and epidemiology

    International Nuclear Information System (INIS)

    1987-01-01

    A consultation on epidemiology related to the Chernobyl accident was held in Copenhagen in May 1987 as a basis for concerted action. This was followed by a joint IAEA/WHO workshop in Vienna, which reviewed appropriate methodologies for possible long-term effects of radiation following nuclear accidents. The reports of these two meetings are included in this volume, and cover the subjects: 1) Epidemiology related to the Chernobyl nuclear accident. 2) Appropriate methodologies for studying possible long-term effects of radiation on individuals exposed in a nuclear accident. Figs and tabs

  4. Organization of public authorities in France for the event of an incident or accident involving nuclear safety: Simulation of a nuclear crisis

    International Nuclear Information System (INIS)

    Cartigny, J.; Majorel, Y.

    1986-01-01

    The French nuclear safety regulations lay down the action to be taken in the event of an incident or accident involving the types of radiological hazard that could arise in a nuclear installation or during the transport of radioactive material. The organization established for this purpose is designed to ensure that the technical measures taken by the authorities responsible for nuclear safety, radiation protection, public order and public safety are fully effective. The Interministerial Nuclear Safety Committee (Comite interministeriel de la securite nucleaire), which reports to the Prime Minister, co-ordinates the measures taken by the public authorities. The public authorities and the operators together organize exercises designed to verify the whole complex of measures foreseen in the event of an incident or accident. These exercises, which have been carried out in a systematic manner in France for some years, are based on scenarios which are as realistic as possible and enable the following objectives to be achieved: (1) analysis of the crisis apparatus (ORSECRAD plans, individual intervention plans, information conventions); (2) uncovering gaps or inadequacies; (3) arrangements for interchange of information between the various participants whose responsibilities involve them in the emergency; and (4) allowance for the information requirements of the media and the population. The information drawn from these exercises enables the various procedures to be improved step by step. (author)

  5. Colloquium / Preparation for nuclear post-accident. Citizens and local authorities involvement in major risks governance - proceedings

    International Nuclear Information System (INIS)

    Pascal, Michel; Villers, Anita; Sene, Monique; Godin, Francois; Quilichini, Jean-Michel; Rollinger, Francois; Delalonde, Jean-Claude; Mehl-Auget, Isabelle; Autret, Jean-Claude; Heriard Dubreuil, Gilles; Petitfrere, Michael; Lochard, Jacques; Demet, Michel; Boucherie, Jean-Claude; Calafat, Alexis; Sommade, Christian; Villain, Alain; Ragazzo, Romeo; Rengot, Marielle; Sename, Jean; Thellier, Yvette; Tremelet, David; Olszewski, Richard; Fournier, Nicolas

    2009-12-01

    During 40 years, France has chosen nuclear energy as main energy source for power generation. Today, nuclear energy covers 80% of the French electricity needs. For this reason, in France, each inhabitant lives at less than 200 km of a nuclear power plant. The September 11, 2001 terror attack has led to reconsider the nuclear risk in terms of security. In 2005, the French nuclear safety authority (ASN) has been entrusted with the preparation of a nuclear post-accident management study. This study has been mainly based on the experience feedback of the Chernobyl accident and on the dialogue with different actors of the French territory: the local authorities, the habitants, the associations and the health, environment and education actors. This colloquium represents the opening act of the joint elaboration of the management of a potential nuclear accident at the region scale. The colloquium was organized around 5 round tables: 1 - Did the nuclear safety transparency law change the situation?; 2 - Examples of pluralistic dialogues: the long-term management of a nuclear accident; 3 - How to encourage the necessary skills development of citizens? 4 - Regional development strategies in terms of nuclear risks management (incidents, effluents, wastes, transports..); 5 - New territory liabilities and citizens' legitimate aspiration in terms of health/environment: building something together. This document is the proceedings of this colloquium. It reports the exchanges between the participants

  6. Report by the 'Fukushima Dai-Ichi major accident' nuclear subgroup

    International Nuclear Information System (INIS)

    Brezin, Edouard; Balibar, Sebastien; Candel, Sebastien; Cesarsky, Catherine; Dautray, Robert; Gratias, Denis; Guillaumont, Robert; Laval, Guy; Quere, Yves; Tissot, Bernard; Zaoui, Andre; Brechet, Yves; Carpentier, Alain; Duplessy, Jean-Claude; Jerome, Denis; Bamberger, Yves; Barre, Bertrand; Comets, Marie-Pierre; Jamet, Philippe; Schwarz, Michel; Baumont, David; Guilhem, Gilbert; Repussard, Jacques; Billot, Philippe; Boullis, Bernard; Gauche, Francois; Zaetta, Alan; Pouget-Abadie, Xavier

    2011-06-01

    This report comprises a description of the succession of events in the Fukushima-Dai-Ichi power plant, a discussion of the situation of the nuclear industry and energy in France after this accident (French nuclear stock, security organisation), and a discussion on the fuel cycle and on future opportunities (comparison with EPR - Gen II safety measures, perspectives beyond the EPR). Numerous appendices are proposed, made of documents from different bodies involved in nuclear industry, energy and safety. They deal with the Fukushima accident, with light water and pressurized water reactors, with severe accidents in PWRs, and so on

  7. Six Decades of Nuclear Accidents, Nuclear Compensation, and Issues of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Boonsuwan, P.; Songjakkeaw, A.

    2011-11-01

    Thailand has made a serious aim to employ nuclear power by adopting five 1,000 MWt in the 2010 national Power Development Plan (PDP 2010) with the first NPP coming online in 2020. However, after the Fukushima nuclear disaster in March 2011, the National Energy Policy Committee had made the resolution to postpone the plan by 3 years. The post-Fukushima atmosphere does not bode well for the public sentiment towards the proposed programme, especially with regards to safety of an NPP. Nonetheless, during the six decades that NPPs have been in operation in 32 countries worldwide, there are only 19 serious accidents involving fatalities and/or damage to properties in excess of 100 million USD. Out of the three significant accidents - Fukushima nuclear accident (2011), Chernobyl nuclear accident (1986), and Three Miles Island nuclear accident (1979) - only the accident at Three Miles Island occurs during normal operation. Such can be implied that the operation of NPPs does maintain a high level of safety. The current technology on nuclear safety has been advancing greatly to the point that the new NPP design claims to render the possibility of a severe accident resulting in core melting insignificant. Along with the technical improvements, laws and regulations have also be progressing in parallel to adequately compensate and limit the liability of operators in case of a nuclear accident. The international agreements such as the Vienna Convention on Civil Liability for Nuclear Damage and the Convention of the Third Party Liability in the Field of Nuclear Energy had also been established and also the national laws of countries such as the United States and Japan have been implemented to address such issues to the point that victims of a nuclear accidents are adequately and justly compensated. In addition to the issues of nuclear accident, the dilemma in nuclear waste management, especially with regards to the High Level Waste which is highly radioactive while having very

  8. Nuclear accident dosimetry

    International Nuclear Information System (INIS)

    1982-01-01

    The film presents statistical data on criticality accidents. It outlines past IAEA activities on criticality accident dosimetry and the technical documents that resulted from this work. The film furthermore illustrates an international comparison study on nuclear accident dosimetry conducted at the Atomic Energy Research Establishment, Harwell, United Kingdom

  9. Nuclear accident dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-12-31

    The film presents statistical data on criticality accidents. It outlines past IAEA activities on criticality accident dosimetry and the technical documents that resulted from this work. The film furthermore illustrates an international comparison study on nuclear accident dosimetry conducted at the Atomic Energy Research Establishment, Harwell, United Kingdom

  10. Nuclear Accidents: Consequences for Human, Society and Energy Sector

    Directory of Open Access Journals (Sweden)

    L. A. Bolshov

    2016-01-01

    Full Text Available The article examines radiation and hygienic regulations with regard to the elimination of consequences of the Chernobyl NPP accident in the context of relationships with other aspects, primarily socio-economic and political factors. This experience is reasonable to take into account when defining criteria in other regulatory fields, for example, in radioactive waste classification and remediation of areas. The article presents an analysis of joint features and peculiarities of nuclear accidents in the industry and energy sectors. It is noted that the scale of global consequences of the Chernobyl NPP accident is defined by the large-scale release of radioactivity into the environment, as well as an affiliation of the nuclear installation with the energy sector. Large-scale radiation accidents affect the most diverse spheres of human activities, what, in its turn, evokes the reverse reaction from the society and its institutions, including involvement of political means of settlement. If the latter is seeing for criteria that are scientifically justified and feasible, then the preconditions for minimizing socio-economic impacts are created. In other cases, political decisions, such as nuclear units’ shutdown and phasing out of nuclear energy, appear to be an economic price which society, as a whole and a single industry sector, pay to compensate the negative public response. The article describes fundamental changes in approaches to ensure nuclear and radiation safety that occurred after the Chernobyl NPP accident. Multiple and negative consequences of the Chernobyl accident for human and society are balanced to some extent by a higher level of operational safety, emergency preparedness, and life-cycle safety. The article indicates that harmonization and ensuring consistency of regulations that involve different aspects of nuclear and radiation safety are important to implement practical solutions to the nuclear legacy problems. The

  11. The application of the assessment of nuclear accident status in emergency decision-making during nuclear accident

    International Nuclear Information System (INIS)

    Yang Ling

    2011-01-01

    Nuclear accident assessment is one of the bases for emergency decision-making in the situation of nuclear accident in NPP. Usually, the assessment includes accident status and consequence assessment. It is accident status assessment, and its application in emergency decision-making is introduced here. (author)

  12. Proposal strategy and policy on nuclear safety for no-more severe accidents

    International Nuclear Information System (INIS)

    2013-01-01

    Following the outspoken advice saying 'scientists and engineers concerning with nuclear power promotion and safety should be responsible for clarifying how preventable or what measures should be needed to prevent severe accidents occurring at Fukushima Daiichi nuclear power plants (NPPs)', committee on prevention of severe accidents at NPPs was established by relevant nuclear scientists and engineers involved so as to discuss basic issues to be solved from scientific and technical viewpoints. Based on the review of 'defense in depth' concept and accident analysis at Fukushima nuclear accident, four major proposals and six supplements to be established were identified such as: (1) finding mechanism of beyond imagination events for natural disaster, terrorism, and internal events, (2) reform of comprehensive safety standards and guidelines with performance basis easy to reflect latest knowledge and technology as 'back-fitting', (3) severe accidents measures, their validation, and drilling on accident management to advance procedures and develop human resources, and (4) risk communications and public disclosure of information. This article described backgrounds of committee's proposals on nuclear safety for no-more severe accidents. (T. Tanaka)

  13. Managing Nuclear Reactor Accidents: Issues Raised by Three Mile Island

    OpenAIRE

    Hamilton, G.W.

    1980-01-01

    This paper provides a descriptive account of significant events in the accident at the Three Mile Island nuclear power plant in March, 1979. It is based upon documents collected as background materials for the IIASA workshop: Procedural and Organizational Measures for Accident Management: Nuclear Reactors. In addition to the references listed, information was supplied by John Lathrop, who conducted interviews with government and industry officials involved in the crisis. There have been ...

  14. Nuclear accidents and safety measures of domestic nuclear power plants

    International Nuclear Information System (INIS)

    Song Zurong; Che Shuwei; Pan Xiang

    2012-01-01

    Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

  15. International aspects of nuclear accidents

    International Nuclear Information System (INIS)

    Uematsu, K.

    1989-09-01

    The accident at Chernobyl revealed that there were shortcomings and gaps in the existing international mechanisms and brought home to governments the need for stronger measures to provide better protection against the risks of severe accidents. The main thrust of international co-operation with regard to nuclear safety issues is aimed at achieving a uniformly high level of safety in nuclear power plants through continuous exchanges of research findings and feedback from reactor operating experience. The second type of problem posed in the event of an accident resulting in radioactive contamination of several countries relates to the obligation to notify details of the circumstances and nature of the accident speedily so that the countries affected can take appropriate protective measures and, if necessary, organize mutual assistance. Giving the public accurate information is also an important aspect of managing an emergency situation arising from a severe accident. Finally, the confusion resulting from the unwarranted variety of protective measures implemented after the Chernobyl accident has highlighted the need for international harmonization of the principles and scientific criteria applicable to the protection of the public in the event of an accident and for a more consistent approach to emergency plans. The international conventions on third party liability in the nuclear energy sector (Paris/Brussels Conventions and the Vienna Convention) provide for compensation for damage caused by nuclear accidents in accordance with the rules and jurisdiction that they lay down. These provisions impose obligations on the operator responsible for an accident, and the State where the nuclear facility is located, towards the victims of damage caused in another country

  16. 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

  17. Cleanup of large areas contaminated as a result of a nuclear accident

    International Nuclear Information System (INIS)

    1989-01-01

    The purposes of the report are to provide an overview of the methodology and technology available to clean up contaminated areas and to give preliminary guidance on matters related to the planning, implementation and management of such cleanups. This report provides an integrated overview of important aspects related to the cleanup of very large areas contaminated as a result of a serious nuclear accident, including information on methods and equipment available to: characterize the affected area and the radioactive fallout; stabilize or isolate the contamination; and clean up contaminated urban, rural and forested areas. The report also includes brief sections on planning and management considerations and the transport and disposal of the large volumes of wastes arising from such cleanups. For the purposes of this report, nuclear accidents which could result in the deposition of decontamination over large areas if the outer containment fails badly include: 1) An accident with a nuclear weapon involving detonation of the chemical high explosive but little, if any, nuclear fission. 2) A major loss of medium/high level liquid waste (HLLW) due to an explosion/fire at a storage site for such waste. 3) An accident at a nuclear power plant (NPP), for example a loss of coolant accident, which results in some core disruption and fuel melting. 4) An accident at an NPP involving an uncontrolled reactivity excursion resulting in the violent ejection of a reactor core material and rupture of the containment building. 117 refs, 32 figs, 12 tabs

  18. 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

  19. A review on liability in case of nuclear accident

    International Nuclear Information System (INIS)

    Gallage-Alwis, Sylvie; Faron, Pauline

    2013-01-01

    After having evoked assessments of the cost of a nuclear accident in France and of that of damages caused by the Fukushima accident, the authors propose an overview of the issue of liability of companies involved in the operation of a nuclear power plant. They outline that this regime is mainly governed by two international conventions: the Paris Convention on third party liability in the field of nuclear energy, and the Brussels Convention. The first one bears on the liability of nuclear installation operators, while the second one aims at ensuring an additional compensation of casualties on public funds. They also evoke the Vienna Convention which aims at defining a world regime for nuclear liability. They outline the limited scope of application of the Paris Convention, and the limitation of compensations. They discuss the liability of companies others than those operating nuclear installations

  20. 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

  1. Statistical evaluation of design-error related nuclear reactor accidents

    International Nuclear Information System (INIS)

    Ott, K.O.; Marchaterre, J.F.

    1981-01-01

    In this paper, general methodology for the statistical evaluation of design-error related accidents is proposed that can be applied to a variety of systems that evolves during the development of large-scale technologies. The evaluation aims at an estimate of the combined ''residual'' frequency of yet unknown types of accidents ''lurking'' in a certain technological system. A special categorization in incidents and accidents is introduced to define the events that should be jointly analyzed. The resulting formalism is applied to the development of U.S. nuclear power reactor technology, considering serious accidents (category 2 events) that involved, in the accident progression, a particular design inadequacy. 9 refs

  2. Severe accident management: radiation dose control, Fukushima Daiichi and TMI-2 nuclear plant accidents

    International Nuclear Information System (INIS)

    Shaw, Roger

    2014-01-01

    This presentation presents valuable dose information related to the Fukushima Daiichi and Three Mile Island Unit 2 (TMI-2) Nuclear Plant accidents. Dose information is provided for what is well known for TMI-2, and what is available for Fukushima Daiichi. Particular emphasis is placed on the difference between the type of reactors involved, overarching plant damage issues, and radiation worker dose outcomes. For TMI-2, more in depth dose data is available for the accident and the subsequent recovery efforts. The comparisons demonstrate the need to understand the wide variation in potential dose management measures and outcomes for severe reactor accidents. (author)

  3. 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

  4. Dutch National Plan combat nuclear accidents

    International Nuclear Information System (INIS)

    1988-01-01

    This document presents the Dutch National Plan combat nuclear accidents (NPK). Ch. 2 discusses some important starting points which are determining for the framework and the performance of the NPK, in particular the accident typology which underlies the plan. Also the new accident-classification system for the Dutch nuclear power plants, the standardization for the measures to be taken and the staging around nuclear power plants are pursued. In ch. 3 the legal framework of the combat nuclear accidents is described. In particular the Nuclear-power law, the Accident law and the Municipality law are pursued. Also the role of province and municipality are described. Ch. 4 deals with the role of the owner/licensee of the object where the accident occurs, in the combat of accident. In ch. 5 the structure of the nuclear-accident combat at national level is outlined, subdivided in alarm phase, combat phase and the winding-up phase. In ch.'s 6-12 these phases are elaborated more in detail. In ch.'s 10-13 the measures to be taken in nuclear accidents, are described. These measures are distinguished with regard to: protection of the population and medical aspects, water economy, drinking-water supply, agriculture and food supply. Ch. 14 describes the responsibility of the burgomaster. Ch.'s 15 and 16 present an overview of the personnel, material, procedural and juridical modifications and supplements of existing structures which are necessary with regard to the new and modified parts of the structure. Ch. 17 indicates how by means of the appropriate education and exercise it can be achieved that all personnel, services and institutes concerned possess the knowledge and experience necessary for the activities from the NKP to be executed as has been described. Ch. 18 contains a survey of activities to be performed and a proposal how these can be realized. (H.W.). figs.; tabs

  5. Criticality accident of nuclear fuel facility. Think back on JCO criticality accident

    International Nuclear Information System (INIS)

    Naito, Keiji

    2003-09-01

    This book is written in order to understand the fundamental knowledge of criticality safety or criticality accident of nuclear fuel facility by the citizens. It consists of four chapters such as critical conditions and criticality accident of nuclear facility, risk of criticality accident, prevention of criticality accident and a measure at an occurrence of criticality accident. A definition of criticality, control of critical conditions, an aspect of accident, a rate of incident, damage, three sufferers, safety control method of criticality, engineering and administrative control, safety design of criticality, investigation of failure of safety control of JCO criticality accident, safety culture are explained. JCO criticality accident was caused with intention of disregarding regulation. It is important that we recognize the correct risk of criticality accident of nuclear fuel facility and prevent disasters. On the basis of them, we should establish safety culture. (S.Y.)

  6. 10 CFR 835.1304 - Nuclear accident dosimetry.

    Science.gov (United States)

    2010-01-01

    ...) Methods and equipment for analysis of biological materials; (3) A system of fixed nuclear accident... Nuclear accident dosimetry. (a) Installations possessing sufficient quantities of fissile material to... 10 Energy 4 2010-01-01 2010-01-01 false Nuclear accident dosimetry. 835.1304 Section 835.1304...

  7. Research investigation report on Fukushima Daiichi nuclear accident

    International Nuclear Information System (INIS)

    2012-03-01

    This report was issued in February 2012 by Rebuild Japan Initiative Foundation's Independent Investigation Commission on the Fukushima Daiichi Nuclear Accident, which consisted of six members from the private sector in independent positions and with no direct interest in the business of promoting nuclear power. Commission aimed to determine the truth behind the accident by clarifying the various problems and reveal systematic problems behind these issues so as to create a new starting point by identifying clear lessons learned. Report composed of four chapters; (1) progression of Fukushima accident and resulting damage (accident management after Fukushima accident, and effects and countermeasure of radioactive materials discharged into the environment), (2) response against Fukushima accident (emergency response of cabinet office against nuclear disaster, risk communication and on-site response against nuclear disaster), (3) analysis of historical and structural factors (technical philosophy of nuclear safety, problems of nuclear safety regulation of Fukushima accident, safety regulatory governance and social background of 'Safety Myth'), (4) Global Context (implication in nuclear security, Japan in nuclear safety regime, U.S.-Japan relations for response against Fukushima accident, lessons learned from Fukushima accident - aiming at creation of resilience). Report could identify causes of Fukushima accident and factors related to resulting damages, show the realities behind failure to prevent the spread of damage, and analyze the overall structural and historical background behind the accidents. (T. Tanaka)

  8. The cost of nuclear accidents

    International Nuclear Information System (INIS)

    2015-01-01

    Proposed by a technical section of the SFEN, and based on a meeting with representatives of different organisations (OECD-NEA, IRSN, EDF, and European Nuclear Energy Forum), this publication addresses the economic consequences of a severe accident (level 6 or 7) within an electricity producing nuclear power plant. Such an assessment essentially relies on three pillars: release of radio-elements outside the reactor, the scenario of induced consequences, and the method of economic quantification. After a recall and a comment of safety arrangements, and of the generally admitted probability of such an accident, this document notices that several actors are concerned by nuclear energy and are trying to assess accident costs. The issue of how to assess a cost (or costs) of a nuclear accident is discussed: there are in fact several types of costs and consequences. Thus, some costs can be rather precisely quantified when some others can be difficult to assess or with uncertainty. The relevance of some cost categories appears to be a matter of discussion and one must not forget that consequences can occur on a long term. The need for methodological advances is outlined and three categories of technical objectives are identified for the assessment (efficiency of safety measures to be put forward to mitigate the risk via a better accident management, compensation of victims and nuclear civil responsibility, and comparison of electricity production sectors and assessment of externalisation to guide public choices). It is outlined that the impact of accidents depend on several factors, that the most efficient mean to limit consequences of accidents is of course to limit radioactive emissions

  9. Indemnification of Damage in the Event of a Nuclear Accident

    International Nuclear Information System (INIS)

    2006-01-01

    The Second International Workshop on the Indemnification of Nuclear Damage was held in Bratislava, Slovak Republic, from 18 to 20 May 2005. The workshop was co-organised by the OECD Nuclear Energy Agency and the Nuclear Regulatory Authority of the Slovak Republic. It attracted wide participation from national nuclear authorities, regulators, operators of nuclear installations, nuclear insurers and international organisations. The purpose of the workshop was to assess the third party liability and compensation mechanisms that would be implemented by participating countries in the event of a nuclear accident taking place within or near their borders. To accommodate this objective, two fictitious accident scenarios were developed: one involving a fire in a nuclear installation located in the Slovak Republic and resulting in the release of significant amounts of radioactive materials off-site, and the other a fire on board a ship transporting enriched uranium hexafluoride along the Danube River. The first scenario was designed to involve the greatest possible number of countries, with the second being restricted to countries with a geographical proximity to the Danube. These proceedings contain the papers presented at the workshop, as well as reports on the discussion sessions held. (author)

  10. 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)

  11. The ultimate nuclear accident

    International Nuclear Information System (INIS)

    Abdus Salam, A.

    1988-01-01

    The estimated energy equivalent of Chernobyl explosion was the 1/150 th of the explosive energy equivalent of atomic bomb dropped on Hiroshima; while the devastation that could be caused by the world's stock pile of nuclear weapons, could be equivalent to 160 millions of Chernobyl-like incidents. As known, the number of nuclear weapons is over 50,000 and 2000 nuclear weapons are sufficient to destroy the world. The Three Mile Island and Chernobyl accidents have been blamed on human factors but also the human element, particularly in the form of psychological stresses on those operating the nuclear weapons, could accidentally bring the world to a nuclear catastrophe. This opinion is encouraged by the London's Sunday Times magazine which gave a graphic description of life inside a nuclear submarine. So, to speak of nuclear reactor accidents and not of nuclear weapons is false security. (author)

  12. 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)

  13. Legal aspects of nuclear and radiological accidents

    International Nuclear Information System (INIS)

    El-baroudy, M.M.

    2005-01-01

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

  14. Links between operating experience feedback of industrial accidents and nuclear safety

    International Nuclear Information System (INIS)

    Eury, S.P.

    2012-01-01

    Since 1992, the bureau for analysis of industrial risks and pollutions (BARPI) collects, analyzes and publishes information on industrial accidents. The ARIA database lists over 40.000 accidents or incidents, most of which occurred in French classified facilities (ICPE). Events occurring in nuclear facilities are rarely reported in ARIA because they are reported in other databases. This paper describes the process of selection, characterization and review of these accidents, as well as the following consultation with industry trade groups. It is essential to publicize widely the lessons learned from analyzing industrial accidents. To this end, a web site (www.aria.developpement-durable.gouv.fr) gives free access to the accidents summaries, detailed sheets, studies, etc. to professionals and the general public. In addition, the accidents descriptions and characteristics serve as inputs to new regulation projects or risk analyses. Finally, the question of the links between operating experience feedback of industrial accidents and nuclear safety is explored: if the rigorous and well-documented methods of experience feedback in the nuclear field certainly set an example for other activities, nuclear safety can also benefit from inputs coming from the vast diversity of accidents arisen into industrial facilities because of common grounds. Among these common grounds we can find: -) the fuel cycle facilities use many chemicals and chemical processes that are also used by chemical industries; -) the problems resulting from the ageing of equipment affect both heavy and nuclear industries; -) the risk of hydrogen explosion; -) the risk of ammonia, ammonia is a gas used by nuclear power plants as an ingredient in the onsite production of mono-chloramine and ammonia is involved in numerous accidents in the industry: at least 900 entries can be found in the ARIA database. The paper is followed by the slides of the presentation

  15. 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

  16. Character and consequence of nuclear criticality accident

    International Nuclear Information System (INIS)

    Liu Xinhua; Liu Hua; Wu Deqiang; Li Bing

    2001-01-01

    The author describes some concepts, the process and magnitude of energy release and the destruction of the nuclear criticality accident and also describes the radiation consequence of criticality accidents from three aspects: prompt radiation, contamination in working place and release of fission products to the environment. It shows that the effects of radioactivity release from criticality accidents in the nuclear fuel processing plants on the environment and the public is minor, the main danger is from the external exposure of prompt rays. The paper make as have a correct understanding of the nuclear criticality accident and it would be helpful to take appropriate emergency response to potential criticality accident

  17. United Kingdom procedures in case of nuclear accidents

    International Nuclear Information System (INIS)

    Chalfont, L.

    1988-01-01

    From the United Kingdom experience, general principles for establishing emergency plans are drawn. Every country with nuclear plant should have such emergency arrangements capable of dealing with the largest scale that can be envisaged as a practical possibility. While the effects of accidents cannot be anticipated in detail these plans should form a good flexible basis for providing the resources, communications and procedures that are likely to be needed. They encompass the administrative infrastructure of the area surrounding the nuclear installation and involve co-ordination with the police, fire services and ambulance services, the local and county authorities, the authorities responsible for food, agriculture, fisheries and water, and the health authorities including hospitals and medical services. Special training and procedures have to be established for the personnel that are involved and exercises graduating from the exercising of special procedures to large scale simulated accidents need to be carried out periodically. Good communication systems have to be established between the nuclear installations, the operational support centres or equivalent, the field and headquarters units of the relevant organizations, and the central government departments so that whatever additional resources and support are needed can be marshalled quickly and efficiently. (author)

  18. Road accidents involving bicycles: configurations and injuries.

    Science.gov (United States)

    Orsi, Chiara; Montomoli, Cristina; Otte, Dietmar; Morandi, Anna

    2017-12-01

    This study analyzed the most common types of accident involving bicycles and compared the frequency of injuries. The data source was the database of German In-Depth Accident Study (GIDAS). Cases consist of bicycles and their riders involved in accidents between 2000 and 2010. In most collisions, the bicycle impacted with a car. The percentage of injured bicyclists was higher in collisions with a heavy vehicle and decreased when the bicycle impacted with lighter vehicles. A high percentage of injured bicyclists in single accidents was observed; the most severe injury was more frequently to head and extremities. Accidents involving a car and a bicycle with the right of way in a bicycle path represented about 20% of involved and injured bicyclists. The ten most frequent configurations represented about 60% of involved and injured bicyclists. These results contribute to understand the dangerous scenarios for bicyclists and to suggest preventive actions.

  19. 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

  20. The OECD/NEA workshop on the indemnification of nuclear damage in the event of a nuclear accident

    International Nuclear Information System (INIS)

    Wagstaff, F.

    2002-01-01

    Since 1993, the OECD Nuclear Energy Agency (OECD/NEA) has run the International Nuclear Emergency Exercise (INEX) Program. The program serves to discuss an effective accident management approach on the basis of a simulated nuclear accident situation together with the states involved and their institutions, and also elaborate measures for its further improvement. At the present time, the INEX Program has reached Phase 3 in which, for the first time, also aspects of liability for the consequences of accidents were included. These aspects were made the subject of a workshop held after an emergency exercise. The scenario covered was based on an INES level-4 accident in the French Gravelines Nuclear Power Station situated close to the French-Belgian border. The workshop dealt with these topics, among others: the application of the Paris Convention on Third Party Liability, the Brussels Supplementary Convention, and the Vienna Convention on Civil Liability for Nuclear Damage as well as the Supplementary Compensation Convention of 1997. It was seen that there was a clear need for further discussion, especially to shed more light on the interrelationship of these treaties. (orig.) [de

  1. Lessons from the Fukushima nuclear power accident

    International Nuclear Information System (INIS)

    Hatamura, Yotaro

    2013-01-01

    Through the investigation of the Fukushima Nuclear Power Accident as the chairman of the related Government's Committee, many things had been considered. Essence of the accident could be not only what occurred in the Fukushima nuclear power station, but also dispersed radioactive materials forced many residents to move and not to be returned. Such events as indication errors of water level meter occurring in severe accident could no be thought and remote mechanical operation of valves under high radiation environment were not prepared. Contamination by radioactive clouds caused the evacuation of residents for a long period. Lessons learned from the accident were described such as; (1) the verification of the road to failure connecting selected accident sequence and road to success with another supposed choice, (2) considering what might occur and then what should be needed on the contrary, (3) nuclear power, if should be continued, should be used with the premise of its hazards, and (4) advise to nuclear engineer for adequate information dissemination and technical explanation to the public and keeping nuclear technologies alive. (T. Tanaka)

  2. Spent fuel transportation accident: a state's involvement

    International Nuclear Information System (INIS)

    Neuweg, M.

    1978-01-01

    On February 9, 1978 at 8:20 p.m., the duty officer for the Illinois Radiological Assistance Team was notified that a shipment containing uranium and plutonium was involved in an accident near Gibson City, Illinois on Route 54. It was reported that a pig containing an unknown amount of uranium and plutonium was involved. The Illinois District 6A State Police were called to the scene and secured the area. The duty officer in the meantime learned after numerous telephone calls, approximately 1 hour after the first notice was received, that the pig actually was a 48,000 pound cask containing 6 spent fuel rods and the tractor-trailer had split apart and was blocking one lane of the highway. The shipment had departed from Dresden Nuclear Power Station, Morris, Illinois, enroute to Babcox and Wilcox in Lynchburg, Virginia. Initial reports indicated the vehicle had split apart. Actually, the semi-trailer bed had buckled beneath the cask due to apparent excess stress. The cask remained entirely intact and was not damaged, but the state highway was closed to traffic. The State Radiological Assistance Team was dispatched and arrived on the scene at 12:45 a.m. Immediate radiation monitoring revealed a reading of 4 milliroentgen per hour at 10 feet from the cask. No contamination existed nor was anyone exposed to radiation unnecessarily. The cask was transferred to a Tri-State semi-trailer vehicle the following morning at approximately 6:30 a.m. At 9:30 a.m., February 10, the new vehicle was again enroute to its destination. This incident demonstrated typical occurrences involving transportation radiation accident: misinformation and/or lack of information on the initial response notification, inaccuracies of radiation monitorings at the scene of the accident, inconsistencies concerning the occurrences of the accident and unfamiliar terminology utilized by personnel first on the scene, i.e., pig, cask, vehicle split apart, etc

  3. 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)

  4. Emergency response and nuclear risk governance. Nuclear safety at nuclear power plant accidents

    International Nuclear Information System (INIS)

    Kuhlen, Johannes

    2014-01-01

    The present study entitled ''Emergency Response and Nuclear Risk Governance: nuclear safety at nuclear power plant accidents'' deals with issues of the protection of the population and the environment against hazardous radiation (the hazards of nuclear energy) and the harmful effects of radioactivity during nuclear power plant accidents. The aim of this study is to contribute to both the identification and remediation of shortcomings and deficits in the management of severe nuclear accidents like those that occurred at Chernobyl in 1986 and at Fukushima in 2011 as well as to the improvement and harmonization of plans and measures taken on an international level in nuclear emergency management. This thesis is divided into a theoretical part and an empirical part. The theoretical part focuses on embedding the subject in a specifically global governance concept, which includes, as far as Nuclear Risk Governance is concerned, the global governance of nuclear risks. Due to their characteristic features the following governance concepts can be assigned to these risks: Nuclear Safety Governance is related to safety, Nuclear Security Governance to security and NonProliferation Governance to safeguards. The subject of investigation of the present study is as a special case of the Nuclear Safety Governance, the Nuclear Emergency governance, which refers to off-site emergency response. The global impact of nuclear accidents and the concepts of security, safety culture and residual risk are contemplated in this context. The findings (accident sequences, their consequences and implications) from the analyses of two reactor accidents prior to Fukushima (Three Mile Iceland in 1979, Chernobyl in 1986) are examined from a historical analytical perspective and the state of the Nuclear Emergency governance and international cooperation aimed at improving nuclear safety after Chernobyl is portrayed by discussing, among other topics, examples of &apos

  5. Civil liability concerning nuclear accidents

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    France and the USA wish to cooperate in order to promote an international regime of civil liability in order to give a fair compensation to victims of nuclear accidents as it is recommended by IAEA. On the other hand the European Commission has launched a consultation to see the necessity or not to harmonize all the civil liability regimes valid throughout Europe. According to the Commission the potential victims of nuclear accidents would not receive equal treatment at the European scale in terms of insurance cover and compensation which might distort competition in the nuclear sector. (A.C.)

  6. Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

    Science.gov (United States)

    TANAKA, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. PMID:23138450

  7. Accident at the Fukushima Dai-ichi nuclear power stations of TEPCO. Outline and lessons learned

    International Nuclear Information System (INIS)

    Tanaka, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. (author)

  8. Nuclear ship accidents, description and analysis

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-03-01

    In this report available information on 44 reported nuclear ship events is considered. Of these 6 deals with U.S. ships and 38 with USSR ships. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/ explosions, sea-water leaks into the submarines and sinking of vessels are considered. Comments are made on each of the events, and at the end of the report an attempt is made to point out the weaknesses of the submarine designs which have resulted in the accidents. It is emphasized that some of the information of which this report is based, may be of dubious nature. Consequently some of the results of the assessments made may not be correct. (au)

  9. Personal nuclear accident dosimetry at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Ward, D.C.; Mohagheghi, A.H.; Burrows, R.

    1996-09-01

    DOE installations possessing sufficient quantities of fissile material to potentially constitute a critical mass, such that the excessive exposure of personnel to radiation from a nuclear accident is possible, are required to provide nuclear accident dosimetry services. This document describes the personal nuclear accident dosimeter (PNAD) used by SNL and prescribes methodologies to initially screen, and to process PNAD results. In addition, this report describes PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study (NAD23), held during 12-16 June 1995, at Los Alamos National Laboratories. Biases for reported neutron doses ranged from -6% to +36% with an average bias of +12%

  10. Trucks involved in fatal accidents factbook 2008.

    Science.gov (United States)

    2011-03-01

    This document presents aggregate statistics on trucks involved in traffic accidents in 2008. The : statistics are derived from the Trucks Involved in Fatal Accidents (TIFA) file, compiled by the : University of Michigan Transportation Research Instit...

  11. Buses involved in fatal accidents factbook 2007

    Science.gov (United States)

    2010-03-01

    This document presents aggregate statistics on buses involved in traffic accidents in 2007. The : statistics are derived from the Buses Involved in Fatal Accidents (BIFA) file, compiled by the : University of Michigan Transportation Research Institut...

  12. Trucks involved in fatal accidents factbook 2007.

    Science.gov (United States)

    2010-01-01

    This document presents aggregate statistics on trucks involved in traffic accidents in 2007. The : statistics are derived from the Trucks Involved in Fatal Accidents (TIFA) file, compiled by the : University of Michigan Transportation Research Instit...

  13. The Impact of Severe Nuclear Accidents on National Decision for Nuclear Decommissioning

    International Nuclear Information System (INIS)

    Suh, Young A; Hornibrook, Carol; Yim, Man Sung

    2016-01-01

    Many researchers have tried to identify the impact of severe nuclear accidents on a country's or international nuclear energy policy [2-3]. However, there is little research on the influence of nuclear accidents and historical events on a country's decision to permanently shutdown an NPP versus international nuclear decommissioning trends. To demonstrate the correlation between a nuclear severe accident and the impact on world nuclear decommissioning, this research reviewed case studies of individual historical events, such as the St. Lucens, TMI, Chernobyl, Fukushima accidents and the series of events leading up to the collapse of the Soviet Union. For validation of the results of these case studies, a statistical analysis was conducted using the R code. This will be useful in explaining how international and national decommissioning strategies are affected by shutdown reasons, i.e. world historical events. The number of permanently shutdown NPPs was selected as an indicator because any relationship between the number of permanently In conclusion, nuclear severe accidents and historical events have an impact on the number of international NPPs that shutdown permanently and cancelled NPP construction. This directly impacts international nuclear decommissioning policy and nuclear energy policy trends. The number of permanently shutdown NPPs was selected as an indicator because any relationship between the number of permanently

  14. The Fukushima Dai-ichi Accident and its implications for the safety of nuclear power

    Science.gov (United States)

    Barletta, William

    2016-05-01

    Five years ago the dramatic events in Fukushima that followed the massive earthquake and subsequent tsunami that struck Japan on March 11, 2011 sharpened the focus of scientists, engineers and general public on the broad range of technical, environmental and societal issues involved in assuring the safety of the world's nuclear power complex. They also called into question the potential of nuclear power to provide a growing, sustainable resource of CO2-free energy. The issues raised by Fukushima Dai-ichi have provoked urgent concern, not only because of the potential harm that could result from severe accidents or from intentional damage to nuclear reactors or to facilities involved in the nuclear fuel cycle, but also because of the extensive economic impact of those accidents and of the measures taken to avoid them.

  15. Short term and long term radiation protection aspects of a nuclear accident: a Cd-Rom for a better stake holders' involvement

    International Nuclear Information System (INIS)

    Oudiz, A.; Badie, M.; Brenot, J.

    2002-01-01

    Many players are involved in managing a nuclear accident apart from radiation protection and nuclear safety experts. In an emergency response situation, the decision making process involves many non-technical players who nonetheless have a major role to play: in France these may include the Prefet, the emergency and civil defence services, the health services, the police, the gendarmerie and local councillors, with advice from the safety and radiological protection authorities and expert evaluation organisations. Within the post-accident response, other players will be involved alongside those already described: professional bodies, particularly farming organisations, residents' associations, those responsible for environmental decontamination, agencies responsible for compensating victims, etc., etc. In both the short and the long-term phases of the crisis management process, it is essential to enable participants who may have very different backgrounds and professional experience to work together with co-operation and mutual understanding. If non-technical players are to contribute effectively, there needs to be a minimum level of mutual understanding between them and the technical players on what the nuclear risk really is and what is the rationale of the short and long term counter-measures aimed at protecting the public and restoring the contaminated environment. Local communities also need to share this basic understanding because their cooperation is required in order to implement the counter-measures properly. Conversely, if the experts are to advise the local authorities properly, they need to understand the criteria on which these local authorities and communities base their decisions: what psycho-sociological factors apply, what logistical support is needed, what are the concerns of the local communities?

  16. Medical consequences of a nuclear plant accident

    International Nuclear Information System (INIS)

    Olsson, S.E.; Reizenstein, P.; Stenke, L.

    1987-01-01

    The report gives background information concerning radiation and the biological medical effects and damages caused by radiation. The report also discusses nuclear power plant accidents and efforts from the medical service in the case of a nuclear power plant accident. (L.F.)

  17. Report of a Special Committee on the Review of U.S. Nuclear Power Plant Accident, second report

    International Nuclear Information System (INIS)

    1979-01-01

    Following on the issuance of the first report, for the accident in Three Mile Island Nuclear Power Plant in the United States there has appeared detailed information of such as reactor operation and radiation control. This has enabled technical evaluation of those items involved in nuclear power safety. The review results up to the beginning of September 1979 are presented, to meet popular desires to know the accident situation and to reflect the results in the nation's nuclear power generation. Contents are features and background of the TMI Nuclear Power Plant accident consequences, safety measures to be taken in Japan, and (in the appendix) the data on the TMI accident, countermeasures taken in Japan, etc. (Mori, K.)

  18. Review and compilation of criticality accidents in nuclear fuel processing facilities outside of Japan

    International Nuclear Information System (INIS)

    Watanabe, Norio; Tamaki, Hitoshi

    2000-04-01

    On September 30, 1999, a criticality accident occurred at the Tokai-mura uranium processing plant operated by JCO Co., Ltd., which resulted in the first nuclear accident involving a fatality, in Japan, and forced the residents in the vicinity of the site to be evacuated and be sheltered indoors. There have now been 21 criticality accidents reported in nuclear fuel processing facilities in foreign countries: seven in the United States, one in the United Kingdom and thirteen in Russia. Most of them occurred during the period from mid-1950's to mid-1960's, but one criticality accident tool place in Russian in 1997. This report reviews and compiles the published information on these accidents, including the latest information, focusing on the event sequence, the consequence of accident, and the cause of accident. The observations from the reviews are summarized as follows: Twenty of the 21 accidents occurred with the fissile material in a liquid. Twenty of the 21 accidents occurred in vessels/tanks with unfavorable geometry but one occurred in the vessel with favorable geometry. There were seven fatalities that were involved in five accidents. Three accidents involved a re-criticality condition caused by inadequate operator actions and two of them led to the death of the operators. One accident reached a re-criticality condition several hours after the first excursion was terminated by injecting borated water into the affected vessel. This accident implies the possibility that the borated water injection might not be effective to the criticality termination due to solubility of boric acid. Mechanisms of the criticality termination vary as follows: ejection or splashing of the solution at the time of power excursion, boiling or evaporation, addition of neutron poisons, or manual draining of solutions. (author)

  19. Review and compilation of criticality accidents in nuclear fuel processing facilities outside of Japan

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Norio [Planning and Analysis Division, Nuclear Safety Research Center, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Tamaki, Hitoshi [Department of Safety Research Technical Support, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

    2000-04-01

    On September 30, 1999, a criticality accident occurred at the Tokai-mura uranium processing plant operated by JCO Co., Ltd., which resulted in the first nuclear accident involving a fatality, in Japan, and forced the residents in the vicinity of the site to be evacuated and be sheltered indoors. There have now been 21 criticality accidents reported in nuclear fuel processing facilities in foreign countries: seven in the United States, one in the United Kingdom and thirteen in Russia. Most of them occurred during the period from mid-1950's to mid-1960's, but one criticality accident tool place in Russian in 1997. This report reviews and compiles the published information on these accidents, including the latest information, focusing on the event sequence, the consequence of accident, and the cause of accident. The observations from the reviews are summarized as follows: Twenty of the 21 accidents occurred with the fissile material in a liquid. Twenty of the 21 accidents occurred in vessels/tanks with unfavorable geometry but one occurred in the vessel with favorable geometry. There were seven fatalities that were involved in five accidents. Three accidents involved a re-criticality condition caused by inadequate operator actions and two of them led to the death of the operators. One accident reached a re-criticality condition several hours after the first excursion was terminated by injecting borated water into the affected vessel. This accident implies the possibility that the borated water injection might not be effective to the criticality termination due to solubility of boric acid. Mechanisms of the criticality termination vary as follows: ejection or splashing of the solution at the time of power excursion, boiling or evaporation, addition of neutron poisons, or manual draining of solutions. (author)

  20. The Impact of Severe Nuclear Accidents on National Decision for Nuclear Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Young A; Hornibrook, Carol; Yim, Man Sung [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    Many researchers have tried to identify the impact of severe nuclear accidents on a country's or international nuclear energy policy [2-3]. However, there is little research on the influence of nuclear accidents and historical events on a country's decision to permanently shutdown an NPP versus international nuclear decommissioning trends. To demonstrate the correlation between a nuclear severe accident and the impact on world nuclear decommissioning, this research reviewed case studies of individual historical events, such as the St. Lucens, TMI, Chernobyl, Fukushima accidents and the series of events leading up to the collapse of the Soviet Union. For validation of the results of these case studies, a statistical analysis was conducted using the R code. This will be useful in explaining how international and national decommissioning strategies are affected by shutdown reasons, i.e. world historical events. The number of permanently shutdown NPPs was selected as an indicator because any relationship between the number of permanently In conclusion, nuclear severe accidents and historical events have an impact on the number of international NPPs that shutdown permanently and cancelled NPP construction. This directly impacts international nuclear decommissioning policy and nuclear energy policy trends. The number of permanently shutdown NPPs was selected as an indicator because any relationship between the number of permanently.

  1. Explanation of procedure on site medical emergency response for nuclear accident

    International Nuclear Information System (INIS)

    Liu Yulong; Jiang Zhong

    2012-01-01

    National occupational health standard-Procedure on Site Medical Emergency Response for Nuclear Accident has been approved and issued by the Ministry of Health. This standard is formulated according to the Emergency Response Law of the People's Republic of China, Law of the People 's Republic of China on Prevention and Control of Occupational Diseases, Regulations on Emergency Measures for Nuclear Accidents at Nuclear Power Plants, and Health Emergency Plans for Nuclear and Radiological Accidents of Ministry of Health, supporting the use of On-site Medical Emergency Planning and Preparedness for Nuclear Accidents and Off-site Medical Emergency Planning and Preparedness for Nuclear Accidents. Nuclear accident on-site medical response procedure is a part of the on-site emergency plan. The standard specifies the basic content and requirements of the nuclear accident on-site medical emergency response procedures of nuclear facilities operating units to guide and regulate the work of nuclear accident on-site medical emergency response of nuclear facilities operating units. The criteria-related contents were interpreted in this article. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

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

  3. Preparedness against nuclear power accidents

    International Nuclear Information System (INIS)

    1985-01-01

    This booklet contains information about the organization against nuclear power accidents, which exist in the four Swedish counties with nuclear power plants. It is aimed at classes 7-9 of the Swedish schools. (L.E.)

  4. Nuclear fuel in a reactor accident.

    Science.gov (United States)

    Burns, Peter C; Ewing, Rodney C; Navrotsky, Alexandra

    2012-03-09

    Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing hundreds of radionuclides, many with short half-lives. The long-lived fission products and transuranium elements within damaged fuel remain a concern for millennia. Currently, accurate fundamental models for the prediction of release rates of radionuclides from fuel, especially in contact with water, after an accident remain limited. Relatively little is known about fuel corrosion and radionuclide release under the extreme chemical, radiation, and thermal conditions during and subsequent to a nuclear accident. We review the current understanding of nuclear fuel interactions with the environment, including studies over the relatively narrow range of geochemical, hydrological, and radiation environments relevant to geological repository performance, and discuss priorities for research needed to develop future predictive models.

  5. Aftermath of the Fukushima Daiichi nuclear accident in March 2011 - Situation review in March 2016

    International Nuclear Information System (INIS)

    2016-03-01

    The first part of this detailed report addresses the consequences of the accident regarding nuclear safety. It proposes a situation review of site damaged installations, of radioactive water management, and of underground water management. It presents and comments lessons learned from this accident for French nuclear installations, gives an overview of researches performed by the IRSN in the field of nuclear safety. The second part addresses health consequences of the accident. It discusses an assessment of epidemiologic studies performed on inhabitants of the Fukushima Prefecture, and comments the situation of workers involved in operations performed in the Fukushima Daiichi nuclear power plant. The third part addresses environmental consequences. It discusses values of radionuclide concentrations in Japanese air five years after the accident, measurements of caesium activities, assessments of contamination of Japanese food products, decontamination actions and waste management, the status of marine contamination in 2015, the evolution of evacuation areas between 2011 and 2016, the first returns and wills to return of evacuated populations, the update of knowledge related to the dispersion and depositions of atmospheric releases of the accident, and the modelling of atmospheric transport and fallouts of releases emitted during the accident. The last part proposes a comparison between the Chernobyl accident and the Fukushima accident in terms of distribution of radioactive depositions within river basins, of knowledge drawn from ecologic studies on fauna and flora performed on the long term in contaminated areas, and of management of forest environments after a nuclear accident

  6. National response plan - Major nuclear or radiological accidents

    International Nuclear Information System (INIS)

    2014-02-01

    preparation for the post-accident phase), the period in which the public must be protected and assisted and the accident must be handled so that the situation is brought back under control. Each emergency management stage in the plan is based on constant communication with each type of public and attention to the public's demand for transparent information. Its objectives are to ensure that: the general public is protected, particularly from exposure to radioactivity; injured persons or people who are exposed to radioactivity receive assistance; economic and social continuity is not disrupted; the measures required to manage the post-accident phase and restore society and its economic and social activities to normal are pro-actively implemented, European and international relations are coordinated. This response plan refers to reference situations rather than accident scenarios as their kinetics, progression and consequences cannot be defined in advance. It must remain adaptable to changes in the situation at hand. As a result, it covers a broad range of accident situations. Although it includes the duties of facility operators, it does not address their internal procedures, such as their on-site emergency plans, which are aimed at running nuclear facilities under all situations and mitigating the consequences of emergencies on workers, the general public and the environment. Due to their magnitude and the fact that they involve different ministries, major crises require a comprehensive government response. They require strong coordination with not only national and local crisis-management participants, but external partners, such as in the EU, as well. To be able to handle these major emergencies, the White Paper on national defense and security recommends implementing an integrated emergency management system that increases the government s ability to respond to emergencies and ensures better central coordination. It is within this framework of improving the French

  7. Chairperson's Summary, International Expert Meeting on Decommissioning and Remediation after a Nuclear Accident

    International Nuclear Information System (INIS)

    Larsson, Carl Magnus

    2013-01-01

    History has clearly demonstrated, and it has repeated itself in the events and aftermath of March 2011, that a major nuclear accident, just as any other major accident, not only affects public and environmental health, but in addition causes a wide range of direct and indirect effects. These include evacuation and relocation; social unrest; indirect health effects related to anxiety, radiological stigma and symptoms of a post-traumatic nature; as well as effects on property, the economy, public policy and politics. All of these factors influence the setting of targets for decommissioning and remediation; this is often an iterative process involving consideration of the legal framework, finances, processes and methodology and technology. Importantly, decommissioning and remediation is carried out in close interaction with stakeholders, of which the public (affected by both the accident and the recovery from its consequences) form an important part. Today, we have substantial knowledge about the impact of major nuclear accidents as well as a wealth of experience - good and sometimes less so - from a range of decommissioning and remediation projects following nuclear accidents. There are also a number of lessons to be learned from decommissioning and remediation of other legacy sites that have not originated from nuclear accidents but where the problems encountered are of similar nature. Experiences have over the years been discussed in many fora, including a number of IAEA initiatives and UNSCEAR reviews of scientific information on health and environmental effects of accidents and legacies of comparable nature. It is timely to discuss this knowledge in relation to the Fukushima Daiichi accident, to provide guidance to future actions aimed at strengthening our understanding of the exposure situation, and our ability to successfully carry out decommissioning of facilities and environmental remediation after a nuclear accident. (author)

  8. Nuclear accidents and protection

    International Nuclear Information System (INIS)

    Biocanin, R.; Amidzic, B.

    2005-01-01

    The numerous threats are our cruel reality. There is a great arsenal of nuclear weapons. Nuclear terrorism and nuclear accidents are always possible, especially during the transport and handling different nuclear material. Terrorist organisation also goes for coming into the possession of the nuclear means. Specific and important problem is human radioactive contamination in using nuclear energy for peaceful and military purpose. So, realisation of the universal and united system of NBCD gives us a possibility by using the modern communication equipment and very effective mobile units to react in a real time and successfully perform monitoring, alarming, protection and decontamination. (author) [sr

  9. Emergency preparedness: medical management of nuclear accidents involving large groups of victims

    International Nuclear Information System (INIS)

    Parmentier, N.; Nenot, J.C.

    1988-01-01

    The treatment of overexposed individuals implies hospitalisation in a specialized unit applying hematological intense care. If the accident results in a small number of casualties, the medical management does not raise major problems in most of the countries, where specialized units exist, as roughly 7% of the beds are available at any time. But an accident which would involved tens or hundreds of people raises much more problems for hospitalization. Such problems are also completely different and will involve steps in the medical handling, mainly triage, (combined injuries), determination of whole body dose levels, transient hospitalization. In this case, preplanning is necessary, adapted to the system of medical care in case of a catastrophic event in the given Country, with the main basic principles : emergency concerns essentially the classical injuries (burns and trauma) - and contamination problems in some cases - treatment of radiation syndrome is not an emergency during the first days but some essential actions have to be taken such as early blood sampling for biological dosimetry and for HLa typing

  10. Compensation for damages in case of a nuclear accident

    International Nuclear Information System (INIS)

    Leger, M.

    2011-01-01

    This article presents the system of compensation for damages in case of a nuclear accident. This system of civil liability for nuclear damage, as a specific regime, departs on several points from the common rules of civil liability, in order to provide an adequate and equitable compensation for the damages suffered by the victims of nuclear accidents. The French system of civil liability for nuclear damage results from two International Conventions integrated in French law (Paris convention 1960 and Brussels convention 1963) and the French law of 1968, October 30 on civil liability in the area of nuclear energy. These texts define the conditions under which a nuclear operator could be held liable in case of a nuclear accident. The protocols to amend the Paris and Brussels Conventions of 2004, not yet come into force, are also presented. They ensure that increased resources are available to compensate a greater number of victims of a nuclear accident. (author)

  11. A comparison of the hazard perception ability of accident-involved and accident-free motorcycle riders.

    Science.gov (United States)

    Cheng, Andy S K; Ng, Terry C K; Lee, Hoe C

    2011-07-01

    Hazard perception is the ability to read the road and is closely related to involvement in traffic accidents. It consists of both cognitive and behavioral components. Within the cognitive component, visual attention is an important function of driving whereas driving behavior, which represents the behavioral component, can affect the hazard perception of the driver. Motorcycle riders are the most vulnerable types of road user. The primary purpose of this study was to deepen our understanding of the correlation of different subtypes of visual attention and driving violation behaviors and their effect on hazard perception between accident-free and accident-involved motorcycle riders. Sixty-three accident-free and 46 accident-involved motorcycle riders undertook four neuropsychological tests of attention (Digit Vigilance Test, Color Trails Test-1, Color Trails Test-2, and Symbol Digit Modalities Test), filled out the Chinese Motorcycle Rider Driving Violation (CMRDV) Questionnaire, and viewed a road-user-based hazard situation with an eye-tracking system to record the response latencies to potentially dangerous traffic situations. The results showed that both the divided and selective attention of accident-involved motorcycle riders were significantly inferior to those of accident-free motorcycle riders, and that accident-involved riders exhibited significantly higher driving violation behaviors and took longer to identify hazardous situations compared to their accident-free counterparts. However, the results of the regression analysis showed that aggressive driving violation CMRDV score significantly predicted hazard perception and accident involvement of motorcycle riders. Given that all participants were mature and experienced motorcycle riders, the most plausible explanation for the differences between them is their driving style (influenced by an undesirable driving attitude), rather than skill deficits per se. The present study points to the importance of

  12. Spread of fission products after a nuclear melt-down accident

    International Nuclear Information System (INIS)

    Andriesse, C.D.; Tanke, R.H.J.

    1987-01-01

    In this article experimental investigation is described into the spread of fission products within a nuclear power plant, which after an accident involving melting of the nucleus, will be possible in spite of prohibiting constructions for the case of severe unbalancing of generated and carried-off energy. 6 refs.; 4 figs

  13. Design of a High Power Robotic Manipulator for Emergency Response to the Nuclear Accidents

    International Nuclear Information System (INIS)

    Park, Jongwon; Bae, Yeong-Geol; Kim, Myoung Ho; Choi, Young Soo

    2016-01-01

    An accident in a nuclear facility causes a great social cost. To prevent an unexpected nuclear accident from spreading to the catastrophic disaster, emergency response action in early stage is required. However, high radiation environment has been proved as a challenging obstacle for human workers to access to the accident site and take an action in previous accident cases. Therefore, emergency response robotic technology to be used in a nuclear accident site instead of human workers are actively conducted in domestically and internationally. Robots in an accident situation are required to carry out a variety of tasks depend on the types and patterns of accidents. An emergency response usually includes removing of debris, make an access road to a certain place and handling valves. These tasks normally involve high payload handling. A small sized high power robotic manipulator can be an appropriate candidate to deal with a wide spectrum of tasks in an emergency situation. In this paper, we discuss about the design of a high power robotic manipulator, which is capable of handling high payloads for an initial response action to the nuclear facility accident. In this paper, we presented a small sized high power robotic manipulator design. Actuator types of manipulator was selected and mechanical structure was discussed. In the future, the servo valve and hydraulic pump systems will be determined. Furthermore, control algorithms and test bed experiments will be also conducted

  14. Design of a High Power Robotic Manipulator for Emergency Response to the Nuclear Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jongwon; Bae, Yeong-Geol; Kim, Myoung Ho; Choi, Young Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    An accident in a nuclear facility causes a great social cost. To prevent an unexpected nuclear accident from spreading to the catastrophic disaster, emergency response action in early stage is required. However, high radiation environment has been proved as a challenging obstacle for human workers to access to the accident site and take an action in previous accident cases. Therefore, emergency response robotic technology to be used in a nuclear accident site instead of human workers are actively conducted in domestically and internationally. Robots in an accident situation are required to carry out a variety of tasks depend on the types and patterns of accidents. An emergency response usually includes removing of debris, make an access road to a certain place and handling valves. These tasks normally involve high payload handling. A small sized high power robotic manipulator can be an appropriate candidate to deal with a wide spectrum of tasks in an emergency situation. In this paper, we discuss about the design of a high power robotic manipulator, which is capable of handling high payloads for an initial response action to the nuclear facility accident. In this paper, we presented a small sized high power robotic manipulator design. Actuator types of manipulator was selected and mechanical structure was discussed. In the future, the servo valve and hydraulic pump systems will be determined. Furthermore, control algorithms and test bed experiments will be also conducted.

  15. Nuclear-station post-accident liquid-sampling system: developed by Duke Power Company

    International Nuclear Information System (INIS)

    Burton, D.A.; Birch, M.L.; Orth, W.C.

    1981-01-01

    The accident at Three Mile Island showed that means must be provided to determine the radioactivity levels in high activity liquid and gaseous systems of a nuclear power plant without undue radiation exposure to personnel. The Duke Power Post Accident Liquid Sampling System provides the means for obtaining diluted liquid samples and diluted dissolved gas samples following a reactor accident involving substantial core damage. Their approach yields a straightforward engineering solution at a fraction of the cost of other systems. A description of the system, general design criteria, and color coded flow diagrams are included

  16. An introduction to serious nuclear accident chemistry

    Directory of Open Access Journals (Sweden)

    Mark Russell St. John Foreman

    2015-12-01

    Full Text Available A review of the chemistry occurring inside a nuclear power plant during a serious reactor accident is presented. This includes some aspects of the behavior of nuclear fuel, its cladding, cesium and iodine. This review concentrates on the chemistry of an accident in a water-cooled reactor loaded with uranium dioxide or mixed metal oxide fuel.

  17. Regulatory aspects of nuclear accidents

    International Nuclear Information System (INIS)

    Caoui, A.

    1988-01-01

    The legislative systems used in different countries insist on requiring the license of the nuclear installations exploitation and on providing a nuclear safety report. For obtaining this license, the operators have to consider all situations of functioning (normal, incidental and accidental) to make workers and the public secure. The licensing procedures depend on the juridical and administrative systems of the country. Usually, protection of people against ionzing radiation is the responsibility of the ministry of health and the ministry of industry. In general, the regulations avoid to fix a definite technical standards by reason of technological development. An emergency plan is normally designed in the stage of the installation project planification. This plan contains the instructions and advices to give to populations in case of accident. The main lesson learnt from the nuclear accidents that happened is to enlarge the international cooperation in the nuclear safety field. 4 refs. (author)

  18. Accident analysis for nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    Deterministic safety analysis (frequently referred to as accident analysis) is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). Owing to the close interrelation between accident analysis and safety, an analysis that lacks consistency, is incomplete or is of poor quality is considered a safety issue for a given NPP. Developing IAEA guidance documents for accident analysis is thus an important step towards resolving this issue. Requirements and guidelines pertaining to the scope and content of accident analysis have, in the past, been partially described in various IAEA documents. Several guidelines relevant to WWER and RBMK type reactors have been developed within the IAEA Extrabudgetary Programme on the Safety of WWER and RBMK NPPs. To a certain extent, accident analysis is also covered in several documents of the revised NUSS series, for example, in the Safety Requirements on Safety of Nuclear Power Plants: Design (NS-R-1) and in the Safety Guide on Safety Assessment and Verification for Nuclear Power Plants (NS-G-1.2). Consistent with these documents, the IAEA has developed the present Safety Report on Accident Analysis for Nuclear Power Plants. Many experts have contributed to the development of this Safety Report. Besides several consultants meetings, comments were collected from more than fifty selected organizations. The report was also reviewed at the IAEA Technical Committee Meeting on Accident Analysis held in Vienna from 30 August to 3 September 1999. The present IAEA Safety Report is aimed at providing practical guidance for performing accident analyses. The guidance is based on present good practice worldwide. The report covers all the steps required to perform accident analyses, i.e. selection of initiating events and acceptance criteria, selection of computer codes and modelling assumptions, preparation of input data and presentation of the

  19. Stakeholder involvement in the management of rural areas following a nuclear accident: the farming network

    International Nuclear Information System (INIS)

    Mercer, J.; Nisbet, A.F.

    2002-01-01

    The importance of the participation of stakeholders in the formulation of strategies for maintaining agricultural production and food safety following a nuclear accident, has been successfully demonstrated by the Agriculture and Food Countermeasures Working Group (AFCWG). This group was set up in the UK by the National Radiological Protection Board (NRPB) and the then Ministry of Agriculture, Fisheries and Food in 1997 (Nisbet and Mondon, 2001). Before this time stakeholder organisations had not collectively considered the implications of contamination of the foodchain in the event of an accidental release of radioactivity. With funding from the European Commission (EC) the UK approach to stakeholder engagement is being taken forward on a European basis during the period 2000-2004 through a project given the acronym FARMING (Food and Agriculture Restoration Management Involving Networked Groups). The overall objective of this project is to create a network of stakeholder working groups in 5 member states (UK, Belgium, Finland, France and Greece) to assist in the development of robust and practicable strategies for restoring and managing contaminated agricultural land and food products in a sustainable way. The initial intention was to involve at least 50 individual stakeholders

  20. Emergency planning and preparedness for a nuclear accident

    International Nuclear Information System (INIS)

    Rahe, E.P.

    1985-01-01

    Based on current regulations, FEMA approves each site-specific plan of state and local governments for each power reactor site after 1) formal review offsite preparedness, 2) holding a public meeting at which the preparedness status has been reviewed, and 3) a satisfactory joint exercise has been conducted with both utility and local participation. Annually, each state, within any position of the 10-mile emergency planning zone, must conduct a joint exercise with the utility to demonstrate its preparedness for a nuclear accident. While it is unlikely that these extreme measures will be needed as a result of an accident at a nuclear power station, the fact that these plans have been well thought out and implemented have already proven their benefit to society. The preparedness for a nuclear accident can be of great advantage in other types of emergencies. For example, on December 11, 1982, a non-nuclear chemical storage tank exploded at a Union Carbide plant in Louisiana shortly after midnight. More than 20,000 people were evacuated from their homes. They were evacuated under the emergency response plan formulated for use in the event of a nuclear accident at the nearby Waterford Nuclear plants. Clearly, this illustrates how a plan conceived for one purpose is appropriate to handle other types of accidents that occur in a modern industrial society

  1. Contribution to evaluating nuclear power plant accidents

    International Nuclear Information System (INIS)

    Razga, J.; Horacek, P.

    1990-01-01

    Large-scale accidents pose the highest risk in the use of nuclear power. They are the major factor that has to be taken into account when assessing the effect of nuclear power plants on human health and on the environment. In Czechoslovak conditions, the effectiveness of provisions made to reduce the hazard of large-scale nuclear power plant accidents must be considered from the following aspects: effect on human health, consequences of long-term disabling of the infrastructure, potential of human and material reserves in coping with the accident, consequences of power failure for the electricity system, effect on agricultural production and catering, risk of ground and surface water contamination in the Labe or Danube river basin, and international political aspects. (Z.M.). 3 tabs., 18 refs

  2. Are the French authorities beginning to prepare for nuclear accident?

    International Nuclear Information System (INIS)

    Autret, J.C.

    2008-01-01

    This article, published in issue 80 of 'l'ACROnique du nucleaire', aims to retrace the early steps in the consideration of the possibility of a nuclear accident in France, with the inclusion of 'non-institutional' participants and applying the lessons learned in Belarus in the contaminated territories around the Chernobyl nuclear power plant. After a review of the origin of the involvement of the Association pour le Controle de la Radioactivite dans l'Ouest (ACRO) in addressing post-accident issues alongside the populations living in an environment polluted by radioactivity, it discusses, from the critical viewpoint of an NGO, the context and the working method adopted for this examination. This is followed by some key elements of the programme and unresolved questions about the available body of knowledge which motivates research and about the method adopted for the work. The conclusion, moderately optimistic, highlights some advances and limits arising during this exercise in a French nuclear scene which remains characterised by a centralized mode of management. (author)

  3. Nuclear Fuel Behaviour during Reactivity Initiated Accidents. Workshop Proceedings

    International Nuclear Information System (INIS)

    2010-01-01

    A reactivity initiated accident (RIA) is a nuclear reactor accident that involves an unwanted increase in fission rate and reactor power. The power increase may damage the reactor core. The main objective of the workshop was to review the current status of the experimental and analytical studies of the fuel behavior during the RIA transients in PWR and BWR reactors and the acceptance criteria for RIA in use and under consideration. The workshop was organized in an opening session and 5 technical sessions: 1) Recent experimental results and experimental techniques used; 2) Modelling and Data Interpretation; 3) Code Assessment; 4) RIA Core Analysis and 5) Revision and application of safety criteria

  4. Occupational accidents involving biological material among public health workers.

    Science.gov (United States)

    Chiodi, Mônica Bonagamba; Marziale, Maria Helena Palucci; Robazzi, Maria Lúcia do Carmo Cruz

    2007-01-01

    This descriptive research aimed to recognize the occurrence of work accidents (WA) involving exposure to biological material among health workers at Public Health Units in Ribeirão Preto-SP, Brazil. A quantitative approach was adopted. In 2004, 155 accidents were notified by means of the Work Accident Communication (WAC). Sixty-two accidents (40%) involved exposure to biological material that could cause infections like Hepatitis and Aids. The highest number of victims (42 accidents) came from the category of nursing aids and technicians. Needles were responsible for 80.6% of accidents and blood was the biological material involved in a majority of occupational exposure cases. This subject needs greater attention, so that prevention measures can be implemented, which consider the peculiarities of the activities carried out by the different professional categories.

  5. EPRI nuclear fuel-cycle accident risk assessment

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    The present results of the nuclear fuel-cycle accident risk assessment conducted by the Electric Power Research Institute show that the total risk contribution of the nuclear fuel cycle is only approx. 1% of the accident risk of the power plant; hence, with little error, the accident risk of nuclear electric power is essentially that of the power plant itself. The power-plant risk, assuming a very large usage of nuclear power by the year 2005 is only approx. 0.5% of the radiological risk of natural background. The smallness of the fuel-cycle risk relative to the power-plant risk may be attributed to the lack of internal energy to drive an accident and the small amount of dispersible material. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihood of errors and the estimated size of errors. The primary probabilistic estimation tool is fault-tree analysis, with the release source terms calculated using physicochemical processes. Doses and health effects are calculated with CRAC (Consequences of Reactor Accident Code). No evacuation or mitigation is considered; source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/t) and short cooling period (90 to 150 d); high-efficiency particulate air filter efficiencies are derived from experiments

  6. The medical implications of nuclear power plant accidents

    International Nuclear Information System (INIS)

    Tyror, J.G.; Pearson, G.W.

    1989-11-01

    This paper examines the UK position regarding the potential for an accident at a nuclear power plant, the safeguards in place to prevent such an accident occurring and the emergency procedures designed to cope with the consequences should one occur. It focuses on the role of the medical services and examines previous accidents to suggest the nature and likely scale of response that may need to be provided. It is apparent that designs of UK nuclear power stations are robust and that the likelihood of a significant accident occurring is extremely remote. Emergency arrangements are, however, in place to deal with the eventuality should it arise and these incorporate sufficient flexibility to accommodate a wide range of accidents. Analysis of previous nuclear accidents at Windscale, Three Mile Island and Chernobyl provide a limited but valuable insight into the diversity and potential scale of response that may be required. It is concluded that above all, the response must be flexible to enable medical services to deal with the wide range of effects that may arise. (author)

  7. Our reflections and lessons from the Fukushima Nuclear Accident

    International Nuclear Information System (INIS)

    Matsuoka, Takeshi; Sawada, Takashi; Yagawa, Genki

    2017-01-01

    In order to investigate the cause of the accident that began on March 11, 2011 at the Tokyo Electric Power Company Fukushima Daiichi Nuclear Power Station, the Science Council of Japan set an investigation committee, the 'Sub-Committee on Fukushima Nuclear Accident (SCFNA)' under the Comprehensive Synthetic Engineering Committee. The committee has published a record entitled 'Reflections and Lessons from the Fukushima Nuclear Accident, (1st report)'. There are still many items about the accident for which the details are not clear. It is important to discuss the reasons why the severe accident could not be prevented and the possibilities that there might have been other proper operations and accident management to prevent or lessen the severity of the accident than those adopted at the time. SCFNA decided to continue its investigation by setting up our working group called the 'Working Group on Fukushima Nuclear Accident'. Our working group have published 'Reflection and Lessons from the Fukushima Nuclear Accident (2nd Report)'. We investigated the issues of specific units. Unit 1 were validity of the operation of the isolation condenser, whether or not a loss of coolant accident occurred due to a failure of the cooling piping system by the seismic ground motion, and the cause of the loss of the emergency AC power supply, Unit 2 was the reason why a large amount of radioactive materials was emitted to the environment although the reactor building did not explode, Unit 3 was the reasons why the operator stopped running the high pressure coolant injection system, and Units 1 to 3 was validity of the venting operation. These items were considered to be the key issues in these units that would have prevented progression to the severe accident. (author)

  8. Individual feature identification method for nuclear accident emergency decision-making

    International Nuclear Information System (INIS)

    Chen Yingfeng; Wang Jianlong; Lin Xiaoling; Yang Yongxin; Lu Xincheng

    2014-01-01

    According to the individual feature identification method and combining with the characteristics of nuclear accident emergency decision-making, the evaluation index system of the nuclear accident emergency decision-making was determined on the basis of investigation and analysis. The effectiveness of the nuclear accident emergency decision-making was evaluated based on the individual standards by solving the individual features of the individual standard identification decisions. The case study shows that the optimization result is reasonable, objective and reliable, and it can provide an effective analysis method and decision-making support for optimization of nuclear accident emergency protective measures. (authors)

  9. Stake-holder involvement in the management of rural areas after an accident

    International Nuclear Information System (INIS)

    Nisbet, A.F.

    2001-01-01

    Widespread contamination of the food chain following a nuclear accident could have considerable consequences for European farming and food industries. For the purposes of contingency planning it is important to bring together the many and diverse stakeholders who would be involved in intervention so that strategies can be developed for maintaining agricultural production and food safety. This type of approach has been successfully implemented in the UK through the setting up of the Agriculture and Food Countermeasures Working Group. Building on this initiative, the European Commission under the auspices of its 5. Framework Programme is funding a thematic network in which similar stakeholder groups are being established in four other Member States. These national groups contain individuals involved in making policy decisions within government departments and agencies, regulatory authorities, the water, milk and farming industries, the retail trade and consumer groups, as well as individuals with specialist expertise. The stakeholder network will provide a European focus for tackling future nuclear accidents and assist in the harmonization of policies and strategies between Member States. This paper gives an overview of the approaches being adopted and discusses the achievements and expected benefits of stakeholder engagement. (author)

  10. 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

  11. Severe accidents: in nuclear power plants

    International Nuclear Information System (INIS)

    1986-01-01

    A ''severe'' nuclear accident refers to a reactor accident that could exceed reactor design specifications to such a degree as to prevent cooling of the reactor's core by normal means. This report summarizes the work of a NEA Senior Group of Experts who have studied the potential response of existing light-water reactors to severe accidents and have found that current designs of reactors are far more capable of coping with severe accidents than design specifications would suggest. The report emphasises the specific knowledge and means that can be used for diagnosing a severe accident and for managing its progression in order to prevent or mitigate its consequences

  12. Severe accidents in nuclear reactors

    International Nuclear Information System (INIS)

    Ohai, Dumitru; Dumitrescu, Iulia; Tunaru, Mariana

    2004-01-01

    The likelihood of accidents leading to core meltdown in nuclear reactors is low. The consequences of such an event are but so severe that developing and implementing of adequate measures for preventing or diminishing the consequences of such events are of paramount importance. The analysis of major accidents requires sophisticated computation codes but necessary are also relevant experiments for checking the accuracy of the predictions and capability of these codes. In this paper an overview of the severe accidents worldwide with definitions, computation codes and relating experiments is presented. The experimental research activity of severe accidents was conducted in INR Pitesti since 2003, when the Institute jointed the SARNET Excellence Network. The INR activity within SARNET consists in studying scenarios of severe accidents by means of ASTEC and RELAP/SCDAP codes and conducting bench-scale experiments

  13. Severe accidents at nuclear power plants. Their risk assessment and accident management

    International Nuclear Information System (INIS)

    Abe, Kiyoharu.

    1995-05-01

    This document is to explain the severe accident issues. Severe Accidents are defined as accidents which are far beyond the design basis and result in severe damage of the core. Accidents at Three Mild Island in USA and at Chernobyl in former Soviet Union are examples of severe accidents. The causes and progressions of the accidents as well as the actions taken are described. Probabilistic Safety Assessment (PSA) is a method to estimate the risk of severe accidents at nuclear reactors. The methodology for PSA is briefly described and current status on its application to safety related issues is introduced. The acceptability of the risks which inherently accompany every technology is then discussed. Finally, provision of accident management in Japan is introduced, including the description of accident management measures proposed for BWRs and PWRs. (author)

  14. DDG Opening Remarks [International Experts' Meeting on Decommissioning and Remediation after a Nuclear Accident

    International Nuclear Information System (INIS)

    Bychkov, Alexander

    2013-01-01

    Any significant nuclear accident results in challenges in terms of the decommissioning of the damaged facilities and in many cases also in the remediation of contaminated areas outside the site boundary. These challenges include the application of appropriate technological and human resources, public involvement and the allocation of the necessary financing, which is of course considerable. There can be no real future for nuclear energy unless the global community is convinced that the legacies associated with its use can be addressed satisfactorily, whether in connection with facilities contaminated as a result of a nuclear or radiological accident, or indeed large facilities used for research or other purposes during the developmental phase of the nuclear industry. It is evident that decommissioning and remediation projects, especially for nuclear facilities and sites after an accident, will continue to be undertaken for many decades, over which time it is expected that technological developments will occur. It will be important that the new and more sophisticated technologies of the future are applied to these activities. However we should also be aware that in case of dealing with accident-damaged facilities there is a great deal to be learnt from the experience from the past 60 years and this meeting is focused directly on reviewing and distilling that experience

  15. 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)

  16. Proposal optimization in nuclear accident emergency decision based on IAHP

    International Nuclear Information System (INIS)

    Xin Jing

    2007-01-01

    On the basis of establishing the multi-layer structure of nuclear accident emergency decision, several decision objectives are synthetically analyzed, and an optimization model of decision proposals for nuclear accident emergency based on interval analytic hierarchy process is proposed in the paper. The model makes comparisons among several emergency decision proposals quantified, and the optimum proposal is selected out, which solved the uncertain and fuzzy decision problem of judgments by experts' experiences in nuclear accidents emergency decision. Case study shows that the optimization result is much more reasonable, objective and reliable than subjective judgments, and it could be decision references for nuclear accident emergency. (authors)

  17. A study on the estimation method of nuclear accident risk cost

    International Nuclear Information System (INIS)

    Matsuo, Yuji

    2016-01-01

    The methodology of estimating nuclear accident risk cost, as a part of nuclear power generation cost, has hardly been established due mainly to the extremely wide range of the estimation of the accident frequency. This study estimates the expected nuclear accident frequency for Japan, making use of the method of Bayesian statistics, which exploits both the information obtained by Probabilistic Risk Assessment (PRA) and the observed historical accident frequencies. Using the PRA estimation of the Containment Failure Frequency (CFF) for Tomari nuclear power plant unit 3 of Hokkaido Electric Power Company (average: 2.1 x 10 -4 , 95th percentile: 7.7 x 10 -4 ) and the actual large-scale accident frequency (once in 1,460 reactor-years), the posterior CFF was estimated at 3.8 x 10 -4 . This study also took into account the 'external' factor causing unexpected nuclear accidents, concluding that such factor could result in higher CFF estimations, especially with larger observed accident numbers. (author)

  18. 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

  19. Ontario is not ready to face a large-scale nuclear accident

    International Nuclear Information System (INIS)

    2017-07-01

    On paper, in Japan as elsewhere, nuclear emergency plans are based on international standards and all look similar. The counter measures are sheltering, potassium iodate prophylaxis, evacuation and control of foodstuffs. With 18 nuclear reactors to produce electricity and a research reactor, Ontario should be especially well prepared. Moreover, in USA, there are six power plants located at less than 100 km from the Canadian border. Would Ontario do better than Japan in case of a severe nuclear disaster? Ontario is not ready to face a severe nuclear accident and the population surrounding nuclear power stations are at risk. The large number of inhabitants will hamper protective response actions. Consequently, Canadian authorities keep lax protective action levels. Using more stringent levels would mean to extend the protection zone that would include a too large number of persons. Canadian authorities should openly acknowledge that a severe nuclear accident could happen in Ontario like in any other country and trigger a complete reorganisation of emergency preparedness and response (EP and R) to cope with such a possibility. New response plans should be defined with the involvement of stakeholders

  20. Analysis of emergency response to fukushima nuclear accident in Japan and suggestions for China's nuclear emergency management

    International Nuclear Information System (INIS)

    Li Wei; Ding Qihua; Wu Haosong

    2014-01-01

    On March 11, 2011, the Fukushima Dai-ichi Nuclear Power Station of the Tokyo Electric Power Company ('TEPCO') was hit and damaged by a magnitude 9 earthquake and accompanying tsunami. The accident is determined to be of the highest rating on the International Nuclear Event Scale. The Government of Japan and TEPCO have taken emergency response actions on-site and off-site at the accident. It became clear through the investigation that the accident had been initiated on the occasion of a natural disaster of an earthquake and tsunami, but there have been various complex problems behind this very serious and large scale accident. For an example, the then-available accident preventive measures and disaster preparedness of TEPCO were insufficient against tsunami and severe accidents; inadequate TEPCO emergency responses to the accident at the site were also identified. The accident rang the alarm for the nuclear safety of nuclear power plants. It also taught us a great of lessons in nuclear emergency management. (authors)

  1. Emergency preparedness and response: compensating victims of a nuclear accident

    International Nuclear Information System (INIS)

    Schwartz, Julia

    2004-01-01

    The 1986 tragedy at the Chernobyl Nuclear Power Plant in Ukraine motivated the entire international nuclear community to ensure that countries would, in the future, be well prepared to manage the physical, psychological and financial consequences of a serious nuclear accident. Since that event, numerous nuclear emergency preparedness and post-emergency management programmes have been established at national and international levels to ensure that appropriate mechanisms will respond to the threat, and the aftermath, of a nuclear accident. The INEX 2000 Workshop on the Indemnification of Nuclear Damage, jointly organised by the OECD/Nuclear Energy Agency and the French Government, was the first ever international programme to address the manner in which victims of a nuclear accident with trans-boundary consequences would be compensated for damage suffered before, during and after the accident. The Workshop results revealed striking differences in the compensation principles and practices implemented in the 30 participating countries, in the co-ordination measures between different public authorities within an affected state, and in the co-operative procedures between the accident state and its neighbours. All participants agreed on the need for improvement in these areas, particularly for maintaining public confidence in governments' ability to properly manage nuclear emergencies

  2. 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

  3. Outline of Fukushima nuclear accident and future action. Lessons learned from accident and countermeasure plan

    International Nuclear Information System (INIS)

    Fukuda, Toshihiko

    2012-01-01

    Fukushima nuclear accident was caused by loss of all AC power sources (SBO) and loss of ultimate heat sink (LUHS) at Fukushima Daiichi Nuclear Power Plants (NPPs) hit by the Great East Japan Earthquake. This article reviewed outline of Fukushima nuclear accident progression when on year had passed since and referred to lessons learned from accident and countermeasure plan to prevent severe accident in SBO and LUHS events by earthquake and tsunami as future action. This countermeasure would be taken to (1) prevent serious flooding in case a tsunami overwhelms the breakwater, with improving water tightness of rooms for emergency diesel generator, batteries and power centers, (2) enhance emergency power supply and cooling function with mobile electricity generator, high pressure fire pump car and alternate water supply source, (3) mitigate environmental effects caused by core damage with installing containment filtered venting, and (4) enforce emergency preparedness in case of severe accident. Definite countermeasure plan for Kashiwazaki-Kariwa NPPs was enumerated. (T. Tanaka)

  4. Nuclear technology and reactor safety engineering. The situation ten years after the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1996-01-01

    Ten years ago, on April 26, 1986 the most serious accident ever in the history of nuclear tgechnology worldwide happened in unit 4 of the nuclear power plant in Chernobyl in the Ukraine, this accident unveiling to the world at large that the Soviet reactor design lines are bearing unthought of safety engineering deficits. The dimensions of this reactor accident on site, and the radioactive fallout spreading far and wide to many countries in Europe, vividly nourished the concern of great parts of the population in the Western world about the safety of nuclear technology, and re-instigated debates about the risks involved and their justification. Now that ten years have elapsed since the accident, it is appropriate to strike a balance and analyse the situation today. The number of nuclear power plants operating worldwide has been growing in the last few years and this trend will continue, primarily due to developments in Asia. The Chernobyl reactor accident has pushed the international dimension of reactor safety to the foreground. Thus the Western world had reason enough to commit itself to enhancing the engineered safety of reactors in East Europe. The article analyses some of the major developments and activities to date and shows future perspectives. (orig.) [de

  5. Experience and lessons learned from emergency disposal of Fukushima nuclear power station accident

    International Nuclear Information System (INIS)

    Xu Xiegu; Zhen Bei; Yang Xiaoming; Chen Xiaohua

    2012-01-01

    After Fukushima nuclear accident, we visited the related medical aid agencies for nuclear accidents and conducted investigations in disaster-affected areas in Japan. This article summarizes the problems with emergency disposal of Fukushima nuclear accident while disclosing problems should be solved during the emergency force construction for nuclear accidents. (authors)

  6. DOZIM - evaluation dose code for nuclear accident

    International Nuclear Information System (INIS)

    Oprea, I.; Musat, D.; Ionita, I.

    2008-01-01

    During a nuclear accident an environmentally significant fission products release can happen. In that case it is not possible to determine precisely the air fission products concentration and, consequently, the estimated doses will be affected by certain errors. The stringent requirement to cope with a nuclear accident, even minor, imposes creation of a computation method for emergency dosimetric evaluations needed to compare the measurement data to certain reference levels, previously established. These comparisons will allow a qualified option regarding the necessary actions to diminish the accident effects. DOZIM code estimates the soil contamination and the irradiation doses produced either by radioactive plume or by soil contamination. Irradiations either on whole body or on certain organs, as well as internal contamination doses produced by isotope inhalation during radioactive plume crossing are taken into account. The calculus does not consider neither the internal contamination produced by contaminated food consumption, or that produced by radioactive deposits resuspension. The code is recommended for dose computation on the wind direction, at distances from 10 2 to 2 x 10 4 m. The DOZIM code was utilized for three different cases: - In air TRIGA-SSR fuel bundle destruction with different input data for fission products fractions released into the environment; - Chernobyl-like accident doses estimation; - Intervention areas determination for a hypothetical severe accident at Cernavoda Nuclear Power Plant. For the first case input data and results (for a 60 m emission height without iodine retention on active coal filters) are presented. To summarize, the DOZIM code conception allows the dose estimation for any nuclear accident. Fission products inventory, released fractions, emission conditions, atmospherical and geographical parameters are the input data. Dosimetric factors are included in the program. The program is in FORTRAN IV language and was run on

  7. 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

  8. Application of simulation techniques for accident management training in nuclear power plants

    International Nuclear Information System (INIS)

    2003-05-01

    core. These capabilities include the optimized use of design margins as well as complementary measures for the prevention of accident progression, its monitoring, and the mitigation of severe accidents. Finally, level 5 includes off-site emergency response measures, the objective of which is to mitigate the radiological consequences of significant releases of radioactive material. Accident management is defined in the IAEA Safety Report on Development and Implementation of Accident Management Programmes in Nuclear Power Plants. The IAEA definitions are in line with the definitions of severe accident management in OECD/NEA documents as given, for example. This report describes simulation techniques used in the training of personnel involved in accident management of NPPs. This concerns both the plant personnel and the persons involved in the management of off-site releases. The report pertains to light water reactors (LWRs) and pressurized heavy water reactors (PHWRs), but it can equally be applied to power reactors of other types. The report is intended for use by experts responsible for planning, developing, executing or supervising the training of personnel involved in the implementation of AMPs in NPPs. It concentrates on existing techniques, but future prospects are also discussed. Various simulation techniques are considered, from incorporating graphical interfaces into existing severe accident codes to full-scope replica simulators. Both preventive and mitigative accident management measures, different training levels and different target personnel groups are taken into account. Based on the available information compiled worldwide, present views on the applicability of simulation techniques for the training of personnel involved in accident management are provided in this report. Apart from the introduction, this report consists of four sections and three appendices. In Section 2, specific aspects of accident management are summarized. Basic approaches in the

  9. Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2011-07-01

    Consideration of severe accidents in nuclear power plants is an essential component of the defence in depth approach in nuclear safety. Severe accidents have very low probabilities of occurring, but may have significant consequences resulting from the degradation of nuclear fuel. The generation of hydrogen and the risk of hydrogen combustion, as well as other phenomena leading to overpressurization of the reactor containment in case of severe accidents, represent complex safety issues in relation to accident management. The combustion of hydrogen, produced primarily as a result of heated zirconium metal reacting with steam, can create short term overpressure or detonation forces that may exceed the strength of the containment structure. An understanding of these phenomena is crucial for planning and implementing effective accident management measures. Analysis of all the issues relating to hydrogen risk is an important step for any measure that is aimed at the prevention or mitigation of hydrogen combustion in reactor containments. The main objective of this publication is to contribute to the implementation of IAEA Safety Standards, in particular, two IAEA Safety Requirements: Safety of Nuclear Power Plants: Design and Safety of Nuclear Power Plants: Operation. These Requirements publications discuss computational analysis of severe accidents and accident management programmes in nuclear power plants. Specifically with regard to the risk posed by hydrogen in nuclear power reactors, computational analysis of severe accidents considers hydrogen sources, hydrogen distribution, hydrogen combustion and control and mitigation measures for hydrogen, while accident management programmes are aimed at mitigating hydrogen hazards in reactor containments.

  10. Learning from nuclear accident experience

    International Nuclear Information System (INIS)

    Vaurio, J.K.

    1984-01-01

    Statistical procedures are developed to estimate accident occurrence rates from historical event records, to predict future rates and trends, and to estimate the accuracy of the rate estimates and predictions. Maximum likelihood estimation is applied to several learning models, and results are compared to earlier graphical and analytical estimates. The models are based on (1) the cumulative number of operating years, (2) the cumulative number of plants built, and (3) accidents (explicitly), with the accident rate distinctly different before and after an accident. The statistical accuracies of the parameters estimated are obtained in analytical form using the Fisher information matrix. Using data on core damage accidents in electricity producing plants, it is estimated that the probability for a plant to have a serious flaw has decreased from 0.1 to 0.01 during the developmental phase of the nuclear industry. At the same time the equivalent frequency of accidents has decreased from 0.04 per reactor year to 0.0004 per reactor year, partly due to the increasing population of plants. 10 references, 7 figures, 2 tables

  11. Nuclear energy policy issues after the 3.11 Fukushima nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Tatsujiro [Japan Atomic Energy Commission (Japan)

    2014-07-01

    The Fukushima nuclear accident has become one of the worst accidents in nuclear history and it is not completely over yet. It will take at least 30 years or more to decontaminate and decommission the crippled nuclear reactors on site. Still, more than 140,000 people are away from home and restoring and assuring the life and welfare of those evacuated people is the top priority of Japanese government's nuclear energy policy. The government will release its new energy policy soon which will state that nuclear power is considered as an important base load electricity source, while committing to reduce its dependence as much as possible. For nuclear energy policy, there are certain important issues to be overcome regardless of future of nuclear power in Japan. They are: (1) spent fuel management and radioactive waste disposal, (2) restoring public trust (3) securing human resources and (4) plutonium stockpile management.

  12. Enhanced safety features of CHASHMA NPP UNIT-2 to encounter selected severe accidents, various challenges involved to prove the adequacy of severe accidents prevention/mitigation measures and to write management guidelines with one possible solution to these challenges

    International Nuclear Information System (INIS)

    Iqbal, Z.; Minhaj, A.

    2007-01-01

    This paper describes enhanced safety features of Chashma Nuclear Power Plant Unit-2 (C-2), a 325 MWe PWR to encounter selected severe accidents and discusses various challenges involved to prove the adequacy of severe accidents encountering measures and to write severe accident management guidelines (SAMGs) in compliance with the recently introduced national regulations based on the new IAEA nuclear safety standards. C-2 is being built by China National Nuclear Corporation (CNNC) for Pakistan Atomic Energy Commission (PAEC). Its twin, Unit-1 (C-1) also a 325 MWe PWR, was commissioned in 2000. Nuclear power safety with reference to severe accidents should be treated as a global issue and therefore the developed countries should include the people of developing countries in nuclear power industry's various severe accidents based research and development programs. The implementation of this idea may also deliver few other useful and mutually beneficial byproducts. (author)

  13. Radioactive release during nuclear accidents in Chernobyl and Fukushima

    Science.gov (United States)

    Nur Ain Sulaiman, Siti; Mohamed, Faizal; Rahim, Ahmad Nabil Ab

    2018-01-01

    Nuclear accidents that occurred in Chernobyl and Fukushima have initiated many research interests to understand the cause and mechanism of radioactive release within reactor compound and to the environment. Common types of radionuclide release are the fission products from the irradiated fuel rod itself. In case of nuclear accident, the focus of monitoring will be mostly on the release of noble gases, I-131 and Cs-137. As these are the only accidents have been rated within International Nuclear Events Scale (INES) Level 7, the radioactive release to the environment was one of the critical insights to be monitored. It was estimated that the release of radioactive material to the atmosphere due to Fukushima accident was approximately 10% of the Chernobyl accident. By referring to the previous reports using computational code systems to model the release rate, the release activity of I-131 and Cs-137 in Chernobyl was significantly higher compare to Fukushima. The simulation code also showed that Chernobyl had higher release rate of both radionuclides on the day of accident. Other factors affecting the radioactive release for Fukushima and Chernobyl accidents such as the current reactor technology and safety measures are also compared for discussion.

  14. Iodine removal in containment filtered venting system during nuclear accident

    International Nuclear Information System (INIS)

    Bera, Subrata; Deo, Anuj Kumar; Nagrale, D.B.; Paul, U.K.; Prasad, M.; Gaikwad, A.J.

    2015-01-01

    Post Fukushima nuclear accident, containment filtered venting system is being introduced in Indian nuclear power plant to strengthen the defense in depth safety barrier by depressurizing the containment building along with minimization of radioactivity release to environment during a severe accident. Radioactive iodine is one of the major contributors to radiation dose during early release phase of a severe accident. Physical and Chemical form of iodine and iodine bearing compounds includes particulates, elemental and organic. In the most efficient design of CFVS, wet scrubbing mechanism has been employed through use of venture scrubber. The Iodine removal process in wet scrubber involves two processes: chemical reaction in highly alkaline aqueous solution and impingement of particulates with water droplets produced in the venturi nozzle. In this paper, venturi has been modeled using the Calvert model. The variation of efficiency has been estimated for the different particle sizes. The impact of the shape parameter of log-normal distribution on the amount of scrubbed iodine has also been assessed. Release phase wise the scrubbed amount of iodine in the venturi based CFVS system has been estimated for a typical BWR. (author)

  15. Risks of potential accidents of nuclear power plants in Europe

    NARCIS (Netherlands)

    Slaper H; Eggink GJ; Blaauboer RO

    1993-01-01

    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed

  16. 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)

  17. 49 CFR 234.7 - Accidents involving grade crossing signal failure.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Accidents involving grade crossing signal failure... PLANS Reports and Plans § 234.7 Accidents involving grade crossing signal failure. (a) Each railroad... (activation failure report) and 49 CFR 225.11 (accident/ incident report). (b) Each telephone report must...

  18. Containment pressure monitoring method after severe accident in nuclear power plant

    International Nuclear Information System (INIS)

    Luo Chuanjie; Zhang Shishui

    2011-01-01

    The containment atmosphere monitoring system in nuclear power plant was designed on the basis of design accident. But containment pressure will increase greatly in a severe accident, and pressure instrument in the containment can't satisfy the monitoring requirement. A new method to monitor the pressure change in the containment after a severe accident was considered, through which accident soften methods can be adopted. Under present technical condition, adding a pressure monitoring channel out of containment for post-severe accident is a considerable method. Daya Bay Nuclear Power Plant implemented this modification, by which the containment release time can be delayed during severe accident, and nuclear safety can be increased. After analysis, this method is safe and feasible. (authors)

  19. Analysis of the 1957-1958 Soviet nuclear accident

    International Nuclear Information System (INIS)

    Trabalka, J.R.; Eyman, L.D.; Auerbach, S.I.

    1980-01-01

    The presence of an extensive environmental contamination zone in Chelibinsk Province of the Soviet Union, associated with an accident in the winter of 1957 to 1958 involving the atmospheric release of fission wastes, appears to have been confirmed, primarily by an analysis of the Soviet radioecology literature. The contamination zone is estimated to contain 10(5) to 10(6) curies of strontium-90. A plausible explanation for the incident is the use of now-obsolete techniques for waste storage and cesium-137 isotope separation. Radioactive contamination appears to have resulted in resettlement of the human population from a significant area (100 to 1000 square kilometers). It therefore seems imperative to obtain a complete explanation of the cause (or causes) and consequences of the accident; Soviet experience gained in the application of corrective measures would be invaluable to the world nuclear community

  20. Severe accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Valle Cepero, R.; Castillo Alvarez, J.; Ramon Fuente, J.

    1996-01-01

    For the assessment of the safety of nuclear power plants it is of great importance the analyses of severe accidents since they allow to estimate the possible failure models of the containment, and also permit knowing the magnitude and composition of the radioactive material that would be released to the environment in case of an accident upon population and the environment. This paper presents in general terms the basic principles for conducting the analysis of severe accidents, the fundamental sources in the generation of radionuclides and aerosols, the transportation and deposition processes, and also makes reference to de main codes used in the modulation of severe accidents. The final part of the paper contents information on how severe accidents are dialed with the regulatory point view in different countries

  1. Nuclear accidents and policy. Notes on public perception

    Energy Technology Data Exchange (ETDEWEB)

    Richter, Felix; Steenbeck, Malte; Wilhelm, Markus [Hamburg Univ. (Germany). Lehrstuhl fuer Wirtschaftspolitik

    2013-07-01

    Major nuclear accidents as recently in Fukushima set nuclear power plant security at the top of the public agenda. Using data of the German Socio-Economic Panel we analyze the effects of the Fukushima accident and a subsequent government decision on nuclear power phase-out on several measures of subjective perception in Germany. In the light of current political debates about the strategic orientation of this energy turnaround, such an analysis is of particular interest since non-pecuniary gains in measures of subjective perception might provide further aspects to be taken into consideration when evaluating the economic costs of the policy. We find that the Fukushima accident increases the probability to report greater worries about the environment. Furthermore, we find evidence for a decrease in the probability to be very worried about the security of nuclear power plants as well as for an increase in reported levels of subjective well-being following the government's resolution on nuclear phase-out. Finally we find that the probabilities of reporting very high concerns are related to the distance between the respondents' place of residence and the nearest nuclear power station.

  2. Nuclear accidents and policy. Notes on public perception

    Energy Technology Data Exchange (ETDEWEB)

    Richter, Felix; Steenbeck, Malte; Wilhelm, Markus [Hamburg Univ. (Germany). Lehrstuhl fuer Wirtschaftspolitik

    2013-07-01

    Major nuclear accidents as recently in Fukushima set nuclear power plant security at the top of the public agenda. Using data of the German Socio-Economic Panel we analyze the effects of the Fukushima accident and a subsequent government decision on nuclear power phase-out on several measures of subjective perception in Germany. In the light of current political debates about the strategic orientation of this energy turnaround, such an analysis is of particular interest since non-pecuniary gains in measures of subjective perception might provide further aspects to be taken into consideration when evaluating the economic costs of the policy. We find that the Fukushima accident increases the probability to report greater worries about the environment. Furthermore, we find evidence for a decrease in the probability to be very worried about the security of nuclear power plants as well as for an increase in reported levels of subjective well-being following the government's resolution on nuclear phase-out. Finally we find that the probabilities of reporting very high concerns are related to the distance between the respondents' place of residence and the nearest nuclear power station.

  3. Practices and Experience in Stakeholder Involvement for Post-nuclear Emergency Management - Summary of the workshop

    International Nuclear Information System (INIS)

    Anon.

    2011-01-01

    One of the most important aspects of post-accident consequence management is the involvement of stakeholders: in the planning, preparation and execution as well as in sustaining efforts over the long term. Having recognised the significance of stakeholder participation in several International Nuclear Emergency Exercises (INEX), the NEA Committee on Radiation Protection and Public Health (CRPPH) decided to organise the Practices and Experience in Stakeholder Involvement for Post-nuclear Emergency Management Workshop to explore these issues. This summary highlights the key issues discussed during the workshop, which brought together 75 emergency management and communication specialists from 16 countries. In light of the accident at the Fukushima Daiichi nuclear power plant, the experience shared during this workshop will be central to further improving national emergency management arrangements

  4. Noticeable aspects of selecting intervention measures for nuclear accidents

    International Nuclear Information System (INIS)

    Guo Yong; Shi Yuanming

    1993-01-01

    Referring to the experience of intervention measures taken for protecting the public after Chernobyl accident and to recent knowledge of source terms of reactor accidents, the noticeable aspects of selecting of intervention measures for nuclear accidents is discussed

  5. Note nuclear accidents combat

    International Nuclear Information System (INIS)

    1989-01-01

    In this document the starting points are described which underlie the new framework for the nuclear-accident combat in the Netherlands. All the elaboration of this is indicated in main lines. The juridical consequences of the proposed structure are enlightened and the sequel activities are indicated. (H.W.). 6 figs.; 8 tabs

  6. 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)

  7. Consequences and countermeasures in a nuclear power accident: Chernobyl experience.

    Science.gov (United States)

    Kirichenko, Vladimir A; Kirichenko, Alexander V; Werts, Day E

    2012-09-01

    Despite the tragic accidents in Fukushima and Chernobyl, the nuclear power industry will continue to contribute to the production of electric energy worldwide until there are efficient and sustainable alternative sources of energy. The Chernobyl nuclear accident, which occurred 26 years ago in the former Soviet Union, released an immense amount of radioactivity over vast territories of Belarus, Ukraine, and the Russian Federation, extending into northern Europe, and became the most severe accident in the history of the nuclear industry. This disaster was a result of numerous factors including inadequate nuclear power plant design, human errors, and violation of safety measures. The lessons learned from nuclear accidents will continue to strengthen the safety design of new reactor installations, but with more than 400 active nuclear power stations worldwide and 104 reactors in the Unites States, it is essential to reassess fundamental issues related to the Chernobyl experience as it continues to evolve. This article summarizes early and late events of the incident, the impact on thyroid health, and attempts to reduce agricultural radioactive contamination.

  8. The Fukushima nuclear accident: insights on the safety aspects

    Energy Technology Data Exchange (ETDEWEB)

    Thome, Zieli D.; Vellozo, Sergio O., E-mail: zielithome@gmail.com, E-mail: vellozo@cbpf.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Secao de Engenharia Nuclear; Gomes, Rogerio S., E-mail: rogeriog@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Silva, Fernando C., E-mail: fernando@con.ufrj.br [Coordenacao do Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The Fukushima nuclear accident has generated doubts and questions which need to be properly understood and addressed. This scientific attitude became necessary to allow the use of the nuclear technology for electricity generation around the world. The nuclear stakeholders are working to obtain these technical answers for the Fukushima questions. We believe that, such challenges will be, certainly, implemented in the next reactor generation, following the technological evolution. The purpose of this work is to perform a critical analysis of the Fukushima nuclear accident, focusing at the common cause failures produced by tsunami, as well as an analysis of the main redundant systems. This work also assesses the mitigative procedures and the subsequent consequences of such actions, which gave results below expectations to avoid the progression of the accident, discussing the concept of sharing of structures, systems and components at multi-unit nuclear power plants, and its eventual inappropriate use in safety-related devices which can compromise the nuclear safety, as well as its consequent impact on the Fukushima accident scenario. The lessons from Fukushima must be better learned, aiming the development of new procedures and new safety systems. Thus, the nuclear technology could reach a higher evolution level in its safety requirements. This knowledge will establish a conceptual milestone in the safety system design, becoming necessary the review of the current acceptance criteria of safety-related systems. (author)

  9. The Fukushima nuclear accident: insights on the safety aspects

    International Nuclear Information System (INIS)

    Thome, Zieli D.; Vellozo, Sergio O.; Silva, Fernando C.

    2013-01-01

    The Fukushima nuclear accident has generated doubts and questions which need to be properly understood and addressed. This scientific attitude became necessary to allow the use of the nuclear technology for electricity generation around the world. The nuclear stakeholders are working to obtain these technical answers for the Fukushima questions. We believe that, such challenges will be, certainly, implemented in the next reactor generation, following the technological evolution. The purpose of this work is to perform a critical analysis of the Fukushima nuclear accident, focusing at the common cause failures produced by tsunami, as well as an analysis of the main redundant systems. This work also assesses the mitigative procedures and the subsequent consequences of such actions, which gave results below expectations to avoid the progression of the accident, discussing the concept of sharing of structures, systems and components at multi-unit nuclear power plants, and its eventual inappropriate use in safety-related devices which can compromise the nuclear safety, as well as its consequent impact on the Fukushima accident scenario. The lessons from Fukushima must be better learned, aiming the development of new procedures and new safety systems. Thus, the nuclear technology could reach a higher evolution level in its safety requirements. This knowledge will establish a conceptual milestone in the safety system design, becoming necessary the review of the current acceptance criteria of safety-related systems. (author)

  10. The Chernobyl nuclear accident and its consequences

    International Nuclear Information System (INIS)

    1986-01-01

    An AAEC Task Group was set up shortly after the accident at the Chernobyl Nuclear Power Plant to monitor and evaluate initial reports and to assess the implications for Australia. The Task Group issued a preliminary report on 9 May 1986. On 25-29 August 1986, the USSR released details of the accident and its consequences and further information has become available from the Nuclear Energy Agency of OECD and the World Health Organisation. The Task Group now presents a revised report summarising this information and commenting on the consequences from the Australian viewpoint

  11. Report on the accident at the Chernobyl Nuclear Power Station

    International Nuclear Information System (INIS)

    1987-01-01

    This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. The various authors are identified in a footnote to each chapter. An overview of the report is provided. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general

  12. Effects of the Chernobyl accident on public perceptions of nuclear plant accident risks

    International Nuclear Information System (INIS)

    Lindell, M.K.; Perry, R.W.

    1990-01-01

    Assessments of public perceptions of the characteristics of a nuclear power plant accident and affective responses to its likelihood were conducted 5 months before and 1 month after the Chernobyl accident. Analyses of data from 69 residents of southwestern Washington showed significant test-retest correlations for only 10 of 18 variables--accident likelihood, three measures of impact characteristics, three measures of affective reactions, and hazard knowledge by governmental sources. Of these variables, only two had significant changes in mean ratings; frequency of thought and frequency of discussion about a nearby nuclear power plant both increased. While there were significant changes only for two personal consequences (expectations of cancer and genetic effects), both of these decreased. The results of this study indicate that more attention should be given to assessing the stability of risk perceptions over time. Moreover, the data demonstrate that experience with a major accident can actually decrease rather than increase perceptions of threat

  13. 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

  14. Incorporation of severe accidents in the licensing of nuclear power plants

    International Nuclear Information System (INIS)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

    2011-01-01

    Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

  15. Incorporation of severe accidents in the licensing of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz, E-mail: bayout@cnen.gov.b, E-mail: sidney@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN) Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

  16. Report from the Special Committee on Fukushima Nuclear Accident

    International Nuclear Information System (INIS)

    Ozawa, Mamoru

    2012-01-01

    The Special Committee on Fukushima Nuclear Accident was established in April 2011 under the Heat Transfer Society of Japan (HTSJ) and discussed (1) how had evolved heat transfer research in progress of nuclear technology, (2) role of expert group in the area of heat transfer academy and technology and (3) energy prospect in Japan after the Fukushima nuclear accident. This report was described by the chairman of the special committee summarizing one year discussions as (1) background of heat transfer research progress, (2) progression of Fukushima Daiichi Nuclear Power Plant accident, (3) energy problem in Japan after the Fukushima accident and (4) social role of the HTSJ. This HTSJ was a unique, nonprofit association in Japan of the people engaged in heat transfers research or in various engineering aspects related to heat transfer, which meant interdisciplinary or common platform of heat transfer as elementary technologies. Such actual complex problems could be discussed in the HTSJ from an overlooking viewpoint in order for the HTSJ to play a social role. (T. Tanaka)

  17. The biotic sample bank of Chernobyl nuclear accident

    International Nuclear Information System (INIS)

    Li Yu; Min Rui; Cai Jianming

    2006-01-01

    Objective: To built a simple and easy biologic sample bank from irradiated people in nuclear accident, for the long time research of biological effect of low dose ionization radiation on people. Methods: The blood sample is fixed on a piece of filter paper rand sealed up in plastic bottle for keeping, blood sample scribble on glass lice, fixed and dyed as routine clinic examination, and still, reserve a slice of hair of the examined people. Results: Having built a biologic sample bank which from 1162 human body. The samples are come from 958 liquidators of Chernobyl nuclear accident, 46 people in other nuclear accident and 158 people as control groups. It is also having much information details. Conclusions: If the biologic sample bank is combined with the modern bimolecular technique, maybe have much meaningful for the theory and practice of radiobiology. (authors)

  18. Nuclear accidents, consumers' perspectives and demands

    International Nuclear Information System (INIS)

    Alevritou-Goulielmou, H.

    2005-01-01

    The public's reaction to life threatening situations is determined by a variety of factors. In the case of nuclear accidents, the panic experienced by citizens may be reasonably justified. This paper briefly describes the parameters that cause panic reactions from a consumer's point of view and summarizes citizen's demands concerning nuclear crisis management

  19. Severe accident analysis and management in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Golshan, Mina

    2013-01-01

    Within the UK regulatory regime, assessment of risks arising from licensee's activities are expected to cover both normal operations and fault conditions. In order to establish the safety case for fault conditions, fault analysis is expected to cover three forms of analysis: design basis analysis (DBA), probabilistic safety assessment (PSA) and severe accident analysis (SAA). DBA should provide a robust demonstration of the fault tolerance of the engineering design and the effectiveness of the safety measures on a conservative basis. PSA looks at a wider range of fault sequences (on a best estimate basis) including those excluded from the DBA. SAA considers significant but unlikely accidents and provides information on their progression and consequences, within the facility, on the site and off site. The assessment of severe accidents is not limited to nuclear power plants and is expected to be carried out for all plant states where the identified dose targets could be exceeded. This paper sets out the UK nuclear regulatory expectation on what constitutes a severe accident, irrespective of the type of facility, and describes characteristics of severe accidents focusing on nuclear fuel cycle facilities. Key rules in assessment of severe accidents as well as the relationship to other fault analysis techniques are discussed. The role of SAA in informing accident management strategies and offsite emergency plans is covered. The paper also presents generic examples of scenarios that could lead to severe accidents in a range of nuclear fuel cycle facilities. (authors)

  20. The accident at the Harrisburg nuclear reactor - Interim conclusions

    International Nuclear Information System (INIS)

    Yiftah, S.

    1979-07-01

    This work describes the first minutes, first day and first week following the Three Mile Island accident. It shows the failures that occurred and the lessons which should be derived. It is pointed out that the doses of radiation that escaped from the TMI plant were at no time large enough to have had any effect on the 2 million people living on a radius of 80 km from the plant. Although no casualties occurred the Harrisburg accident will create an impulse for a new study and understanding of the nuclear plant safety and might serve as a live safety laboratory. After the TMI accident nuclear plants are already safer, one of the conclusions being that a new planning of the operation room is required, with the operators acquiring a better understanding of what is going on during a nuclear reactor accident. (B.G.)

  1. Soviet medical response to the Chernobyl nuclear accident

    International Nuclear Information System (INIS)

    Linnemann, R.E.

    1987-01-01

    The nuclear accident at Chernobyl was the worst in the history of nuclear power. It tested the organized medical response to mass radiation casualties. This article reviews the Soviet response as reported at the 1986 postaccident review meeting in Vienna and as determined from interviews. The Soviets used three levels of care: rescue and first aid at the plant site; emergency treatment at regional hospitals; and definitive evaluation and treatment in Moscow. Diagnosis, triage, patient disposition, attendant exposure, and preventive actions are detailed. The United States would be well advised to organize its resources definitively to cope with future nonmilitary nuclear accidents

  2. Chernobyl and the problem of international obligations regarding nuclear accidents

    International Nuclear Information System (INIS)

    Strohl, P.

    1988-01-01

    This paper analyses the way nuclear law was put to the test by the Chernobyl accident - in particular international nuclear law - so as to propose a train of thought which might contribute to adopting and revising the legal system presently in force or even new orientations. It deals only with that part of nuclear law which concerns accidents and their consequences (NEA) [fr

  3. 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

  4. Nuclear installations abroad the accident risks and their potential consequences

    Energy Technology Data Exchange (ETDEWEB)

    Turvey, F J [Radiological Protection Inst. of Ireland (Ireland)

    1996-10-01

    This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of `tolerable` risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid.

  5. Nuclear installations abroad the accident risks and their potential consequences

    International Nuclear Information System (INIS)

    Turvey, F.J.

    1996-01-01

    This paper endeavors to assess the threat to Ireland from severe accidents at civil nuclear installations. Among the various types of nuclear installations worldwide, reactors and reprocessing plants are considered to be the most threatening and so the paper focuses on these. The threat is assumed to be a function of the risk of severe accidents at the above types of installations and the probability of unfavourable weather conditions carrying the radioactive releases to Ireland. Although nuclear installations designed in eastern Europe and Asia are less safe than others, the greatest threat to Ireland arises from nearby installations in the UK. The difficulty of measuring the probabilities and consequences of severe nuclear accidents at nuclear installations in general is explained. In the case of the UK installations, this difficulty is overcome to some degree by using values of 'tolerable' risk adopted by the national nuclear regulator to define the radiotoxic releases from nuclear accidents. These are used as input to atmospheric dispersion models in which unfavourable weather conditions for Ireland are assumed and radiation doses are calculated to members of the Irish public. No countermeasures, such as sheltering, are assumed. In the worst cast scenario no deaths would be expected in Ireland in the immediate aftermath of the accident however, an increase in cancers over a period of 25 years or so would be expected assuming present-day models for the effect of low level radiation are valid

  6. Relative evaluation on decommissioning accident scenarios of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jei-Kwon; Hyun, Dong-Jun; Kim, Geun-Ho; Kim, Tae-Hyoung; Jo, Kyung-Hwa; Seo, Jae-Seok; Jeong, Seong-Young; Lee, Jung-Jun

    2012-01-01

    Highlights: ► This paper suggests relative importance on accident scenarios during decommissioning of nuclear facilities. ► The importance of scenarios can be performed by using AHP and Sugeno fuzzy method. ► The AHP and Sugeno fuzzy method guarantee reliability of the importance evaluation. -- Abstract: This paper suggests the evaluation method of relative importance on accident scenarios during decommissioning of nuclear facilities. The evaluation method consists of AHP method and Sugeno fuzzy integral method. This method will guarantee the reliability of relative importance evaluation for decommissioning accident scenarios.

  7. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-10-01

    The Reactor Safety Study was sponsored by the U. S. Atomic Energy Commission to estimate the public risks that could be involved in potential accidents in commercial nuclear power plants of the type now in use. It was performed under the independent direction of Professor Norman C. Rasmussen of the Massachusetts Institute of Technology. The risks had to be estimated, rather than measured, because although there are about 50 such plants now operating, there have been no nuclear accidents to date resulting in significant releases of radioactivity in U.S. commercial nuclear power plants. The objective of the study was to make a realistic estimate of these risks and, to provide perspective, to compare them with non-nuclear risks to which our society and its individuals are already exposed. This information may be of help in determining the future reliance by society on nuclear power as a source of electricity. The results from this study suggest that the risks to the public from potential accidents in nuclear power plants are comparatively small.

  8. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary

    International Nuclear Information System (INIS)

    1975-10-01

    The Reactor Safety Study was sponsored by the U. S. Atomic Energy Commission to estimate the public risks that could be involved in potential accidents in commercial nuclear power plants of the type now in use. It was performed under the independent direction of Professor Norman C. Rasmussen of the Massachusetts Institute of Technology. The risks had to be estimated, rather than measured, because although there are about 50 such plants now operating, there have been no nuclear accidents to date resulting in significant releases of radioactivity in U.S. commercial nuclear power plants. The objective of the study was to make a realistic estimate of these risks and, to provide perspective, to compare them with non-nuclear risks to which our society and its individuals are already exposed. This information may be of help in determining the future reliance by society on nuclear power as a source of electricity. The results from this study suggest that the risks to the public from potential accidents in nuclear power plants are comparatively small

  9. Response to the accident at TEPCO's Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Nei, Hisanori

    2012-01-01

    This article was reading from the author's plenary lecture at the thermal and nuclear power generation convention 2011, which was summary of the author edited report of Japanese government to IAEA ministerial conference on nuclear safety. The article consisted of (1) outlines of occurrence and development of the accident at TEPCO's Fukushima Daiichi Nuclear Power Plants (NPPs), (2) comparison of Fukushima Daiichi NPPs with other NPPs (Fukushima Daini, Onagawa and Tokai Daini NPPs), (3) major countermeasures to settle the situation regarding the accident, (4) comprehensive safety evaluation of other NPPs as response to the accident and (5) lessons learned from the accident so far. It was highly important to ensure power supplies and robust cooling functions of reactors, pressure containment vessels and spent fuel pools. 28 lessons were categorized into five groups such as (1) strengthen preventive measures against a severe accident, (2) enhancement of response measures against severe accidents, (3) enhancement of nuclear emergency responses, (4) reinforcement of safety infrastructure and (5) thoroughness of safety culture. (T. Tanaka)

  10. Systematic approach for assessment of accident risks in chemical and nuclear processing

    International Nuclear Information System (INIS)

    Senne Junior, Murillo

    2003-07-01

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of systematizing

  11. Effects of the Fukushima Daiichi nuclear accident on goshawk reproduction

    Science.gov (United States)

    Murase, Kaori; Murase, Joe; Horie, Reiko; Endo, Koichi

    2015-01-01

    Although the influence of nuclear accidents on the reproduction of top predators has not been investigated, it is important that we identify the effects of such accidents because humans are also top predators. We conducted field observation for 22 years and analysed the reproductive performance of the goshawk (Accipiter gentilis fujiyamae), a top avian predator in the North Kanto area of Japan, before and after the accidents at the Fukushima Daiichi nuclear power plant that occurred in 2011. The reproductive performance declined markedly compared with the pre-accident years and progressively decreased for the three post-accident study years. Moreover, it was suggested that these declines were primarily caused by an increase in the air dose rate of radio-active contaminants measured under the nests caused by the nuclear accidents, rather than by other factors. We consider the trends in the changes of the reproductive success rates and suggest that internal exposure may play an important role in the reproductive performance of the goshawk, as well as external exposure. PMID:25802117

  12. Radiation protection issues on preparedness and response for a severe nuclear accident: experiences of the Fukushima accident.

    Science.gov (United States)

    Homma, T; Takahara, S; Kimura, M; Kinase, S

    2015-06-01

    Radiation protection issues on preparedness and response for a severe nuclear accident are discussed in this paper based on the experiences following the accident at Fukushima Daiichi nuclear power plant. The criteria for use in nuclear emergencies in the Japanese emergency preparedness guide were based on the recommendations of International Commission of Radiological Protection (ICRP) Publications 60 and 63. Although the decision-making process for implementing protective actions relied heavily on computer-based predictive models prior to the accident, urgent protective actions, such as evacuation and sheltering, were implemented effectively based on the plant conditions. As there were no recommendations and criteria for long-term protective actions in the emergency preparedness guide, the recommendations of ICRP Publications 103, 109, and 111 were taken into consideration in determining the temporary relocation of inhabitants of heavily contaminated areas. These recommendations were very useful in deciding the emergency protective actions to take in the early stages of the Fukushima accident. However, some suggestions have been made for improving emergency preparedness and response in the early stages of a severe nuclear accident. © The Chartered Institution of Building Services Engineers 2014.

  13. Compensation for damages in case of a nuclear accident; L'indemnisation des prejudices en cas d'accident nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Leger, M. [CEA Saclay, 91 - Gif sur Yvette (France)

    2011-01-15

    This article presents the system of compensation for damages in case of a nuclear accident. This system of civil liability for nuclear damage, as a specific regime, departs on several points from the common rules of civil liability, in order to provide an adequate and equitable compensation for the damages suffered by the victims of nuclear accidents. The French system of civil liability for nuclear damage results from two International Conventions integrated in French law (Paris convention 1960 and Brussels convention 1963) and the French law of 1968, October 30 on civil liability in the area of nuclear energy. These texts define the conditions under which a nuclear operator could be held liable in case of a nuclear accident. The protocols to amend the Paris and Brussels Conventions of 2004, not yet come into force, are also presented. They ensure that increased resources are available to compensate a greater number of victims of a nuclear accident. (author)

  14. The Fukushima nuclear accident and its effect on global energy security

    International Nuclear Information System (INIS)

    Hayashi, Masatsugu; Hughes, Larry

    2013-01-01

    The March 2011 nuclear accident at the Fukushima Daiichi nuclear power station affected both short- and long-term energy-security in Japan, resulting in crisis-driven, ad hoc energy policy and, because of the decision to shutter all nuclear reactors, increased the country’s demand for fossil fuels, primarily natural gas. However, the effects of the accident on energy security were not restricted to Japan; for example, the worldwide availability and affordability of liquefied natural gas were affected by Japan’s increased demand; while the accident itself resulted in the loss of public acceptability of nuclear power and led countries, such as Germany and Italy, to immediately shut down some of the nuclear reactors or abandon plans to build new ones. This paper examines some of the short-term effects on global energy security following the accident at Fukushima, focusing on the main replacement fuel, liquefied natural gas. It shows, amongst other things, that the accident increased investment in liquefied natural gas projects around the world. The paper shows that despite Fukushima contributing to nuclear power’s loss of acceptability in most developed countries, it is still seen as an essential way of improving energy security in many countries and, despite what its critics may say, will probably continue to be used as a significant source of low-carbon electricity. - Highlights: ► Japan’s demands for fossil fuels raised the price of LNG and low-sulfur crudes. ► The accident affected the global price of uranium and producer share prices. ► The accident accelerated foreign-direct investment in LNG projects worldwide. ► The change in public perception toward nuclear power was relatively limited. ► A radical shift in global nuclear policy seems to be unrealistic after Fukushima

  15. Planning for large-scale accidents: learning from the Three Mile Island accident

    International Nuclear Information System (INIS)

    Fischer, D.W.

    1981-01-01

    Decision-making issues raised at the Three Mile Island nuclear accident in Pennsylvania are explored. The organizations involved, their interconnections, and decisions are described. The underlying issues bearing on allocation of effort to pre-accident planning and actual accident responses are also noted. Finally, a framework from this effort is used for guiding the planning of operations for future accidents. (author)

  16. Accidents with nuclear power plants, ch. 11

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A recalculation of the consequences of nuclear power plant accidents is presented taking into account different parameters or different quantities than those usually accepted. A case study of a nuclear power plant planned for the Eems-river estuary in the Netherlands is presented

  17. Supporting system in emergency response plan for nuclear material transport accidents

    International Nuclear Information System (INIS)

    Nakagome, Y.; Aoki, S.

    1993-01-01

    As aiming to provide the detailed information concerning nuclear material transport accidents and to supply it to the concerned organizations by an online computer, the Emergency Response Supporting System has been constructed in the Nuclear Safety Technology Center, Japan. The system consists of four subsystems and four data bases. By inputting initial information such as name of package and date of accident, one can obtain the appropriate initial response procedures and related information for the accident immediately. The system must be useful for protecting the public safety from nuclear material transport accidents. But, it is not expected that the system shall be used in future. (J.P.N.)

  18. Graphical representation of nuclear incidents/accidents by associating network in nuclear technical communication

    International Nuclear Information System (INIS)

    Hibino, Aiko; Niwa, Yuji

    2008-01-01

    Nuclear Information Archives (NUCIA) is a service for information disclosure toward the public on nuclear power plants in Japan. This paper focuses on an experience of how information stored in the NUCIA database is processed for information sharing by a 'sociotechnical interface,' the interface to the general public. Information on nuclear accidents was analyzed by market basket analysis and mapped to some graphical representation in the website for comprehension. The resultant data obtained by questionnaire survey suggests that this graphical conversion is effective for letting the public understand nuclear accidents. In this sense, this attempt gives significant hints of 'how technical communication to the public' should be. (author)

  19. Nuclear safety in light water reactors severe accident phenomenology

    CERN Document Server

    Sehgal, Bal Raj

    2011-01-01

    This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents to teach nuclear professionals

  20. 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)

  1. Including severe accidents in the design basis of nuclear power plants: An organizational factors perspective after the Fukushima accident

    International Nuclear Information System (INIS)

    Alvarenga, M.A.B.; Frutuoso e Melo, P.F.

    2015-01-01

    Highlights: • The Fukushima accident was man-made and not caused by natural phenomena. • Vulnerabilities were known by regulator and licensee but measures were not taken. • There was lack of independence and transparency of the regulatory body. • Laws and regulations have not been updated to international standards. • Organizational failures have played an important role in the Fukushima accident. - Abstract: The Fukushima accident was clearly an accident made by humans and not caused by natural phenomena as was initially thought. Vulnerabilities were known by both regulators and operator but they postponed measures. The emergency plan was not effective in protecting the public, because the involved parties were not sufficiently prepared to make the right decisions. The shortcomings and faults mentioned above resulted from the lack of independence and transparency of the regulatory body. Even laws and regulations, and technical standards, have not been upgraded to international standards. Regulators have not defined requirements and left for the operator to decide what would be more appropriate. In this aspect, there was clearly a lack of independence between these bodies and operator’s lobby power. The above situation raised the question of urgent updating of institutions, in particular those responsible for nuclear safety. The above evidences show that several nuclear safety principles were not followed. This paper intends to highlight some existing safety criteria that were developed from the operational experience of the severe accidents that occurred at TMI and Chernobyl that should be incorporated in the design of new nuclear power plants and to provide appropriate design changes (backfittings) for reactors that belong to the previous generation prior to the occurrence of these accidents, through the study of design vulnerabilities. Furthermore, the main criteria that define an effective regulatory agency are also discussed. Although these

  2. Development of Northeast Asia Nuclear Power Plant Accident Simulator.

    Science.gov (United States)

    Kim, Juyub; Kim, Juyoul; Po, Li-Chi Cliff

    2017-06-15

    A conclusion from the lessons learned after the March 2011 Fukushima Daiichi accident was that Korea needs a tool to estimate consequences from a major accident that could occur at a nuclear power plant located in a neighboring country. This paper describes a suite of computer-based codes to be used by Korea's nuclear emergency response staff for training and potentially operational support in Korea's national emergency preparedness and response program. The systems of codes, Northeast Asia Nuclear Accident Simulator (NANAS), consist of three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. To quickly assess potential doses to the public in Korea, NANAS includes specific reactor data from the nuclear power plants in China, Japan and Taiwan. The completed simulator is demonstrated using data for a hypothetical release. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  3. 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

  4. Trend of nuclear power development in main countries and perspective of nuclear industry after the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Murakami, Tomoko

    2011-01-01

    Fukushima Daiichi Accident occurred in March 11, 2011 was of highest interest in the world and had been reported worldwide from relevant Japanese organizations almost in real time just after happened. This article overviewed five month's response of government and energy related organization of each country and international agency and summarized effects of the accident on nuclear power in energy policy of each country as well as perspective of nuclear industry responded to change of market trend. After the accident, basic policy to regard nuclear power as important was maintained with enhancing reactor safety against extreme events in countries choosing nuclear power as important and requisite energy and there appeared such a trend of nuclear power phase-out in countries promoting nuclear power prudently. Choice of nuclear power would be decided on energy state of each country and was not affected before and after the accident. Trend of nuclear business was closely related with that of market and no fundamental change was observed although some industries with revenue from business in nuclear power phase-out country or cancelled project after the accident were obliged to be affected. (T. Tanaka)

  5. Nuclear industry after the Fukushima accident

    International Nuclear Information System (INIS)

    Branche, Thomas; Billes-Garabedian, Laurent; Salha, Bernard; Behar, Christophe; Dupuis, Marie-Claude; Labalette, Thibaud; Lagarde, Dominique; Planchais, Bernard; West, Jean-Pierre; Stubler, Jerome; Lancia, Bruno; Machenaud, Herve; Einaudi, Andre; Anglaret, Philippe; Brachet, Yves; Bonnave, Philippe; Knoche, Philippe; Gasquet, Denis

    2013-01-01

    This special dossier about the situation of nuclear industry two years after the Fukushima accident comprises 15 contributions dealing with: the nuclear industry two years after the Fukushima accident (Bernard Salha); a low-carbon electricity at a reasonable cost (Christophe Behar); nuclear engineering has to gain even more efficiency (Thomas Branche); how to dispose off the most radioactive wastes (Marie-Claude Dupuis, Thibaud Labalette); ensuring the continuation for more than 40 years onward (Denis Gasquet); developing and investing in the future (Philippe Knoche); more than just signing contracts (Dominique Lagarde); immersed power plants, an innovative concept (Bernard Planchais); R and D as a source of innovation for safety and performances (Jean-Pierre West); dismantlement, a very long term market (Jerome Stubler, Bruno Lancia); a reference industrial model (Herve Machenaud); recruiting and training (Andre Einaudi); a diversity of modern reactors and a world market in rebirth (Philippe Anglaret); an industrial revolution is necessary (Yves Brachet); contracts adapted to sensible works (Philippe Bonnave)

  6. Buses involved in fatal accidents codebook 2008.

    Science.gov (United States)

    2011-03-01

    This report provides documentation for UMTRIs file of Buses Involved in Fatal Accidents (BIFA), 2008, : including distributions of the code values for each variable in the file. The 2008 BIFA file is a census of all : buses involved in a fatal acc...

  7. Buses involved in fatal accidents codebook 2007.

    Science.gov (United States)

    2009-12-01

    This report provides documentation for UMTRIs file of Buses Involved in Fatal Accidents (BIFA), 2007, : including distributions of the code values for each variable in the file. The 2007 BIFA file is a census of all : buses involved in a fatal acc...

  8. Report of the Fukushima nuclear accident by the National Academy of Science. Lessons learned from the Fukushima nuclear accident for improving safety of U.S. nuclear plants

    International Nuclear Information System (INIS)

    Nariai, Hideki

    2014-01-01

    U.S. National Academy of Science investigated the accident at the Fukushima Daiichi nuclear plant initiated by the Great East Japan Earthquake for two years and published a draft report in July 24, 2014. Investigation results were summarized in nine new findings and made ten recommendations in a wide horizon; (1) hardware countermeasures against severe accidents and training of operators, (2) upgrade of risk assessment capability for beyond design basis accident, (3) incorporation of new information about hazards in safety regulations, (4) needed improvement of off-site emergency preparedness, and (5) improvements of nuclear safety culture. New information about hazards related with tsunami assessment, new risk assessment for beyond design basis accident, advice of foreigner resident evacuations, regulatory capture, and safety culture and regulator's specialty were discussed as Japanese issues. (T. Tanaka)

  9. Radionuclide release rate inversion of nuclear accidents in nuclear facility based on Kalman filter

    International Nuclear Information System (INIS)

    Tang Xiuhuan; Bao Lihong; Li Hua; Wan Junsheng

    2014-01-01

    The rapidly and continually back-calculating source term is important for nuclear emergency response. The Gaussian multi-puff atmospheric dispersion model was used to produce regional environment monitoring data virtually, and then a Kalman filter was designed to inverse radionuclide release rate of nuclear accidents in nuclear facility and the release rate tracking in real time was achieved. The results show that the Kalman filter combined with Gaussian multi-puff atmospheric dispersion model can successfully track the virtually stable, linear or nonlinear release rate after being iterated about 10 times. The standard error of inversion results increases with the true value. Meanwhile extended Kalman filter cannot inverse the height parameter of accident release as interceptive error is too large to converge. Kalman filter constructed from environment monitoring data and Gaussian multi-puff atmospheric dispersion model can be applied to source inversion in nuclear accident which is characterized by static height and position, short and continual release in nuclear facility. Hence it turns out to be an alternative source inversion method in nuclear emergency response. (authors)

  10. Impacts of the Fukushima Daiichi Accident on Nuclear Development Policies

    International Nuclear Information System (INIS)

    Vance, Robert; Henderson, David; ); Moore, Laurie

    2017-01-01

    The Fukushima Daiichi nuclear power plant accident has had an impact on the development of nuclear power around the world. While the accident was followed by thorough technical assessments of the safety of all operating nuclear power plants, and a general increase in safety requirements has been observed worldwide, national policy responses have been more varied. These responses have ranged from countries phasing out or accelerating decisions to phase out nuclear energy to countries reducing their reliance on nuclear power or on the contrary continuing to pursue or expand their nuclear power programs. This study examines changes to policies, and plans and attempts to distinguish the impact of the Fukushima Daiichi accident from other factors that have affected policy-making in relation to nuclear energy, in particular electricity market economics, financing challenges and competition from other sources (gas, coal and renewables). It also examines changes over time to long-term, quantitative country projections, which reveal interesting trends on the possible role of nuclear energy in future energy systems. (authors)

  11. 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

  12. Consideration of Command and Control Performance during Accident Management Process at the Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed, Nisrene M. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Kim, Sok Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The accident at the Fukushima Daiichi nuclear power plants shifted the nuclear safety paradigm from risk management to on-site management capability during a severe accident. The kernel of on-site management capability during an accident at a nuclear power plant is situation awareness and agility of command and control. However, little consideration has been given to accident management. After the events of September 11, 2001 and the catastrophic Fukushima nuclear disaster, agility of command and control has emerged as a significant element for effective and efficient accident management, with many studies emphasizing accident management strategies, particularly man-machine interface, which is considered a key role in ensuring nuclear power plant safety during severe accident conditions. This paper proposes a conceptual model for evaluating command and control performance during the accident management process at a nuclear power plant. Communication and information processing while responding to an accident is one of the key issues needed to mitigate the accident. This model will give guidelines for accurate and fast communication response during accident conditions.

  13. Crisis, criticism, change: Regulatory reform in the wake of nuclear accidents

    International Nuclear Information System (INIS)

    Sexton, Kimberly A.; )

    2015-01-01

    Accidents are a forcing function for change in the nuclear industry. While these events can shed light on needed technical safety reforms, they can also shine a light on needed regulatory system reforms. The TEPCO Fukushima Daiichi nuclear power plant (NPP) accident in Japan is the most recent example of this phenomenon, but it is not the only one. In the wake of the three major accidents that have occurred in the nuclear power industry - Three Mile Island (TMI) in the United States; Chernobyl in Ukraine, in the former Soviet Union; and the Fukushima Daiichi NPP accident in Japan - a commission or committee of experts issued a report (or reports) with harsh criticism of the countries' regulatory system. And each of these accidents prompted changes in the respective regulatory systems. In looking at these responses, however, one must ask if this crisis, criticism, change approach is working and whether regulatory bodies around the world should instead undertake their own systematic reviews, un-prompted by crisis, to better ensure safety. This article will attempt to analyse the issue of regulatory reform in the wake of nuclear accidents by first providing a background in nuclear regulatory systems, looking to international and national legal frameworks. Next, the article will detail a cross-section of current regulatory systems around the world. Following that, the article will analyse the before and after of the regulatory systems in the United States, the Soviet Union and Japan in relation to the TMI, Chernobyl and Fukushima accidents. Finally, taking all this together, the article will address some of the international and national efforts to define exactly what makes a good regulator and provide conclusions on regulatory reform in the wake of nuclear accidents. (author)

  14. Agricultural implications of the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Nakanishi, Tomoko M.

    2016-01-01

    More than 4 years has passed since the accident at the Fukushima Nuclear Power Plant. Immediately after the accident, 40 to 50 academic staff of the Graduate School of Agricultural and Life Sciences at the University of Tokyo created an independent team to monitor the behavior of the radioactive materials in the field and their effects on agricultural farm lands, forests, rivers, animals, etc. When the radioactive nuclides from the nuclear power plant fell, they were instantly adsorbed at the site where they first touched; consequently, the fallout was found as scattered spots on the surface of anything that was exposed to the air at the time of the accident. The adsorption has become stronger over time, so the radioactive nuclides are now difficult to remove. The findings of our study regarding the wide range of effects on agricultural fields are summarized in this report

  15. [Labor accidents involving the eyes: assessment of occupational risks involving nursing workers].

    Science.gov (United States)

    de Almeida, Cristiana Brasil; Pagliuca, Lorita Marlena Freitag; Leite, Ana Lourdes Almeida e Silva

    2005-01-01

    The study aimed at identifying nursing workers who were victims of eye accidents and the type of accident; describing the measures taken and proposing Health Education methods. A descriptive and exploratory study was carried out at a public maternity hospital from September 2002 to January 2003. Data were collected through direct observation of the environment and interviews with workers. Subjects were ten professionals (one nurse, two technicians and seven nursing auxiliaries) who were victims of work accidents involving the eye. The accidents were grouped according to the type of material that caused the trauma: chemical substances (4), medication (3), mechanical trauma (1), scalp (1) and urine (1). The results reveal that hospital workers are vulnerable to labor accidents because the environment presents biological, chemical and physical risks. An important step to prevent the occurrence of new accidents would be the prevention of human mistakes through permanent training and the use of protection glasses.

  16. Nuclear power plant safety - the risk of accidents

    International Nuclear Information System (INIS)

    Higson, D.; Crancher, D.W.

    1975-08-01

    Although it is physically impossible for any nuclear plant to explode like an atom bomb, an accidental release of radioactive material into the environment is conceivable. Three factors reduce the probability of such releases, in dangerous quantities, to an extremely low level. Firstly, there are many safety features built into the plant including a leaktight containment building to prevent the escape of such material. Secondly, the quality of engineering and standards used are far more demanding than in conventional power engineering. Thirdly, strict government licensing and regulatory control is enforced at all phases from design through construction to operation. No member of the general public is known to have been injured or died as a result of any accident to a commercial nuclear power plant. Ten workers have died as a result of over-exposure to radiation from experimental reactors and laboratory work connected with the development of nuclear plant since 1945. Because of this excellent safety record the risk of serious accidents can only be estimated. On the basis of such estimates, the chance of an accident in a nuclear power reactor which could cause a detectable increase in the incidence of radiation-induced illnesses would be less than one chance in a million per year. In a typical highly industrialised society, such as the USA, the estimated risk of an individual being killed by such accidents, from one hundred operating reactors, is no greater than one chance in sixteen million per year. There are undoubtedly risks from reactor accidents but estimates of these risks show that they are considerably less than from other activities which are accepted by society. (author)

  17. Real-time assessment of radiation burden of the population in the vicinity of nuclear power plants during radiation accidents

    International Nuclear Information System (INIS)

    Stubna, M.

    1986-01-01

    The method is presented of real-time calculation of the radiation situation (dose equivalents) in the environs of a nuclear power plant in case of an accident involving the release of radioactive substances into the atmosphere, this for the potentially most significant exposure paths in the initial and medium stages of the accident. The method allows to take into consideration the time dependence of the rate of radioactive substance release from the nuclear power plant and to assess the development in space and time of the radiation situation in the environs of the nuclear power plant. The use of the method is illustrated by an example of the calculation of the development of the radiation situation for model accidents of a hypothetical PWR with containment. (author)

  18. 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

  19. Analytical measurements of fission products during a severe nuclear accident

    Science.gov (United States)

    Doizi, D.; Reymond la Ruinaz, S.; Haykal, I.; Manceron, L.; Perrin, A.; Boudon, V.; Vander Auwera, J.; tchana, F. Kwabia; Faye, M.

    2018-01-01

    The Fukushima accident emphasized the fact that ways to monitor in real time the evolution of a nuclear reactor during a severe accident remain to be developed. No fission products were monitored during twelve days; only dose rates were measured, which is not sufficient to carry out an online diagnosis of the event. The first measurements were announced with little reliability for low volatile fission products. In order to improve the safety of nuclear plants and minimize the industrial, ecological and health consequences of a severe accident, it is necessary to develop new reliable measurement systems, operating at the earliest and closest to the emission source of fission products. Through the French program ANR « Projet d'Investissement d'Avenir », the aim of the DECA-PF project (diagnosis of core degradation from fission products measurements) is to monitor in real time the release of the major fission products (krypton, xenon, gaseous forms of iodine and ruthenium) outside the nuclear reactor containment. These products are released at different times during a nuclear accident and at different states of the nuclear core degradation. Thus, monitoring these fission products gives information on the situation inside the containment and helps to apply the Severe Accident Management procedures. Analytical techniques have been proposed and evaluated. The results are discussed here.

  20. Analytical measurements of fission products during a severe nuclear accident

    Directory of Open Access Journals (Sweden)

    Doizi D.

    2018-01-01

    Full Text Available The Fukushima accident emphasized the fact that ways to monitor in real time the evolution of a nuclear reactor during a severe accident remain to be developed. No fission products were monitored during twelve days; only dose rates were measured, which is not sufficient to carry out an online diagnosis of the event. The first measurements were announced with little reliability for low volatile fission products. In order to improve the safety of nuclear plants and minimize the industrial, ecological and health consequences of a severe accident, it is necessary to develop new reliable measurement systems, operating at the earliest and closest to the emission source of fission products. Through the French program ANR « Projet d’Investissement d’Avenir », the aim of the DECA-PF project (diagnosis of core degradation from fission products measurements is to monitor in real time the release of the major fission products (krypton, xenon, gaseous forms of iodine and ruthenium outside the nuclear reactor containment. These products are released at different times during a nuclear accident and at different states of the nuclear core degradation. Thus, monitoring these fission products gives information on the situation inside the containment and helps to apply the Severe Accident Management procedures. Analytical techniques have been proposed and evaluated. The results are discussed here.

  1. Experience in the analysis of accidents and incidents involving the transport of radioactive materials

    International Nuclear Information System (INIS)

    Warner-Jones, S.M.; Hughes, J.S.; Shaw, K.B.

    2002-01-01

    Some half a million packages containing radioactive materials are transported to, from and within the UK annually. Accidents and incidents involving these shipments are rare. However, there is always the potential for such an event, which could lead to a release of the contents of a package or an increase in radiation level caused by damaged shielding. These events could result in radiological consequences for transport workers. As transport occurs in the public environment, such events could also lead to radiation exposures of members of the public. The UK Department for Transport (DfT), together with the Health and Safety Executive (HSE) have supported, for almost 20 years, work to compile, analyse and report on accidents and incidents that occur during the transport of radioactive materials. Annual reports on these events have been produced for twelve years. The details of these events are recorded in the Radioactive Materials Transport Event Database (RAMTED) maintained by the National Radiological Protection Board on behalf of the DfT and HSE. Information on accidents and incidents dates back to 1958. RAMTED currently includes information of 708 accidents and incidents, covering the period 1958 to 2000. This paper presents a summary of the data covering this period, identifying trends and lessons learned together with a discussion of some examples. It was found that, historically, the most significant exposures were received as a result of accidents involving the transport of industrial radiography sources. However, the frequency and severity of these events has decreased considerably in the later years of this study due to improvements in training, awareness and equipment. The International Atomic Energy Agency and the Nuclear Energy Agency, have established the international nuclear event scale (INES), which is described in detail in a users' guide. The INES has been revised to fully include transport events, and the information in RAMTED has been reviewed

  2. On the Impact to the Human Health from the Fukushima Nuclear Accident

    International Nuclear Information System (INIS)

    Simic, Zdenko

    2014-01-01

    Nuclear energy has long controversial history with hypes of utopian promises and doom fears; from 'electricity too cheap to meter' to the certain destruction of the world. Three major nuclear accidents (TMI, Chernobyl and Fukushima) helped only to strengthen mostly negative perception of the public. After TMI and Chernobyl understanding of the nuclear accidents impact to human health has considerably improved. This has helped to reduce uncertainty about risk estimates, but too little was achieved regarding the communication of how absolutely and relatively this risk is in fact small. Now with Fukushima there is new potential for even better understanding of the realistic scope of the total nuclear accident impact. Based on the experience with previous accidents obviously there are significant obstacles to achieve that. This paper is presenting current understanding of the impact on the human health from the Fukushima nuclear accident. Focus is given also to the uncertainties, perception, and relative prospective to other non radiation related risks. It is clear from data and assessments that immediate radiation related risk as well as expected long term health impact is even with conservative approach negligible and that it will be most probable impossible to determine it with health monitoring and epidemiological study. However, because of existing perception, lack of thrust and better approach many practical reactions are going to perpetuate negative picture, about radiation and nuclear energy, and perhaps cause some additional psychosocial risk. It is troubling that this induced risk is substantial and it could have been mainly prevented by timely applying experience form previous major accidents thru education, communication and transparency. Because of historical and local circumstance, communication difficulties and lack of sufficient understanding of uncertainties and magnitudes it seems that Fukushima nuclear accident will not be much better case

  3. Human Factors in Nuclear Reactor Accidents

    International Nuclear Information System (INIS)

    Mustafa, M.E.

    2016-01-01

    While many people would blame nature for the disaster of the “Fukushima Daiichi” accident, experts considered this accident to be also a human-induced disaster. This confirmed the importance of human errors which have been getting a growing interest in the nuclear field after the Three Mile Island accident. Personnel play an important role in design, operation, maintenance, planning, and management. The interface between machine and man is known as a human factor. In the present work, the human factors that have to be considered were discussed. The effect of the control room configuration and equipment design effect on the human behavior was also discussed. Precise reviewing of person’s qualifications and experience was focused. Insufficient training has been a major cause of human error in the nuclear field. The effective training issues were introduced. Avoiding complicated operational processes and non responsive management systems was stressed. Distinguishing between the procedures for normal and emergency operations was emphasised. It was stated that human error during maintenance and testing activities could cause a serious accident. This is because safety systems do not cover much more risk probabilities in the maintenance and testing activities like they do in the normal operation. In nuclear industry, the need for a classification and identification of human errors has been well recognised. As a result of this, human reliability must be assessed. These errors are analyzed by a probabilistic safety assessment which deals with errors in reading, listening and implementing procedures but not with cognitive errors. Much efforts must be accomplished to consider cognitive errors in the probabilistic safety assessment. The ways of collecting human factor data were surveyed. The methods for identifying safe designs, helping decision makers to predict how proposed or current policies will affect safety, and comprehensive understanding of the relationship

  4. The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt

    International Nuclear Information System (INIS)

    2013-01-01

    Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, all NEA member countries took early action to ensure and confirm the continued safety of their nuclear power plants and the protection of the public. After these preliminary safety reviews, all countries with nuclear facilities carried out comprehensive safety reviews, often referred to as 'stress tests', which reassessed safety margins of nuclear facilities with a primary focus on challenges related to conditions experienced at the Fukushima Daiichi nuclear power plant, for example extreme external events and the loss of safety functions, or capabilities to cope with severe accidents. As appropriate, improvements are being made to safety and emergency response systems to ensure that nuclear power plants are capable of withstanding events that lead to loss of electrical power and/or cooling capability. In the weeks following the accident, the NEA immediately began establishing expert groups in the nuclear safety and radiological protection areas, as well as contributing to information exchange with the Japanese authorities and other international organisations. It promptly provided a forum for high-level decision makers and regulators within the G8-G20 frameworks. The NEA actions taken at the international level in response to the accident have been carried out primarily by the three NEA standing technical committees concerned with nuclear and radiation safety issues - the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH) - under the leadership of the CNRA. More than two years following the accident, the NEA continues to assist the Japanese authorities in dealing with their nuclear safety and recovery efforts as well as to facilitate international co-operation on nuclear safety and radiological protection matters. It is strongly supporting the establishment of

  5. A description of nuclear reactor accidents and their consequences

    International Nuclear Information System (INIS)

    Murray, A.

    1989-01-01

    Nuclear reactor accidents which have caused core damage, released a significant amount of radioactivity, or caused death or serious injury are described. The reactor accidents discussed in detail include Chernobyl, Three Mile Island, SL-1 and Windscale, although information on other less consequential accidents is also provided. The consequences of these accidents are examined in terms of the amounts of radioactivity released, the radiation doses received, and remedial actions and interventions taken following the accident. 10 refs., 1 fig., 2 tabs

  6. Study Of Severe Accident Phenomena In Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sugiyanto; Antariksawan; Anhar, R.; Arifal

    2001-01-01

    Several phenomena that occurred in the light water reactor type of nuclear power plant during severe accident were studied. The study was carried out based on the results of severe accident researches in various countries. In general, severe accident phenomena can be classified into in-vessel phenomena, retention in the reactor coolant system, and ex-vessel phenomena. In-vessel retention has been recommended as a severe accident management strategy

  7. Hazards to nuclear plants from surface traffic accidents

    International Nuclear Information System (INIS)

    Hornyik, K.

    1975-01-01

    Analytic models have been developed for evaluating hazards to nuclear plants from hazardous-materials accidents in the vicinity of the plant. In particular, these models permit the evaluation of hazards from such accidents occurring on surface traffic routes near the plant. The analysis uses statistical information on accident rates, traffic frequency, and cargo-size distribution along with parameters describing properties of the hazardous cargo, plant design, and atmospheric conditions, to arrive at a conservative estimate of the annual probability of a catastrophic event. Two of the major effects associated with hazardous-materials accidents, explosion and release of toxic vapors, are treated by a common formalism which can be readily applied to any given case by means of a graphic procedure. As an example, for a typical case it is found that railroad shipments of chlorine in 55-ton tank cars constitute a greater hazard to a nearby nuclear plant than equally frequent rail shipments of explosives in amounts of 10 tons. 11 references. (U.S.)

  8. Effects of personality on risky driving behavior and accident involvement for Chinese drivers.

    Science.gov (United States)

    Yang, Jiaoyan; Du, Feng; Qu, Weina; Gong, Zhun; Sun, Xianghong

    2013-01-01

    Motor vehicle accidents are the leading cause of injury-related fatalities in China and pose the most serious threat to driving safety. Driver personality is considered as an effective predictor for risky driving behavior and accident liability. Previous studies have focused on the relationship between personality and risky driving behavior, but only a few of them have explored the effects of personality variables on accident involvement. In addition, few studies have examined the effects of personality on Chinese drivers' risky driving and accident involvement. The present study aimed to examine the effects of personality variables on Chinese drivers' unsafe driving behaviors and accident involvement. Two hundred and twenty-four Chinese drivers aged 20 to 50 were required to complete questionnaires assessing their personality traits (anger, sensation-seeking, altruism, and normlessness), risky driving behaviors (aggressive violations, ordinary violations), and accident involvement (all accidents, serious accidents, at-fault accidents). Multivariate regression analyses, adjusting for gender, age, and overall mileage, were conducted to identify the personality traits related to risky driving behaviors and accident involvement. Participants' personality traits were found to be significantly correlated with both risky driving behavior and accident involvement. Specifically, the traits of anger and normlessness were effective predictors for aggressive violations. The traits of anger, sensation-seeking, normlessness, and altruism were effective predictors for ordinary violations. Moreover, altruism and normlessness were significant predictors for the total number of accidents participants had during the past 3 years. Consistent with previous studies, the present study revealed that personality traits play an important role in predicting Chinese drivers' risky driving behaviors. In addition, Chinese drivers' personality characteristics were also associated with accident

  9. Regulatory risks associated with nuclear safety legislation after Fukushima Daiichi Nuclear Accident in Japan. Focus on legal structure of the nuclear reactor regulation act

    International Nuclear Information System (INIS)

    Tanabe, Tomoyuki; Maruyama, Masahiro

    2016-01-01

    Nuclear safety regulations enforced after Fukushima Daiichi Nuclear Accident under the Nuclear Reactor Regulation Act face the following regulatory problems that involve potential risk factors for nuclear businesses; 1) 'entity based regulation' unable to cope with business cessation or bankruptcy of the entity subject of regulation, 2) potential risk of the Nuclear Regulation Authority's inappropriate involvement in nuclear industry policy beyond their duty, and 3) compliance of backfits under vague regulations. In order to alleviate them, this report, through analyzing these regulatory problems from the view point of sound development of the nuclear industry, proposes the following regulatory reforms; (1) To clarify the rule for industry policy in nuclear regulations and enable the authority, Ministry of Economy, Trade and Industry, to choose most appropriate industrial policy measure. (2) Through establishing safety goals as measures to promote continuous improvement of nuclear safety regulations, to stimulate timely adjustments of the regulations, and to introduce a legal mechanism into the nuclear regulation systems under which validity of administrative law and its application can be checked. (author)

  10. Effects of the accident at Mihama Nuclear Power Plant Unit 3 on the public's attitude to nuclear power generation

    International Nuclear Information System (INIS)

    Kitada, Atsuko

    2005-01-01

    As part of an ongoing public opinion survey regarding nuclear power generation, which started in 1993, a survey was carried out in the Kansai and Kanto regions two months after the accident at Unit 3 of the Mihama Nuclear Power Plant. In addition to analyzing the statistically significant changes that have taken place since the previous survey (taken in 2003), increase and decrease of the ratio of answers to all the questions related to nuclear power before and after the two accidents were compared in the case of the accidents which occurred in the Mihama Unit 3 and the JCO company's nuclear-fuel plant. In the Kansai region, a feeling of uneasiness about the risky character of nuclear power generation increased to some extent, while the public's trust in the safety of nuclear power plants decreased somewhat. After a safety-related explanation on ''Early detection of troubles'' and Accident prevention'' was given from a managerial standpoint, people felt a little less at ease than they had before. Uneasiness, however, did not increase in relation to the overall safety explanation given about the engineering and technical functioning of the plant. There was no significant negative effect on the respondents' evaluation of or attitude toward nuclear power generation. It was found that the people's awareness about the Mihama Unit 3 accident was lower and the effect of the accident on their awareness of nuclear power generation was more limited and smaller when compared with the case of the JCO accident. In the Kanto region, people knew less about the Mihama Unit 3 accident than those living in the Kansai region, and they remembered the JCO accident, the subsequent cover-up by Tokyo Electric Power Company, and the resulting power shortage better than those living in Kansai. This suggested that there was a little difference in terms of psychological distance in relation to the accidents an incidents depending on the place where the events occurred and the company which

  11. The international nuclear liability and compensation regime put to the test of a nuclear accident

    International Nuclear Information System (INIS)

    Reyners, P.; Tetley, M.

    2003-01-01

    Full text: It appears that nuclear emergency plans place generally more emphasis on the nuclear safety and radiation protection aspects of the management of an accident, both inside the installation concerned and off-site, than on the particular requirements of local residents who would find themselves suddenly in such an emergency situation and of possible victims of nuclear damage. In a similar vein, studies focusing on the international nuclear third party liability regime usually take a global perspective and leave little room for the treatment of individual cases. The albeit welcome dearth of practical experience in Western countries in providing compensation for accidents of nuclear origin has, however, meant that public and local authorities are not always fully conscious of the importance of this question which should be dealt with in as practical a manner as possible. In order to cover all the legal and practical questions that could arise during the management of the consequences of a nuclear accident with regard to third party liability, insurance and compensation, the OECD/NEA held in co-operation with French authorities a workshop in November 2001. It was decided to organize this workshop according to three main stages: the alert phase, the accident phase and the post-accident phase; and to examine during these three stages the various roles played by local and national authorities, the nuclear operator and his insurer, as well as the nature and form of their respective actions. These questions were addressed both from the angle of applicable domestic legislation and of the relevant international conventions. From the analysis of different national experiences and of the information exchanged during the workshop, a striking diversity may be noted of solutions adopted or envisaged to address various aspects of civil liability, insurance and indemnification of damage in a nuclear emergency situation. This lack of uniformity should not necessarily be

  12. 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

  13. 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

  14. 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.)

  15. Indemnification of damage in the event of a nuclear accident

    International Nuclear Information System (INIS)

    2003-01-01

    The Workshop on the Indemnification of Damage in the Event of a Nuclear Accident, organised by the OECD Nuclear Energy Agency in close co-operation with the French authorities, was held in Paris from 26 to 28 November 2001. This event was an integral part of the International Nuclear Emergency Exercise INEX 2000. It attracted wide participation from national nuclear authorities, regulators, operators of nuclear installations, nuclear insurers and international organisations. The objective was to test the capacity of the existing nuclear liability and compensation mechanisms in the 29 countries represented at the workshop to manage the consequences of a nuclear emergency. This workshop was based upon the scenario used for the INEX 2000 Exercise, i.e. an accident simulated at the Gravelines nuclear power plant in the north of France in May 2001. These proceedings contain a comparative analysis of legislative and regulatory provisions governing emergency response and nuclear third party liability, based upon country replies to a questionnaire. This publication also includes the full responses provided to that questionnaire, as well as the texts of presentations made by special guests from Germany and Japan describing the manner in which the public authorities in their respective countries responded to two nuclear accidents of a very different nature and scale. (authors)

  16. Nineteenth nuclear accident dosimetry intercomparison study, August 9-13, 1982

    International Nuclear Information System (INIS)

    Greene, R.T.; Sims, C.C.; Swaja, R.E.

    1983-11-01

    The Nineteenth Nuclear Accident Dosimetry Intercomparison Study was held August 9 to 13, 1982, at the Oak Ridge National Laboratory using the Health Physics Research Reactor operated in the pulse mode to simulate nuclear criticality accidents. Participants from eight organizations measured neutron and gamma doses at air stations and on phantoms for three different shielding conditions. Measured results were compared to nuclear industry guidelines for criticality accident dosimeters which suggest accuracies of +-25% for neutron dose and +-20% for gamma dose. Seventy-two percent of the neutron dose measurements using foil activation, sodium activation, hair sulfur activation, and thermoluminescent methods met the guidelines while less than 40% of the gamma dose measurements were within +-20% of reference values. The softest neutron energy spectrum (also lowest neutron/gamma dose ratio) provided the most difficulty in measuring neutron and gamma doses. Results of this study indicate the need for continued intercomparison and testing of nuclear accident dosimetry systems and for training of evaluating personnel. 14 references, 7 figures, 16 tables

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    1997-01-01

    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

  19. 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.

  20. Analysis of accidents and troubles of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Kobayashi, Kunio

    1980-01-01

    In Japan, electric power companies are obliged to report the accidents and troubles occurred in nuclear power stations to the MITI according to the relevant laws, and 166 cases in total have been reported as of the end of March, 1980. These accidents and troubles are all trivial, and do not cause problems from the viewpoint of the safety nuclear power stations. Regarding respective accidents and troubles, the causes have been sought thoroughly, and the sufficient countermeasures have been taken on all occasions. But in order to improve the reliability of nuclear power stations further, it is important to treat the accidents and troubles occurred so far statistically and grasp the general trend. Thereupon, 152 accidents and troubles occurred till September, 1979, were analyzed quantitatively, and the results are reported in this paper. From the results, the prospect hereafter is discussed. The number of the reported cases of accidents and troubles in each nuclear power plant in operation every year is tabulated. The accidents and troubles were relatively frequent in the initial two or three years of operation of respective new reactor types, but decreased thereafter. The systems to which troubled equipments belong and the troubled equipments are shown. Most troubles have occurred in reactor cooling systems and valves. The situations and causes of troubles, the operational conditions at the time of the accidents and troubles and the effects and others are reported. (Kako, I.)

  1. Fukushima nuclear accident and the social responsibility of science

    International Nuclear Information System (INIS)

    Yoshioka, Hitoshi

    2011-01-01

    Five months had passed since Fukushima Daiichi Nuclear Power Plant (NPP) accident occurred but still there was no knowing when the accident ended. Released radioactivity seemed to be greater than one million terra Bq and if there occurred an explosive rupture of containment vessel due to the failure of containment vent or occurrence of steam explosion, the amount of released radioactivity might amount to be at least equivalent to or surpass that of Chernobyl NPP accident. There existed still a risk that overheating and meltdown of nuclear fuels might reoccur with loss of cooling due to a possible giant aftershock. This article described total views on significant disaster that the accident brought about on many neighboring residents or wide range of people. After a general discussion about what was social responsibility of scientists, social responsibility of scientists for Fukushima Daiichi NPP accident was discussed. Responsibility of omission was also argued. (T. Tanaka)

  2. Japanese Nuclear Accident and U.S. Response

    International Nuclear Information System (INIS)

    Douet, Randy

    2011-01-01

    U.S. Government response to the Fukushima accident: • Multi-agency task force (Nuclear Regulatory Commission, Department of Energy, Department of Defense) supporting Japan recovery efforts; • President Obama directed the NRC to perform a comprehensive review of U.S. reactors; • NRC established agency task force to develop lessons learned from Fukushima Daiichi accident to provide short-term and long-term analysis of the events

  3. Accident at Three Mile Island nuclear power plant and lessons learned

    International Nuclear Information System (INIS)

    Ashrafi, A.; Farnoudi, F.; Tochai, M.T.M.; Mirhabibi, N.

    1986-01-01

    On March 28, 1979, the TMI, unit 2 nuclear power plant experienced a loss of coolant accident (LOCA) which has had a major impact among the others, upon the safety of nuclear power plants. Although a small part of the reactor core melted in this accident, but due to well performance of the vital safety equipment, there was no serious radioactivity release to the environment, and the accident has had no impact on the basic safety goals. A brief scenario of the accident, its consequences and the lessons learned are discussed

  4. Cleanup and decommissioning of a nuclear reactor after a severe accident

    International Nuclear Information System (INIS)

    1992-01-01

    Although the development of commercial nuclear power plants has in general been associated with an excellent record of nuclear safety, the possibility of a severe accident resulting in major fuel and core damage cannot be excluded and such accidents have in fact already occurred. For over a decade, IAEA publications have provided technical guidance and recommendations for post-accident planning to be considered by appropriate authorities. Guidance and recommendations have recently been published on the management of damaged nuclear fuel, sealing of the reactor building and related safety and performance assessment aspects. The present technical report on the cleanup and decommissioning of reactors which have undergone a severe accident represents a further publication in the series. Refs, figs and tabs.

  5. The risk of major nuclear accident: calculation and perception of probabilities

    International Nuclear Information System (INIS)

    Leveque, Francois

    2013-01-01

    Whereas before the Fukushima accident, already eight major accidents occurred in nuclear power plants, a number which is higher than that expected by experts and rather close to that corresponding of people perception of risk, the author discusses how to understand these differences and reconcile observations, objective probability of accidents and subjective assessment of risks, why experts have been over-optimistic, whether public opinion is irrational regarding nuclear risk, and how to measure risk and its perception. Thus, he addresses and discusses the following issues: risk calculation (cost, calculated frequency of major accident, bias between the number of observed accidents and model predictions), perceived probabilities and aversion for disasters (perception biases of probability, perception biases unfavourable to nuclear), the Bayes contribution and its application (Bayes-Laplace law, statistics, choice of an a priori probability, prediction of the next event, probability of a core fusion tomorrow)

  6. Technical basis for nuclear accident dosimetry at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kerr, G.D.; Mei, G.T.

    1993-08-01

    The Oak Ridge National Laboratory (ORNL) Environmental, Safety, and Health Emergency Response Organization has the responsibility of providing analyses of personnel exposures to neutrons and gamma rays from a nuclear accident. This report presents the technical and philosophical basis for the dose assessment aspects of the nuclear accident dosimetry (NAD) system at ORNL. The issues addressed are regulatory guidelines, ORNL NAD system components and performance, and the interpretation of dosimetric information that would be gathered following a nuclear accident

  7. Global risk of radioactive fallout after major nuclear reactor accidents

    International Nuclear Information System (INIS)

    Lelieveld, J.; Kunkel, D.; Lawrence, M.G.

    2012-01-01

    Major reactor accidents of nuclear power plants are rare, yet the consequences are catastrophic. But what is meant by ''rare''? And what can be learned from the Chernobyl and Fukushima incidents? Here we assess the cumulative, global risk of exposure to radioactivity due to atmospheric dispersion of gases and particles following severe nuclear accidents (the most severe ones on the International Nuclear Event Scale, INES 7), using particulate "1"3"7Cs and gaseous "1"3"1I as proxies for the fallout. Our results indicate that previously the occurrence of INES 7 major accidents and the risks of radioactive contamination have been underestimated. Using a global model of the atmosphere we compute that on average, in the event of a major reactor accident of any nuclear power plant worldwide, more than 90% of emitted "1"3"7Cs would be transported beyond 50 km and about 50% beyond 1000 km distance before being deposited. This corroborates that such accidents have large-scale and trans-boundary impacts. Although the emission strengths and atmospheric removal processes of "1"3"7Cs and "1"3"1I are quite different, the radioactive contamination patterns over land and the human exposure due to deposition are computed to be similar. High human exposure risks occur around reactors in densely populated regions, notably in West Europe and South Asia, where a major reactor accident can subject around 30 million people to radioactive contamination. The recent decision by Germany to phase out its nuclear reactors will reduce the national risk, though a large risk will still remain from the reactors in neighbouring countries.

  8. Organizational influence on the occurrence of work accidents involving exposure to biological material.

    Science.gov (United States)

    Marziale, Maria Helena Palucci; Rocha, Fernanda Ludmilla Rossi; Robazzi, Maria Lúcia do Carmo Cruz; Cenzi, Camila Maria; dos Santos, Heloisa Ehmke Cardoso; Trovó, Marli Elisa Mendes

    2013-01-01

    to analyze work accidents involving exposure to biological materials which took place among personnel working in nursing and to evaluate the influence of the organizational culture on the occurrence of these accidents. a retrospective, analytical study, carried out in two stages in a hospital that was part of the Network for the Prevention of Work Accidents. The first stage involved the analysis of the characteristics of the work accidents involving exposure to biological materials as recorded over a seven-year period by the nursing staff in the hospital studied, and registered in the Network databank. The second stage involved the analysis of 122 nursing staff members' perception of the institutional culture, who were allocated to the control group (workers who had not had an accident) and the case group (workers who had had an accident). 386 accidents had been recorded: percutaneous lesions occurred in 79% of the cases, needles were the materials involved in 69.7% of the accidents, and in 81.9% of the accident there was contact with blood. Regarding the influence of the organizational culture on the occurrence of accidents, the results obtained through the analysis of the two groups did not demonstrate significant differences between the average scores attributed by the workers in each organizational value or practice category. It is concluded that accidents involving exposure to biological material need to be avoided, however, it was not possible to confirm the influence of organizational values or practices on workers' behavior concerning the occurrence of these accidents.

  9. Severe accident management program at Cofrentes Nuclear Power Plant

    International Nuclear Information System (INIS)

    Borondo, L.; Serrano, C.; Fiol, M.J.; Sanchez, A.

    2000-01-01

    Cofrentes Nuclear Power Plant (GE BWR/6) has implemented its specific Severe Accident Management Program within this year 2000. New organization and guides have been developed to successfully undertake the management of a severe accident. In particular, the Technical Support Center will count on a new ''Severe Accident Management Team'' (SAMT) which will be in charge of the Severe Accident Guides (SAG) when Control Room Crew reaches the Emergency Operation Procedures (EOP) step that requires containment flooding. Specific tools and training have also been developed to help the SAMT to mitigate the accident. (author)

  10. Scientific aspects of the Tohoku earthquake and Fukushima nuclear accident

    Science.gov (United States)

    Koketsu, Kazuki

    2016-04-01

    We investigated the 2011 Tohoku earthquake, the accident of the Fukushima Daiichi nuclear power plant, and assessments conducted beforehand for earthquake and tsunami potential in the Pacific offshore region of the Tohoku District. The results of our investigation show that all the assessments failed to foresee the earthquake and its related tsunami, which was the main cause of the accident. Therefore, the disaster caused by the earthquake, and the accident were scientifically unforeseeable at the time. However, for a zone neighboring the reactors, a 2008 assessment showed tsunamis higher than the plant height. As a lesson learned from the accident, companies operating nuclear power plants should be prepared using even such assessment results for neighboring zones.

  11. On-site emergency intervention plan for nuclear accident situation at INR-Pitesti TRIGA reactor

    International Nuclear Information System (INIS)

    Oprea, I.; Margenu, S.; Preda, M.

    2001-01-01

    A nuclear incident is defined as a series of events leading to release of radioactive materials into the environment of sufficient concentration to make necessary protective actions. The decision to initiate a protective action is a complex process. The benefits of taking the action is weighed against the involved risk and constraints. In addition the decision will be made under difficult emergency conditions, probably with little detailed information available. Therefore, considerable planing is necessary to reduce to manageable levels the types of decisions leading to effective responses to protect the public in the event of a nuclear incident. The sequence of events for developing emergency plans and responding to nuclear incidents will vary according to individual circumstances, because the international recommendations and site-specific emergency plans cannot provide detailed guidance for all accident scenarios and variations in local conditions. Flexibility must be maintained in emergency response to reflect the actual circumstances encountered (e.g. source term characteristics, the large number of possible weather conditions and environmental situation such as time of the day, season of the year, land use and soil types, population distribution and economic structures, uncertainties in the availability of technical and administrative support and the behaviour of the population). This further complicates the decision-making process, especially under accident conditions where there are time pressures and psychological stress. Therefore one the most important problems in the case of a nuclear emergency is quantifying all these very different types of off-site consequences. Last years, and in particular since the Chernobyl accident, there has been a considerable increase in the resources allocated to development of computerised systems which allow for predicting the radiological impact of accidents and to provide information in a manageable and effective form to

  12. Accident at the Three Mile Island Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bajusz, J.; Vamos, G.

    1979-01-01

    A short description of the TMI power plant is given. The course of events leading to the reactor accident and that of the first two weeks is described. The effect on the environment is estimated. The reasons and consequences of the accident are analysed. The probability of such an accident at the Paks Nuclear Power Plant is estimated. (R.J.)

  13. The risk of a major nuclear accident: calculation and perception of probabilities

    International Nuclear Information System (INIS)

    Leveque, Francois

    2013-07-01

    The accident at Fukushima Daiichi, Japan, occurred on 11 March 2011. This nuclear disaster, the third on such a scale, left a lasting mark in the minds of hundreds of millions of people. Much as Three Mile Island or Chernobyl, yet another place will be permanently associated with a nuclear power plant which went out of control. Fukushima Daiichi revived the issue of the hazards of civil nuclear power, stirring up all the associated passion and emotion. The whole of this paper is devoted to the risk of a major nuclear accident. By this we mean a failure initiating core meltdown, a situation in which the fuel rods melt and mix with the metal in their cladding. Such accidents are classified as at least level 5 on the International Nuclear Event Scale. The Three Mile Island accident, which occurred in 1979 in the United States, reached this level of severity. The explosion of reactor 4 at the Chernobyl plant in Ukraine in 1986 and the recent accident in Japan were classified as class 7, the highest grade on this logarithmic scale. The main difference between the top two levels and level 5 relates to a significant or major release of radioactive material to the environment. In the event of a level-5 accident, damage is restricted to the inside of the plant, whereas, in the case of level-7 accidents, huge areas of land, above or below the surface, and/or sea may be contaminated. Before the meltdown of reactors 1, 2 and 3 at Fukushima Daiichi, eight major accidents affecting nuclear power plants had occurred worldwide. This is a high figure compared with the one calculated by the experts. Observations in the field do not appear to fit the results of the probabilistic models of nuclear accidents produced since the 1970's. Oddly enough the number of major accidents is closer to the risk as perceived by the general public. In general we tend to overestimate any risk relating to rare, fearsome accidents. What are we to make of this divergence? How are we to reconcile

  14. Transportation accidents/incidents involving radioactive materials (1971--1991)

    International Nuclear Information System (INIS)

    Cashwell, C.E.; McClure, J.D.

    1992-01-01

    The Radioactive Materials Incident Report (RMIR) database contains information on transportation-related accidents and incidents involving radioactive materials that have occurred in the United States. The RMIR was developed at Sandia National Laboratories (SNL) to support its research and development program efforts for the US Department of Energy (DOE). This paper will address the following topics: background information on the regulations and process for reporting a hazardous materials transportation incident, overview data of radioactive materials transportation accidents and incidents, and additional information and summary data on how packagings have performed in accident conditions

  15. Severe accidents and nuclear containment integrity (SANCY). SANCY summary report

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, I. [VTT Processes, Espoo (Finland)

    2004-07-01

    SANCY project investigates physical phenomena related to severe nuclear accidents with importance to Finnish nuclear power plants. Currently the major topics are the ex-vessel coolability issues, long-term severe accident management and containment leak tightness and adoption and development of new calculation tools considering also the needs of the future Olkiluoto 3 plant. SANCY employs both experimental and analytical methods. (orig.)

  16. Using modular neural networks to monitor accident conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Guo, Z.

    1992-01-01

    Nuclear power plants are very complex systems. The diagnoses of transients or accident conditions is very difficult because a large amount of information, which is often noisy, or intermittent, or even incomplete, need to be processed in real time. To demonstrate their potential application to nuclear power plants, neural networks axe used to monitor the accident scenarios simulated by the training simulator of TVA's Watts Bar Nuclear Power Plant. A self-organization network is used to compress original data to reduce the total number of training patterns. Different accident scenarios are closely related to different key parameters which distinguish one accident scenario from another. Therefore, the accident scenarios can be monitored by a set of small size neural networks, called modular networks, each one of which monitors only one assigned accident scenario, to obtain fast training and recall. Sensitivity analysis is applied to select proper input variables for modular networks

  17. International Experts' Meeting on Decommissioning and Remediation after a Nuclear Accident. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    Against the backdrop of the accident at TEPCO's Fukushima Daiichi nuclear power plant in March 2011, the Director General of the International Atomic Energy Agency (IAEA) convened the IAEA Ministerial Conference on Nuclear Safety in Vienna, Austria, in June 2011. The Conference adopted a Ministerial Declaration which, inter alia, requested the Director General to prepare a draft Action Plan covering all the relevant aspects relating to nuclear safety, emergency preparedness and response, and radiation protection of people and the environment, as well as the relevant international legal framework. On 22 September 2011, the IAEA General Conference unanimously endorsed the draft IAEA Action Plan on Nuclear Safety approved by the Board of Governors. The Action Plan sets out a comprehensive programme of work, in 12 major areas, to strengthen nuclear safety worldwide. Under one of these areas, headed 'Enhance transparency and effectiveness of communication and improve dissemination of information', the IAEA Secretariat was requested to organize an International Experts' Meeting (IEM) on decommissioning, cleanup and remediation of nuclear facilities and contaminated lands after a nuclear accident. This IEM was organized in response to that request. The IEM focussed on the complex technical, societal, environmental and economic issues that need to be considered for decommissioning and remediation activities after a nuclear accident, specifically after the emergency exposure situation of an accident has been declared ended. The objective of the IEM is to assist Member States to prepare for and to be able to manage the consequences resulting from a nuclear accident. The meeting highlighted the specific short term and long term issues that may need to be addressed during decommissioning of facilities and remediation of the off-site environment affected by a nuclear accident. It is of interest to a wide range of experts, such as decision makers, regulators, operators

  18. How a nuclear power plant accident influences acceptance of nuclear power: results of a longitudinal study before and after the Fukushima disaster.

    Science.gov (United States)

    Visschers, Vivianne H M; Siegrist, Michael

    2013-02-01

    Major nuclear accidents, such as the recent accident in Fukushima, Japan, have been shown to decrease the public's acceptance of nuclear power. However, little is known about how a serious accident affects people's acceptance of nuclear power and the determinants of acceptance. We conducted a longitudinal study (N= 790) in Switzerland: one survey was done five months before and one directly after the accident in Fukushima. We assessed acceptance, perceived risks, perceived benefits, and trust related to nuclear power stations. In our model, we assumed that both benefit and risk perceptions determine acceptance of nuclear power. We further hypothesized that trust influences benefit and risk perceptions and that trust before a disaster relates to trust after a disaster. Results showed that the acceptance and perceptions of nuclear power as well as its trust were more negative after the accident. In our model, perceived benefits and risks determined the acceptance of nuclear power stations both before and after Fukushima. Trust had strong effects on perceived benefits and risks, at both times. People's trust before Fukushima strongly influenced their trust after the accident. In addition, perceived benefits before Fukushima correlated with perceived benefits after the accident. Thus, the nuclear accident did not seem to have changed the relations between the determinants of acceptance. Even after a severe accident, the public may still consider the benefits as relevant, and trust remains important for determining their risk and benefit perceptions. A discussion of the benefits of nuclear power seems most likely to affect the public's acceptance of nuclear power, even after a nuclear accident. © 2012 Society for Risk Analysis.

  19. Inventory of accidents and losses at sea involving radioactive material

    International Nuclear Information System (INIS)

    2001-09-01

    The present report describes the content of the inventory of accidents and losses at sea involving radioactive material. It covers accidents and losses resulting in the actual release of radioactive materials into the marine environment and also those which have the potential for release. For completeness, records of radioactive materials involved in accidents but which were recovered intact from the sea are also reported. Information on losses of sealed sources resulting in actual or potential release of activity to the marine environment nad of sealed sources that were recovered intact is also presented

  20. Health problems raised by the elimination of radioactive wastes and nuclear accidents

    International Nuclear Information System (INIS)

    Jammet, H.; Mechali, D.; Dousset, M.

    1964-01-01

    The rapid development of nuclear energy demands an urgent solution to the health problems arising from the discharge into the environment of radioactive residues produced by nuclear installations. - To be able to evaluate the risks run by the population and to fix tolerance limits for waste discharge, it is necessary to possess an exact knowledge of the course taken by the radioelements discharged, from their source until they reach man. The incorporation of radioelements in food cycles is the first risk to take into consideration. The factors involved in all stages of this transmission must be foreseen, whether they concern physical or biological media, because of their continuity and their interdependence. Finally, socio-economic and dietetic data must be collected in order that the risks and tolerance levels estimated are based on concrete and experimental rather than theoretical knowledge. The risk of nuclear accidents in the atomic industry, although very improbable, must be taken into consideration because of the seriousness of their consequences. The health problems arise in the field of professional hygiene on the one hand and in that of public hygiene on the other. In the first field the risk is two-fold and involves irradiation and contamination. The public sphere is reduced essentially to the risk of contamination by radioactive substances accidentally released in the surrounding medium. The health studies to be conducted in this field therefore include research not only on irradiation or contamination therapeutics but also on the transfer of radioelements from the accident site to man, mainly through food cycles, in their physical and in their biological components. Studies of this kind form the basis of decisions in the health field which would have to be taken in the case of an accident. (authors) [fr

  1. Nuclear accidents and bone marrow graft

    International Nuclear Information System (INIS)

    Bernard, J.

    1988-01-01

    In case of serious contamination, the only efficacious treatment is the bone marrow grafts. The graft types and conditions have been explained. To restrict the nuclear accidents consequences, it is recommended to: - take osseous medulla of the personnel exposed to radiations and preserve it , that permits to carry out rapidly the auto-graft in case of accidents; - determine, beforehand, the HLA group of the personnel; - to register the voluntary donors names and addresses, and their HLA group, that permits to find easily a compatible donar in case of allo-graft. (author)

  2. The response to a worst-case scenario - the national emergency plan for nuclear accidents

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham D, John [Radiological Protection Inst. of Ireland (Ireland)

    1996-10-01

    The Chernobyl accident in 1986 highlighted many deficiencies in the preparedness of countries to deal with a major accident. It demonstrated how vulnerable countries are to transboundary contamination. Ireland had no emergency plan at the time of the accident and only minimal facilities with which to assess the consequences of the accident. Nonetheless, the then Nuclear Energy Board with the assistance of Government Departments and the Civil Defence organisation reacted quickly to assess the situation despite the complete lack of information about the accident from the then USSR. Even countries with advanced nuclear technologies faced similar difficulties. It was quickly recognised by Government that the national laboratory facilities were totally inadequate. The Nuclear Energy Board was provided with additional resources to assist it to cope in the short term with the very large demand for monitoring. In the longer term a new national radiation laboratory was provided and the Board was formally replaced by the Radiological Protection Institute of Ireland. It was given statutory responsibility to monitor radiation levels, to advise measures to be taken for the protection of the public and to provide information for the public. An emergency plan based on the Chernobyl experience was drafted in 1987, amended and published in 1992. Certain features of this plan were implemented from 1987 onwards, notably the classification of responsibilities and the installation of a national continuous radiation monitoring system. The paper outlines the responsibilities of those who could be involved in a response to a nuclear incident, the procedures used to evaluate its consequences and the provision of information for the public. The plan provides an integrated management system which has sufficient flexibility to enable a rapid response to be made to a major or minor crisis, either foreseen or unforeseen and whatever its cause.

  3. Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010

    International Nuclear Information System (INIS)

    Hickman, D.P.; Wysong, A.R.; Heinrichs, D.P.; Wong, C.T.; Merritt, M.J.; Topper, J.D.; Gressmann, F.A.; Madden, D.J.

    2011-01-01

    The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE

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

    International Nuclear Information System (INIS)

    1994-01-01

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

  5. Nuclear power reactor core melt accidents. Current State of Knowledge

    International Nuclear Information System (INIS)

    Jacquemain, Didier; Cenerino, Gerard; Corenwinder, Francois; Raimond, Emmanuel IRSN; Bentaib, Ahmed; Bonneville, Herve; Clement, Bernard; Cranga, Michel; Fichot, Florian; Koundy, Vincent; Meignen, Renaud; Corenwinder, Francois; Leteinturier, Denis; Monroig, Frederique; Nahas, Georges; Pichereau, Frederique; Van-Dorsselaere, Jean-Pierre; Couturier, Jean; Debaudringhien, Cecile; Duprat, Anna; Dupuy, Patricia; Evrard, Jean-Michel; Nicaise, Gregory; Berthoud, Georges; Studer, Etienne; Boulaud, Denis; Chaumont, Bernard; Clement, Bernard; Gonzalez, Richard; Queniart, Daniel; Peltier, Jean; Goue, Georges; Lefevre, Odile; Marano, Sandrine; Gobin, Jean-Dominique; Schwarz, Michel; Repussard, Jacques; Haste, Tim; Ducros, Gerard; Journeau, Christophe; Magallon, Daniel; Seiler, Jean-Marie; Tourniaire, Bruno; Durin, Michel; Andreo, Francois; Atkhen, Kresna; Daguse, Thierry; Dubreuil-Chambardel, Alain; Kappler, Francois; Labadie, Gerard; Schumm, Andreas; Gauntt, Randall O.; Birchley, Jonathan

    2015-11-01

    accidents and, secondly, the physical phenomena, studies and analyses described in Chapters 5 to 8. Chapter 5 is devoted to describing the physical phenomena liable to occur during a core melt accident, in the reactor vessel and the reactor containment. It also presents the sequence of events and the methods for mitigating their impact. For each of the subjects covered, a summary of the physical phenomena involved is followed by a description of the past, present and planned experiments designed to study these phenomena, along with their modelling, the validation of which is based on the test results. The chapter then describes the computer codes that couple all of the models and provide the best current state of knowledge of the phenomena. Lastly, this knowledge is reviewed while taking into account the gaps and uncertainties, and the outlook for the future is presented, notably regarding experimental programmes and the development of modelling and numerical simulation tools. Chapter 6 focuses on the behaviour of the containment enclosures during a core melt accident. After summarising the potential leakage paths of radioactive substances through the different containments in the case of the accidents chosen in the design phase, it presents the studies of the mechanical behaviour of the different containments under the loadings that can result from the hazards linked with the phenomena described in Chapter 5. Chapter 6 also discusses the risks of containment building bypass in a core melt accident situation. Chapter 7 presents the lessons learned regarding the phenomenology of core melt accidents and the improvement of nuclear reactor safety. Lastly, Chapter 8 presents a review of development and validation efforts regarding the main computer codes dealing with 'severe accidents', which draw on and build upon the knowledge mainly acquired through the research programmes: ASTEC (IRSN and GRS), MAAP-4 (FAI (US)) and used by EDF and by utilities in many other

  6. A study into the consequences of a nuclear accident

    International Nuclear Information System (INIS)

    Arnott, D.G.

    1987-07-01

    The nuclear industry in Britain would like to believe, and would like the general public to believe, that major accidents such as that at Chernobyl in 1986, could no happen in Britain, because the design and operating procedure have been made as safe as possible. However, because the designers and operators are human, they can make mistakes. Some of these are mentioned; errors of design, errors of maintenance or inspection and errors of judgement. In spite of protestations to the contrary, a major accident could occur at Sizewell-B reactor. Given that this a real possibility, plans should be drawn up to prepare for the situation. The study considers the possible consequences of a nuclear accident under the headings, human error, how nuclear fission works, radioactivity, the truth about Chernobyl, what patterns of reactor accident are possible, what can be done (this includes meteorological information, the issuing of potassium iodate tables, radiation monitoring and evacuation). Practical issues which should concern the local authorities, especially Wrekin Council, are discussed and a recommendation made for an environmental protection officer to be appointed to keep the matter under continuing review. (U.K.)

  7. Public opinion change after the Fukushima nuclear accident: The role of national context revisited

    International Nuclear Information System (INIS)

    Latré, Edwin; Perko, Tanja; Thijssen, Peter

    2017-01-01

    This study explores how national context moderated change in support for nuclear energy after the Fukushima accident. The following national contextual variables are tested: geographical distance, nuclear energy production status, freedom of the press, and the building of new nuclear reactors. The results illustrate that previous research has misunderstood the moderating role of national context on opinion change after the Fukushima accident. A survey conducted shortly after the accident with more than 23,000 respondents from 41 countries has shown that geographical distance from the accident mattered: Contradicting a previous study, the decrease in support for nuclear energy was stronger in countries closer to Fukushima. In addition, support for nuclear energy decreased more in countries where new nuclear reactors were under construction. The country's nuclear energy production status and press freedom did not determine opinion change after the Fukushima accident. The non-effect of freedom of the press on opinion change contradicts the role of media after a focusing event as described in the literature. Overall results demonstrate a limited effect of national context on opinion change following a focusing event. Hence, national context provides only limited information to policy makers on how to respond to a nuclear accident. - Highlights: • National context had limited effect on opinion change after Fukushima. • Support for nuclear energy decreased more in counties closer to the accident. • Support for nuclear energy decreased more where the nuclear energy debate was salient. • Freedom of the press did not determine opinion change after Fukushima. • Not all contextual factors are relevant when designing appropriate policy response.

  8. A source term estimation method for a nuclear accident using atmospheric dispersion models

    DEFF Research Database (Denmark)

    Kim, Minsik; Ohba, Ryohji; Oura, Masamichi

    2015-01-01

    The objective of this study is to develop an operational source term estimation (STE) method applicable for a nuclear accident like the incident that occurred at the Fukushima Dai-ichi nuclear power station in 2011. The new STE method presented here is based on data from atmospheric dispersion...... models and short-range observational data around the nuclear power plants.The accuracy of this method is validated with data from a wind tunnel study that involved a tracer gas release from a scaled model experiment at Tokai Daini nuclear power station in Japan. We then use the methodology developed...... and validated through the effort described in this manuscript to estimate the release rate of radioactive material from the Fukushima Dai-ichi nuclear power station....

  9. The nuclear accident risk: a territorial approach

    International Nuclear Information System (INIS)

    Ambroise, Pascal

    2011-01-01

    How many people live in the vicinity of French nuclear power stations? Recent events - notably in Japan, but also in France - highlight the urgent need to be able to predict the possible effects of a nuclear accident on surrounding territories. Here, Ambroise Pascal identifies two key criteria for such an estimation: residential density and land use. (author)

  10. Overview of domestic and foreign comments on Fukushima nuclear accident in the past half year

    International Nuclear Information System (INIS)

    Liu Yuanyuan; Chen Haiying; Zhang Chunming

    2011-01-01

    On March 11, 2011, Fukushima Dai-ichi nuclear power plant happened severity level nuclear accident, and caused great disasters. To be able to get more experience feedbacks for the safe development of nuclear technology from this accident, this paper investigated the domestic and foreign comments on Fukushima nuclear accident in the past half year, summarized and analyzed the attentions of experts a- bout this accident and improvement methods for the existing nuclear power technology. The results show that most domestic experts focus on improving nuclear power technology and management of emergency response and supervision, while foreign experts pay more attentions to how to deal with the environmental impact of accident on the biological side. All of these attentions and improvement methods will provide more useful information for developing safe nuclear power technology. (authors)

  11. Accident information needs

    International Nuclear Information System (INIS)

    Hanson, D.J.; Arcieri, W.C.; Ward, L.W.

    1992-01-01

    A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the information personnel involved in accident management will need to understand plant behavior. Step 3 determines the capability of the instrumentation to function properly under severe accident conditions. Step 4 determines the conditions expected during the identified severe accidents. Step 5 compares the instrument capabilities and the severe accident conditions to evaluate the availability of the instrumentation to supply needed plant information

  12. Accident information needs

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, D.J.; Arcieri, W.C.; Ward, L.W.

    1992-12-31

    A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the information personnel involved in accident management will need to understand plant behavior. Step 3 determines the capability of the instrumentation to function properly under severe accident conditions. Step 4 determines the conditions expected during the identified severe accidents. Step 5 compares the instrument capabilities and the severe accident conditions to evaluate the availability of the instrumentation to supply needed plant information.

  13. Accident information needs

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, D.J.; Arcieri, W.C.; Ward, L.W.

    1992-01-01

    A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the information personnel involved in accident management will need to understand plant behavior. Step 3 determines the capability of the instrumentation to function properly under severe accident conditions. Step 4 determines the conditions expected during the identified severe accidents. Step 5 compares the instrument capabilities and the severe accident conditions to evaluate the availability of the instrumentation to supply needed plant information.

  14. Radioactive fallout from the Chernobyl nuclear reactor accident

    International Nuclear Information System (INIS)

    Beiriger, J.M.; Failor, R.A.; Marsh, K.V.; Shaw, G.E.

    1987-08-01

    This report describes the detection of fallout in the United States from the Chernobyl nuclear reactor accident. As part of its environmental surveillance program, Lawrence Livermore National Laboratory maintained detectors for gamma-emitting radionuclides. Following the reactor accident, additional air filters were set out. Several uncommon isotopes were detected at the time the plume passed into the US

  15. Estimation Of 137Cs Using Atmospheric Dispersion Models After A Nuclear Reactor Accident

    Science.gov (United States)

    Simsek, V.; Kindap, T.; Unal, A.; Pozzoli, L.; Karaca, M.

    2012-04-01

    Nuclear energy will continue to have an important role in the production of electricity in the world as the need of energy grows up. But the safety of power plants will always be a question mark for people because of the accidents happened in the past. Chernobyl nuclear reactor accident which happened in 26 April 1986 was the biggest nuclear accident ever. Because of explosion and fire large quantities of radioactive material was released to the atmosphere. The release of the radioactive particles because of accident affected not only its region but the entire Northern hemisphere. But much of the radioactive material was spread over west USSR and Europe. There are many studies about distribution of radioactive particles and the deposition of radionuclides all over Europe. But this was not true for Turkey especially for the deposition of radionuclides released after Chernobyl nuclear reactor accident and the radiation doses received by people. The aim of this study is to determine the radiation doses received by people living in Turkish territory after Chernobyl nuclear reactor accident and use this method in case of an emergency. For this purpose The Weather Research and Forecasting (WRF) Model was used to simulate meteorological conditions after the accident. The results of WRF which were for the 12 days after accident were used as input data for the HYSPLIT model. NOAA-ARL's (National Oceanic and Atmospheric Administration Air Resources Laboratory) dispersion model HYSPLIT was used to simulate the 137Cs distrubition. The deposition values of 137Cs in our domain after Chernobyl Nuclear Reactor Accident were between 1.2E-37 Bq/m2 and 3.5E+08 Bq/m2. The results showed that Turkey was affected because of the accident especially the Black Sea Region. And the doses were calculated by using GENII-LIN which is multipurpose health physics code.

  16. The Fukushima Daiichi nuclear accident final report of the AESJ investigation committee

    CERN Document Server

    Atomic Energy Society of Japan

    2015-01-01

    The Magnitude 9 Great East Japan Earthquake on March 11, 2011, followed by a massive tsunami struck  TEPCO’s Fukushima Daiichi Nuclear Power Station and triggered an unprecedented core melt/severe accident in Units 1 – 3. The radioactivity release led to the evacuation of local residents, many of whom still have not been able to return to their homes. As a group of nuclear experts, the Atomic Energy Society of Japan established the Investigation Committee on the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station, to investigate and analyze the accident from scientific and technical perspectives for clarifying the underlying and fundamental causes, and to make recommendations. The results of the investigation by the AESJ Investigation Committee has been compiled herewith as the Final Report. Direct contributing factors of the catastrophic nuclear incident at Fukushima Daiichi NPP initiated by an unprecedented massive earthquake/ tsunami – inadequacies in tsunami measures, severe accident ma...

  17. The nuclear accidents: Causes and consequences

    International Nuclear Information System (INIS)

    Rochd, M.

    1988-01-01

    The author discussed and compared the real causes of T.M.I. and Chernobyl accidents and cited their consequences. To better understand how these accidents occurred, a brief description of PWR type (reactor type of T.M.I.) and of RBMK type (reactor type of Chernobyl) has been presented. The author has also set out briefly the safety analysis objectives and the three barriers established to protect the public against the radiological consequences. To distinguish failures that cause severe accidents and to analyze them in details, it is necessary to classify the accidents. There are many ways to do it according to their initiator event, or to their frequency, or to their degree of gravity. The safety criteria adopted by nuclear industry have been explained. These criteria specify the limits of certain physical parameters that should not be exceeded in case of incidents or accidents. To compare the real causes of T.M.I. and Chernobyl accidents, the events that led to both have been presented. As observed the main common contributing factors in both cases are that the operators did not pay attention to warnings and signals that were available to them and that they were not trained to handle these accident sequences. The essential conclusions derived from these severe accidents are: -The improvement of operators competence contribute to reduce the accident risks; -The rapid and correct diagnosis of real conditions at each point of the accidents permits an appropriate behavior that would bring the plant to a stable state; -Competent technical teams have to intervene and to assist the operators in case of emergency; -Emergency plans and an international collaboration are necessary to limit the accident risks. 11 figs. (author)

  18. Problems of probabilistic safety assessment after Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    Sugiyama, Naoki

    2011-01-01

    Probabilistic safety assessment (PSA) methodology to assure nuclear safety is had great expectations of lessons learned from Fukushima Daiichi nuclear power plant (NPP) accident and on the other hand this accident made actualized technical problems of PSA. Effectiveness of current PSA methodology for risk assessment was confirmed by comparing the accident development with accident scenario of PSA and equipment failure rate. From a viewpoint of nuclear safety objective and defense in depth approach of IAEA, technical problems of PSA were (1) extension of PSA for spent fuel pool and waste disposal system as well as level 3PSA for broader environmental contamination and (2) overlapping of accident scenario of plural unit site, balance of high quality plant management and preceding negation, treatment of uncertainty of external events, severe accident measure and human reliability analysis and reflection of disaster prevention capability to level 3PSA. In order to upgrade PSA technology, six proposals were described for nuclear safety and defense in depth, comprehensive evaluation scope and catch-up of latest technology, necessity of strategic preparation of PSA standard, human resources fostering and risk communication. (T. Tanaka)

  19. Accidents involving specialized aircraft in agriculture aerial spraying

    Directory of Open Access Journals (Sweden)

    Marcelo Boamorte Ravelli

    Full Text Available ABSTRACT: The great challenge for the practice of agricultural aviation has been to avoid accidents. Although, there are technological progress and high resources for safety, accidents continue to occur. The objective of this research was to analyze the influence and occurrence of factors in agricultural aviation accidents in Brazil recently. Based on research and technical - scientific papers written by researchers and aviation authorities, recommendations directed towards reducing the risks associated with this aircraft modality are assessed. The main factors responsible for accidents are normally operational errors and maneuvers that cause flight collisions, engine failures and altitude loss. Professional awareness and qualification converge towards the success of the agricultural pilot in the detection of inherent dangers or occasional in the various systems involved.

  20. Accident consequence analysis models applied to licensing process of nuclear installations, radioactive and conventional industries

    International Nuclear Information System (INIS)

    Senne Junior, Murillo; Vasconcelos, Vanderley de; Jordao, Elizabete

    2002-01-01

    The industrial accidents happened in the last years, particularly in the eighty's decade, had contributed in a significant way to call the attention to government authorities, industry and society as a whole, demanding mechanisms for preventing episodes that could affect people's safety and environment quality. Techniques and methods already thoroughly used in the nuclear, aeronautic and war industries were then adapted for performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. Some models for analyzing the consequences of accidents involving fire and explosion, used in the licensing processes of nuclear and radioactive facilities, are presented in this paper. These models have also application in the licensing of conventional industrial facilities. (author)

  1. The Fukushima Nuclear Accident: What has been learned from it?

    Science.gov (United States)

    Ohska, Tokio

    2014-05-01

    The ill-fated Fukushima nuclear reactors are still in a state in which Japanese are struggling to find the end of the tunnel. They are now facing with the highly contaminated radioactive water. It is polluting the world unless confined in a small space for an incredibly long time. There have been many cases such as the crude oil leak from a deep-sea oil well polluting ocean or many volcanic eruptions that had globally polluted air. Why the Fukushima nuclear accident should be treated in a different way when these radioactive materials were originally from ground and they will eventually find their way back into a soil? The reality is not as simple and a remarkable difference needs to be put into consideration: nuclear wastes are highly condensed because humans worked to make them that way so that they can be used as nuclear fuel or atomic bomb. Trouble is that one finds in nuclear waste many radioactive substances with very long half-life times that would stay hazardous for many future generations. Most ashes from big volcanic eruption find their way to the ground within several years or so. Once they landed the surface of the ground, they are no different from the soil and will become basically harmless dusts. On the contrary, for some part of nuclear waste it will take over 10,000 years to become almost harmless. In general any human being does not feel a real threat on anything that would happen far beyond his/her life span. People usually are optimistic by saying that someone in a future would come up with a perfect solution to take care of the problems associated with nuclear waste. This argument reflects a very irresponsible attitude of people working on the project involving nuclear fuel. The problems in Fukushima nuclear accidents are mainly resulting from such an irresponsible attitude. Is it ever possible to see a happy end with any nuclear power station based on such a human mentality?

  2. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-15

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident.

  3. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    International Nuclear Information System (INIS)

    1986-11-01

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident

  4. Utilization technique of 'radiation management manual in medical field (2012).' What should be learnt from the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Kikuchi, Toru

    2014-01-01

    From the abstract of contents of the 'Radiation management manual in medical field (2012),' the utilization technique of the manual is introduced. Introduced items are as follows: (1) Exposure management; exposure management for radiation medical workers, patients, and citizens in the medical field, and exposure management for radiation workers and citizens involved in the emergency work related to the Fukushima nuclear accident, (2) Health management; health management for radiation medical workers, (3) Radiation education: Education/training for radiation medical workers, and radiation education for health care workers, (4) Accident and emergency measures; emergency actions involved in the radiation accidents and radiation medicine at medical facilities

  5. Management of foodstuffs after nuclear accidents

    International Nuclear Information System (INIS)

    1991-01-01

    A model for the management of foodstuffs after nuclear accidents is presented. The model is a synthesis of traditions and principles taken from both radioactive protection and management of food. It is based on cooperation between the Nordic countries and on practical experience gained from the Chernobyl accident. The aim of the model is to produce a basis for common plans for critical situations based on criteria for decision making. In the case of radioactive accidents it is important that the protection of the public and of the society is handled in a positive way. The model concerns production, marketing and consumption of food and beverage. The overall aim is that the radiation doses should be as low and harmless to health for individual members of the public. (CLS) 35 refs

  6. Reflections on the emergency preparations and responses of China to Fukushima nuclear accident in Japan

    International Nuclear Information System (INIS)

    Chen Xiaoqiu; Li Bing; Yu Shaoqing

    2012-01-01

    This paper reviewed the emergency response of Japan in Fukushima nuclear accident, provided and discussed the issues should be of concern on emergency preparedness and response in future: (1) modifying the existing emergency preparedness and response system; (2) consolidating the concept of emergency preparedness as the ultimate level of defense-in-depth; (3) promoting the emergency response decision-making support capabilities; (4) valuing the information opening of involving nuclear news and radiation environmental information. (authors)

  7. Traffic Accidents Involving Cyclists Identifying Causal Factors Using Questionnaire Survey, Traffic Accident Data, and Real-World Observation.

    Science.gov (United States)

    Oikawa, Shoko; Hirose, Toshiya; Aomura, Shigeru; Matsui, Yasuhiro

    2016-11-01

    The purpose of this study is to clarify the mechanism of traffic accidents involving cyclists. The focus is on the characteristics of cyclist accidents and scenarios, because the number of traffic accidents involving cyclists in Tokyo is the highest in Japan. First, dangerous situations in traffic incidents were investigated by collecting data from 304 cyclists in one city in Tokyo using a questionnaire survey. The survey indicated that cyclists used their bicycles generally while commuting to work or school in the morning. Second, the study investigated the characteristics of 250 accident situations involving cyclists that happened in the city using real-world bicycle accident data. The results revealed that the traffic accidents occurred at intersections of local streets, where cyclists collided most often with vehicles during commute time in the morning. Third, cyclists' behavior was observed at a local street intersection in the morning in the city using video pictures. In one hour during the morning commute period, 250 bicycles passed through the intersection. The results indicated that one of the reasons for traffic accidents involving cyclists might be the combined effect of low visibility, caused by the presence of box-like building structures close to the intersections, and the cyclists' behavior in terms of their velocity and no confirming safety. It was observed that, on average, bicycle velocity was 3.1 m/s at the initial line of an intersection. The findings from this study could be useful in developing new technologies to improve cyclist safety, such as alert devices for cyclists and vehicle drivers, wireless communication systems between cyclists and vehicle drivers, or advanced vehicles with bicycle detection and collision mitigation systems.

  8. Empirical Risk Analysis of Severe Reactor Accidents in Nuclear Power Plants after Fukushima

    OpenAIRE

    Kaiser, Jan Christian

    2012-01-01

    Many countries are reexamining the risks connected with nuclear power generation after the Fukushima accidents. To provide updated information for the corresponding discussion a simple empirical approach is applied for risk quantification of severe reactor accidents with International Nuclear and Radiological Event Scale (INES) level ≥5. The analysis is based on worldwide data of commercial nuclear facilities. An empirical hazard of 21 (95% confidence intervals (CI) 4; 62) severe accidents am...

  9. Analysis of simulation results of damaged nuclear fuel accidents at NPPs with shell-type nuclear reactors

    Directory of Open Access Journals (Sweden)

    Igor L. Kozlov

    2015-03-01

    Full Text Available Lessons from the accident at the Fukushima Daiichi NPP made it necessary to reevaluate and intensificate the work on modeling and analyzing various scenarios of severe accidents with damage to the nuclear fuel in the reactor, containment and spent nuclear fuel storage pool with the expansion of the primary initiating event causes group listing. Further development of computational tools for modeling the explosion prevention criteria as to steam and gas mixtures, considering the specific thermal-hydrodynamic conditions and mechanisms of explosive situations arrival at different stages of a severe accident development, is substantiated. Based on the analysis of the known shell-type nuclear reactors accidents results the explosion safety thermodynamic criteria are presented, the parameters defining the steam and gas explosions conditions are found, the need to perform the further verification and validation of deterministic codes serving to simulate general accident processes behavior as well as phase-to-phase interaction calculated dependencies is established. The main parameters controlling and defining the criteria explosion safety effective regulation areas and their optimization conditions are found.

  10. Instructions on the nuclear critical accident and how to correspond to future

    International Nuclear Information System (INIS)

    Kimura, Itsuro

    2000-01-01

    The nuclear accident occurred at Tokai Works of the JCO Co., Ltd. is a simple but disallowable one formed by neglecting possibility of nuclear fission chain reaction, one of three dangers specific to nuclear power facilities and by feeding middle concentrated uranium solution with more than critical mass into a precipitation tank. As a man consumed most of his life to nuclear power, it is to occur a critical accident forming about 50 previous examples in the world and about 10 victims at Tokai-mura the most earnestly promoting its experiment and analysis and to generate new victims, what was thought to be the most regrettable in this accident. How the previous experiences and results in Tokai-mura could be transmitted to the JCO Co., Ltd. ? This was a large alarm-bell for persons engaging to R and D on nuclear power. As this accident was much deplorable and apological for the common public, it must be carried out to thoroughly analyze its causes, to establish its future responses, and to promote its essential countermeasures. As it is important to open informations on its contents, it is hopeful not to over-exaggerate and over-differentiate the accident, to calmly and scientifically analyze the risk as well as in the other accidents, and to construct actually effective countermeasures. (G.K.)

  11. Characteristics of motorcyclists involved in accidents between motorcycles and automobiles.

    Science.gov (United States)

    Oliveira, Amanda Lima de; Petroianu, Andy; Gonçalves, Dafne Maria Villar; Pereira, Gisele Araújo; Alberti, Luiz Ronaldo

    2015-01-01

    traffic accidents are one of the main causes of death and disability, with motorcyclists representing the great majority of both the victims and the perpetrators. this work studied the characteristics of motorcyclists injured in accidents involving motorcycles and automobiles. this study sought to interview 100 motorcyclists who had been injured in collisions between motorcycles and automobiles, and who were undergoing emergency hospital treatment in the region of Belo Horizonte, Brazil. The questionnaires included demographic information (age, gender, skin color, education level, profession) and questions about years of licensed driving practice, how often they would drive an automobile, how long they had had a motorcycle driver's license, how often they would ride a motorcycle, the number of prior accidents involving a car, and the number of prior accidents not involving a car. of the 100 consecutive accidents studied, 91 occurred with men and 9 with women, aged between 16 and 79 (m = 29 ± 11) years. Regarding their reason for using a motorcycle, 83% reported using it for transport, 7% for work, and 10% for leisure. Most of these accident victims had secondary or higher education (47%). Of the motorcyclists who held a car driver's license, 68.3% drove the vehicle daily or weekly and held the license for more than one year. Sixty-seven percent of the accident victims used a motorcycle daily and had a motorcycle driver's license for at least one year. among the motorcyclists injured, most were men aged 20 years or older, with complete secondary education, and experienced in driving both motorcycles and cars, indicating that recklessness while driving the motorcycle is the main cause of traffic accidents.

  12. Economic damage caused by a nuclear reactor accident

    International Nuclear Information System (INIS)

    Goemans, T.; Schwarz, J.J.

    1988-01-01

    This study is directed towards the estimation of the economic damage which arises from a severe possible accident with a newly built 1000 MWE nuclear power plant in the Netherlands. A number of cases have been considered which are specified by the weather conditions during and the severity of the accident and the location of the nuclear power plant. For each accident case the economic damage has been estimated for the following impact categories: loss of the power plant, public health, evacuation and relocation of population, export of agricultural products, working and living in contaminated regions, decontamination, costs of transportation and incoming foreign tourism. The consequences for drinking water could not be quantified adequately. The total economic damage could reach 30 billion guilders. Besides the power plant itself, loss of export and decreasing incoming foreign tourism determine an important part of the total damage. 12 figs.; 52 tabs

  13. Emergency response and nuclear risk governance. Nuclear safety at nuclear power plant accidents; Notfallschutz und Risk Governance. Zur nuklearen Sicherheit bei Kernkraftwerksunfaellen

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlen, Johannes

    2014-07-01

    The present study entitled ''Emergency Response and Nuclear Risk Governance: nuclear safety at nuclear power plant accidents'' deals with issues of the protection of the population and the environment against hazardous radiation (the hazards of nuclear energy) and the harmful effects of radioactivity during nuclear power plant accidents. The aim of this study is to contribute to both the identification and remediation of shortcomings and deficits in the management of severe nuclear accidents like those that occurred at Chernobyl in 1986 and at Fukushima in 2011 as well as to the improvement and harmonization of plans and measures taken on an international level in nuclear emergency management. This thesis is divided into a theoretical part and an empirical part. The theoretical part focuses on embedding the subject in a specifically global governance concept, which includes, as far as Nuclear Risk Governance is concerned, the global governance of nuclear risks. Due to their characteristic features the following governance concepts can be assigned to these risks: Nuclear Safety Governance is related to safety, Nuclear Security Governance to security and NonProliferation Governance to safeguards. The subject of investigation of the present study is as a special case of the Nuclear Safety Governance, the Nuclear Emergency governance, which refers to off-site emergency response. The global impact of nuclear accidents and the concepts of security, safety culture and residual risk are contemplated in this context. The findings (accident sequences, their consequences and implications) from the analyses of two reactor accidents prior to Fukushima (Three Mile Iceland in 1979, Chernobyl in 1986) are examined from a historical analytical perspective and the state of the Nuclear Emergency governance and international cooperation aimed at improving nuclear safety after Chernobyl is portrayed by discussing, among other topics, examples of &apos

  14. Nuclear Measurement Technologies and Solutions Implemented during Nuclear Accident at Fukushima

    International Nuclear Information System (INIS)

    Morichi, M.; Toubon, H.; Bronson, Frazier; Venkataraman, Ram; Beaujoin, J.; Dubart, P.

    2013-06-01

    Fukushima accident imposed a stretch to nuclear measurement operational approach requiring in such emergency situation: fast concept development, fast system integration, deployment and start-up in a very short time frame. This paper is describing the Nuclear Measurement that AREVA-BUNM (CANBERRA) has realized and foresight at Fukushima accident site describing the technical solution conceived developed and deployed at Fukushima NPP for the process control of the treatment system of contaminated water. A detailed description of all levels design choices, from detection technologies to system architecture is offer in the paper as well as the read-out and global data management system. This paper describes also the technical choices executed and put in place to overcome the challenges related to the high radiological contamination on site. (authors)

  15. Reactor accidents and nuclear catastrophes

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Linde, H.J.

    1979-01-01

    Assuming some preliminary knowledge of the fundamentals of atomic physics, the book describes the effects of ionizing radiation on the human organism. In order to assess the potential hazards of reactor accidents and the extent of a nuclear catastrophe, the technology of power generation in nuclear power stations is presented together with its potential dangers as well as the physical and medical processes occurring during a nuclear weapons explosion. The special medical aspects are presented which range from first aid in the case of a catastrophe to the accute radiation syndrome, the treatment of burns to the therapy of late radiolesions. Finally, it is confirmed that the treatment of radiation injured persons does not give rise to basically new medical problems. (orig./HP) [de

  16. 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

  17. Preliminary evaluation of the Accident Response Mobile Manipulation System for accident site salvage operations

    International Nuclear Information System (INIS)

    Trujillo, J.M.; Morse, W.D.; Jones, D.P.

    1994-01-01

    This paper describes and evaluates operational experiences with the Accident Response Mobile Manipulation System (ARMMS) during simulated accident site salvage operations which might involve nuclear weapons. The ARMMS is based upon a teleoperated mobility platform with two Schilling Titan 7F Manipulators

  18. Main lessons based on the Chernobyl nuclear power plant accident liquidation experience

    International Nuclear Information System (INIS)

    Vasil'chenko, V.N.; Nosovskij, A.V.

    2006-01-01

    The authors review the main lessons of the Chernobyl nuclear power plant accident and the liquidation of its consequences in the area of the nuclear reactors safety operation, any major accident management, liquidation accident consequences criteria, emergency procedures, preventative measures and treatment irradiated victims, the monitoring methods etc. The special emphasis is put on the questions of the emergency response and the antiaccidental measures planning in frame of international cooperation program

  19. Study on public awareness of utilizing nuclear power in China. Changes in public awareness after the accident of Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Xu, Ting; Wakabayashi, Toshio

    2012-01-01

    The purpose of this study is to clarify public awareness of utilizing nuclear power in China and to determine the effects of the accident of Fukushima Daiichi nuclear power plants. Web online surveys were carried out before and after the accident of Fukushima Daiichi nuclear power plants. The online survey before the accident of Fukushima Daiichi nuclear power plants had 4,255 adult respondents consisting of 1,851 males and 2,404 females. The online survey after the accident had 721 respondents consisting of 406 males and 315 females. The two online surveys about the attitude toward nuclear power plants consisted of 37 items, such as the necessity of nuclear power plants, the reliability of safety, and government confidence. As a result, respondents of the online surveys in China consider that nuclear energy is more important than the anxiety of accident. On the other hand, women have sensation of fear for the accident of Fukushima Daiichi nuclear power plants and radiation. (author)

  20. Lessons learned from our accident at Fukushima nuclear power stations

    International Nuclear Information System (INIS)

    Kawano, A.

    2012-01-01

    This paper is given in order to share the detailed information on the Fukushima Accident which occurred on March 11, 2011, and the lessons learned from it which worldwide nuclear experts might currently have more interest in. The paper first reflects how the facilities were damaged by a very strong earthquake and a series of beyond design-basis tsunamis. The earthquake caused loss of all off-site electric power at Fukushima Daiichi Nuclear Power Station (1F), and the following series of tsunami made all emergency diesel generators except one for Unit 6 and most of DC batteries inoperable and severely damaged most of the facilities located on the ocean side. Thus all the units at 1F resulted in the loss of cooling function and ultimate heat sink for a long time period. TEPCO focused on restoration of the instruments and lights in the Main Control Room (MCR), preparation of alternative water injection and venting of Primary Containment Vessel (PCV) in the recovery process. However, the workers faced a lot of difficulties such as total darkness, repeated aftershocks, high radiation dose, a lot of debris on the ground, loss of communication means, etc. Massive damages by the tsunami and lack of necessary equipments and resources hampered a quick recovery. It eventually resulted in the severe core damage of Unit 1, 2, and 3 and also the hydrogen explosions in the reactor buildings of Unit 1, 3, and 4. This paper finally extracts the lessons learned from the accident and proposes the countermeasures, such as flood protection for essential facilities, preparation of practical and effective tools, securing communication means and so on. These would help the people involved in the nuclear industries all over the world properly understand the accident and develop their own countermeasures appropriately. (authors)

  1. Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

    International Nuclear Information System (INIS)

    Youngen, G.

    1988-10-01

    The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant's operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ''onsite'' response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world's collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously

  2. Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Youngen, G.

    1988-10-01

    The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

  3. Severe accident sequences simulated at the Grand Gulf Nuclear Station

    International Nuclear Information System (INIS)

    Carbajo, J.J.

    1999-01-01

    Different severe accident sequences employing the MELCOR code, version 1.8.4 QK, have been simulated at the Grand Gulf Nuclear Station (Grand Gulf). The postulated severe accidents simulated are two low-pressure, short-term, station blackouts; two unmitigated small-break (SB) loss-of-coolant accidents (LOCAs) (SBLOCAs); and one unmitigated large LOCA (LLOCA). The purpose of this study was to calculate best-estimate timings of events and source terms for a wide range of severe accidents and to compare the plant response to these accidents

  4. Report on the accident at the Chernobyl Nuclear Power Station

    International Nuclear Information System (INIS)

    1987-12-01

    This report presents the compilation of information obtained by various organizations regarding the accident (and the consequences of the accident) that occurred at Unit 4 of the nuclear power station at Chernobyl in the USSR on April 26, 1986. Each organization has independently accepted responsibility for one or more chapters. The specific responsibility of each organization is indicated. The various authors are identified in a footnote to each chapter. Very briefly the other chapters cover: the design of the Chernobyl nuclear station Unit 4; safety analyses for Unit 4; the accident scenario; the role of the operator; an assessment of the radioactive release, dispersion, and transport; the activities associated with emergency actions; and information on the health and environmental consequences from the accident. These subjects cover the major aspects of the accident that have the potential to present new information and lessons for the nuclear industry in general. The task of evaluating the information obtained in these various areas and the assessment of the potential implications has been left to each organization to pursue according to the relevance of the subject to their organization. Those findings will be issued separately by the cognizant organizations. The basic purpose of this report is to provide the information upon which such assessments can be made

  5. Fifteenth nuclear accident dosimetry intercomparison study: August 14--22, 1978

    International Nuclear Information System (INIS)

    Sims, C.S.

    1979-05-01

    The fifteenth in the continuing series of Nuclear Accident Dosimetry Intercomparison Studies was held August 14--22, 1978 at the Oak Ridge National Laboratory. The Health Physics Research Reactor, operated in the pulse mode, served as the radiation source. Using different shielding configurations, nuclear accidents with three different neutron and gamma spectra were simulated. Participants from 19 organizations, the most in the history of the studies, exposed dosimeters set up as area monitors as well as dosimeters mounted on phantoms for personnel monitoring. Although many participants performed accurate measurements, the composite dose results, in the majority of cases, failed to meet established nuclear criticality accident dosimetry guidelines which suggest accuracies of +- 25% for neutron dose and +- 20% for gamma dose. This indicates that many participants need to improve their dosimetry systems, their analytical techniques, or both

  6. Overview of training methodology for accident management at nuclear power plants

    International Nuclear Information System (INIS)

    2005-04-01

    Many IAEA Member States operating nuclear power plants (NPPs) are at present developing accident management programmes (AMPs) for the prevention and mitigation of severe accidents. However, the level of implementation varies significantly between NPPs. The exchange of experience and best practices can considerably contribute to the quality and facilitate the implementation of AMPs at the plants. The main objective of this publication is to describe available material and technical support tools that can be used to support training of the personnel involved in the accident management (AM), and to highlight the current status of their application. The focus is on those operator aids that can help the plant personnel to take correct actions during an emergency to prevent and mitigate consequences of a severe accident. The second objective is to describe the available material for the training courses of those people who are responsible of the AMP development and implementation of an individual plant. The third objective is to collect a compact set of information on various aspects of AM training into a single publication. In this context, the AM personnel includes both the plant staff responsible for taking the decision and actions concerning preventive and mitigative AM and the persons involved in the management of off-site releases. Thus, the scope of this publication is on the training of personnel directly involved in the decisions and execution of the SAM actions during progression of an accident. The integration of training into the AMP development and implementation is summarized. The technical AM support tools and material are defined as operator aids involving severe accident guidelines, various computational aids and computerized tools. The operator aids make also an essential part of the training tools. The simulators to be applied for the AM training have been developed or are under development by various organizations in order to support the training on

  7. 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.)

  8. Root causes and impacts of severe accidents at large nuclear power plants.

    Science.gov (United States)

    Högberg, Lars

    2013-04-01

    The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long-lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities.

  9. Root Causes and Impacts of Severe Accidents at Large Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hoegberg, Lars

    2013-01-01

    The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities

  10. Root Causes and Impacts of Severe Accidents at Large Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Hoegberg, Lars

    2013-04-15

    The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities.

  11. Accident management insights after the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Degueldre, Didier; Viktorov, Alexandre; Tuomainen, Minna; Ducamp, Francois; Chevalier, Sophie; Guigueno, Yves; Tasset, Daniel; Heinrich, Marcus; Schneider, Matthias; Funahashi, Toshihiro; Hotta, Akitoshi; Kajimoto, Mitsuhiro; Chung, Dae-Wook; Kuriene, Laima; Kozlova, Nadezhda; Zivko, Tomi; Aleza, Santiago; Jones, John; McHale, Jack; Nieh, Ho; Pascal, Ghislain; ); Nakoski, John; Neretin, Victor; Nezuka, Takayoshi; )

    2014-01-01

    events and accidents at NPPs, and what additional measures should be considered as an accident progresses to the severe accident stage. Insights are provided on the experiences and practices existing or being proposed in the NEA member states, as well as new findings from post-Fukushima studies. Emphasis is placed on identifying commendable practices that support enhanced and integrated on-site accident management response and decision-making by NPP operators. The report provides information (including commendable practices) useful for regulatory authorities to consider as they implement enhancements to their regulatory framework in the area of integrated accident management building on the lessons learnt from the Fukushima Daiichi NPP accident. The report's insights also should be useful to regulatory authorities, operating organisations and others in the nuclear safety community for addressing accident management issues such as procedures and guidelines, equipment, infrastructure and instrumentation, and human and organisational resources. Factors such as accidents involving spent fuel pools, multi-unit aspects of accident management, the interface between onsite and off-site organisations and resources, and degradation of the surrounding infrastructure are also discussed. (authors)

  12. Characteristics of motorcyclists involved in accidents between motorcycles and automobiles

    Directory of Open Access Journals (Sweden)

    Amanda Lima de Oliveira

    2015-02-01

    Full Text Available Introduction: traffic accidents are one of the main causes of death and disability, with motorcyclists representing the great majority of both the victims and the perpetrators. Objective: this work studied the characteristics of motorcyclists injured in accidents involving motorcycles and automobiles. Method: this study sought to interview 100 motorcyclists who had been injured in collisions between motorcycles and automobiles, and who were undergoing emergency hospital treatment in the region of Belo Horizonte, Brazil. The questionnaires included demographic information (age, gender, skin color, education level, profession and questions about years of licensed driving practice, how often they would drive an automobile, how long they had had a motorcycle driver’s license, how often they would ride a motorcycle, the number of prior accidents involving a car, and the number of prior accidents not involving a car. Results: of the 100 consecutive accidents studied, 91 occurred with men and 9 with women, aged between 16 and 79 (m = 29 ± 11 years. Regarding their reason for using a motorcycle, 83% reported using it for transport, 7% for work, and 10% for leisure. Most of these accident victims had secondary or higher education (47%. Of the motorcyclists who held a car driver’s license, 68.3% drove the vehicle daily or weekly and held the license for more than one year. Sixty-seven percent of the accident victims used a motorcycle daily and had a motorcycle driver’s license for at least one year. Conclusion: among the motorcyclists injured, most were men aged 20 years or older, with complete secondary education, and experienced in driving both motorcycles and cars, indicating that recklessness while driving the motorcycle is the main cause of traffic accidents.

  13. Medical and policy considerations for nuclear and radiation accidents, incidents and terrorism.

    Science.gov (United States)

    Gale, Robert Peter

    2017-11-01

    The purpose of this review is to address the increasing medical and public concern regarding the health consequences of radiation exposure, a concern shaped not only by fear of another Chernobyl or Fukushima nuclear power facility accident but also by the intentional use of a nuclear weapon, a radiological dispersion device, a radiological exposure device, or an improved nuclear device by rogue states such as North Korea and terrorist organizations such as Al Qaeda and ISIS. The United States has the medical capacity to respond to a limited nuclear or radiation accident or incident but an effective medical response to a catastrophic nuclear event is impossible. Dealing effectively with nuclear and radiation accidents or incidents requires diverse strategies, including policy decisions, public education, and medical preparedness. I review medical consequences of exposures to ionizing radiations, likely concomitant injuries and potential medical intervention. These data should help haematologists and other healthcare professionals understand the principles of medical consequences of nuclear terrorism. However, the best strategy is prevention.

  14. 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

  15. Pregnancy outcome in women involved in road traffic accidents

    African Journals Online (AJOL)

    bbshehu

    December, 2002, was undertaken to determine the incidence, type of injury and pregnancy outcome. Results: One hundred and forty nine women ... road traffic accidents.6 Pregnant mothers could also be involved in road traffic accident.6 ... use of helmet lowers the risk of traumatic brain injury. 11 and a case is made for the ...

  16. 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

  17. Tracing nuclear elements released by Fukushima Nuclear Power Plant accident

    Science.gov (United States)

    Tsujimura, M.; Onda, Y.; Abe, Y.; Hada, M.; Pun, I.

    2011-12-01

    Radioactive contamination has been detected in Fukushima and the neighboring regions due to the nuclear accident at Fukushima Daiichi Nuclear Power Plant (NPP) following the earthquake and tsunami occurred on 11th March 2011. The small experimental catchments have been established in Yamakiya district, Kawamata Town, Fukushima Prefecture, located approximately 35 km west from the Fukushima NPP. The tritium (3H) concentration and stable isotopic compositions of deuterium and oxygen-18 have been determined on the water samples of precipitation, soil water at the depths of 10 to 30 cm, groundwater at the depths of 5 m to 50 m, spring water and stream water taken at the watersheds in the recharge and discharge zones from the view point of the groundwater flow system. The tritium concentration of the rain water fell just a few days after the earthquake showed a value of approximately 17 Tritium Unit (T.U.), whereas the average concentration of the tritium in the precipitation was less than 5 T.U. before the Fukushima accident. The spring water in the recharge zone showed a relatively high tritium concentration of approximately 12 T.U., whereas that of the discharge zone showed less than 5 T.U. Thus, the artificial tritium was apparently injected in the groundwater flow system due to the Fukushima NPP accident, whereas that has not reached at the discharge zone yet. The monitoring of the nuclear elements is now on going from the view points of the hydrological cycles and the drinking water security.

  18. The role of post accident chemistry data in nuclear safety

    International Nuclear Information System (INIS)

    Bradshaw, R.W.; Caruthers, G.F.

    1982-01-01

    The NRC instituted the NUREG-0737 requirements as implementation of the Post-TMI Action Plan in October, 1980. Among these requirements was the capability to obtain chemistry samples of the reactor coolant and containment building atmosphere under post accident conditions. The quantitative criteria were, in general, beyond the capabilities of existing plant systems. As a consequence the nuclear industry expended substantial efforts to design and install the post-accident sampling systems necessary to comply with these criteria. With such efforts essentially complete, the task remains to establish the role that data provided by these systems would play in mitigating the consequences of a nuclear plant accident. This role definition must include a characterization of the timing and priority for the post accident chemistry data. This paper defines that role using the Safety Level and Safety Function concepts as a matrix

  19. Health effects of the nuclear accident at Three Mile Island

    International Nuclear Information System (INIS)

    Fabrikant, J.I.

    1980-05-01

    Between March 28 and April 15, 1979 the collective dose resulting from the radioactivity released to the population living within a 50-mile radius of the Three Mile Island nuclear plant was about 2000 person-rems, less than 1% of the annual natural background level. The average dose to a person living within 5 miles of the nuclear plant was less than 10% of annual background radiation. The maximum estimated radiation dose received by any one individual in the general population (excluding the nuclear plant workers) during the accident was 70 mrem. The doses received by the general population as a result of the accident were so small that there will be no detectable additional cases of cancer, developmental abnormalities, or genetic ill-health. Three Three Mile Island nuclear workers received radiation doses of about 3 to 4 rem, exceeding maximum permissible quarterly dose of 3 rem. The major health effect of the accident at Three Mile Island was that of a pronounced demoralizing effect on the general population in the Three Mile Island area, including teenagers and mothers of preschool children and the nuclear plant workers. However, this effect proved transient in all groups studied except the nuclear workers

  20. Trucks involved in fatal accidents codebook 2008.

    Science.gov (United States)

    2011-01-01

    This report provides documentation for UMTRIs file of Trucks Involved in Fatal Accidents : (TIFA), 2008, including distributions of the code values for each variable in the file. The 2008 : TIFA file is a census of all medium and heavy trucks invo...

  1. Impact of accidents on organizational aspects of nuclear utilities

    OpenAIRE

    Spurgin, A. J.; Stupples, D.

    2012-01-01

    This paper applies the Beer Viable Systems Model (VSM) approach to the study of nuclear accidents. It relates how organizational structures and rules are affected by accidents in the attempt to improve safety and reduce risk. The paper illustrates this process with reference to a number of accidents. The dynamic cybernetic aspect of the VSM approach to organizations yields a better understanding of the need for good decision-making to minimize risk and how organizations really operate.

  2. On the Perspective of Nuclear Energy Following the Fukushima Accident

    International Nuclear Information System (INIS)

    Cavlina, N.; Knapp, V.; Pevec, D.

    2011-01-01

    Future of nuclear energy after accidents on the nuclear power station Daichi at Fukushima has been questioned and discussed. At present 433 nuclear power plants are contributing with about 14% to the world production of electricity. Looking at regional distribution of nuclear power plants, the largest number of nuclear power plants (143) is operating in European Union (EU) producing around one third of its electric energy. EU leads the world in the use of nuclear energy, with very good geopolitical and strategic reasons. Without its own oil and gas resources and with high dependence on external supplier EU has a problem in conducting independent foreign policy. As industrially and technologically developed region of the world EU intends to play a leading role in efforts to reduce C0 2 emission and limit the global temperature increase to below 2 degrees of C. Also, nuclear energy is important for international competitiveness of European industry. After the Fukushima accident, and in the light of that event, many expert groups have revaluated the safety of operating nuclear power plants. Whilst they do not find faults with basic conceptions, some safety related improvements will be recommended. As regards to nuclear energy in EU, irrespectively of short or medium term political decisions, long term geopolitical and strategic reasons that stimulated strong nuclear development in the past, continue to exist. Thus, we may expect continuation of nuclear development in EU without essential delays. As it appears, pending post-Fukushima nuclear safety analysis and applying safety improvements where needed, Fukushima accident will not stop nuclear development in industrially and technologically developed regions of the world. In view of frequently expressed claims that nuclear fuel resources are insufficient for the long term large scale production of nuclear energy we also give a short comment on the sustainability of nuclear energy. (author)

  3. Manual on the medical management of individuals involved in radiation accidents

    International Nuclear Information System (INIS)

    Swindon, T.N.

    1991-09-01

    This manual is concerned with accidents or emergencies which involve sources of ionizing radiation. It does not cover other forms of radiation such as non-ionizing radiation (ultra-violet, light, radiofrequency radiations), heat, etc. Most radiation accidents have involved individuals either at the workplace or with medical misadministrations; they have received external exposure from X-ray or gamma-ray sources or have been contaminated with radioactive material. A few members of the public have also been involved through misadventures with radioactive sources although these may not be thought of as accidents; more commonly, they are referred to as 'incidents'. For the purpose of this manual, there is not differentiation between an accident and an incident, as the medical care required is the same in both situations. Some of the reference papers are reprinted at the back of the manual. 17 refs., 12 tabs., 9 figs

  4. Nuclear Accidents Archive Knowledge Organization System Portal “NAAKOS”: An Application of Semantic Technologies in the Nuclear Domain

    International Nuclear Information System (INIS)

    Atieh, T.

    2016-01-01

    Full text: In line with the IAEA Action Plan on Nuclear Safety, the IAEA was requested to assist Member States enhancing transparency and effectiveness of communication among operators, regulators and various international organizations, and supporting wide dissemination of safety related technical information on nuclear safety. In this context, the IAEA was further asked to analyse and preserve lessons learned from the Fukushima Daiichi NPP accident, as well as from past major incidents and radiological events. The IAEA NKM Section has launched the Nuclear Accidents Repository Portal Knowledge Organization System “NAAKOS” initiative which aims at collecting and preserving data, information, and knowledge related to nuclear accidents and making this knowledge available through one single access point, while ensuring their long term preservation. The NKM Section has developed the Nuclear Accidents Taxonomy which will be used, along other nuclear taxonomies, to enhance information retrieval. It would also include the use of semantic technologies, data mining and linked data to support users beyond the traditional search facilities. The overall objective is to assist to find predefined measures in a timely manner that could prevent, or at least minimize the adverse effects of incidents. (author

  5. Development of stable walking robot for accident condition monitoring on uneven floors in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Seog; Jang, You Hyun [Central Research Institute of Korea Hydro and Nuclear Power Company, Daejeon (Korea, Republic of)

    2017-04-15

    Even though the potential for an accident in nuclear power plants is very low, multiple emergency plans are necessary because the impact of such an accident to the public is enormous. One of these emergency plans involves a robotic system for investigating accidents under conditions of high radiation and contaminated air. To develop a robot suitable for operation in a nuclear power plant, we focused on eliminating the three major obstacles that challenge robots in such conditions: the disconnection of radio communication, falling on uneven floors, and loss of localization. To solve the radio problem, a Wi-Fi extender was used in radio shadow areas. To reinforce the walking, we developed two- and four-leg convertible walking, a floor adaptive foot, a roly-poly defensive falling design, and automatic standing recovery after falling methods were developed. To allow the robot to determine its location in the containment building, a bar code landmark reading method was chosen. When a severe accident occurs, this robot will be useful for accident condition monitoring. We also anticipate the robot can serve as a workman aid in a high radiation area during normal operations.

  6. Alcohol abuse and involvement in traffic accidents in the Brazilian population, 2013.

    Science.gov (United States)

    Damacena, Giseli Nogueira; Malta, Deborah Carvalho; Boccolini, Cristiano Siqueira; Souza, Paulo Roberto Borges de; Almeida, Wanessa da Silva de; Ribeiro, Lucas Sisinno; Szwarcwald, Célia Landmann

    2016-12-01

    Abstract This article aims to analyze alcohol abuse and frequent consumption according to sociodemographic characteristics and investigate the risk of greater involvement in traffic accidents, using data from the National Health Survey (PNS), 2013, Brazil. Events investigated were alcohol abuse and frequent consumption and if the individual was involved in a traffic accident and sustained an injury in the last 12 months. We investigated both events according to sociodemographic characteristics and assessed the association among them through multivariate logistic regression. The prevalence of alcohol abuse and frequent consumption was 6.1% for the population aged 18 years and over, 8.9% among men and 3.6% among women. The prevalence of involvement in traffic accidents was 3.1% in the general population and 6.1% among those who reported alcohol abuse. After controlling for sociodemographic factors, alcohol abuse and frequent consumption was significantly associated with traffic accidents. Considering a higher risk of involvement in traffic accidents among individuals who reported alcohol abuse and frequent consumption, monitoring blood alcohol concentration of drivers becomes a strategic possibility of intervention.

  7. Nuclear energy. Danger only in case of accidents?

    International Nuclear Information System (INIS)

    Scherb, Hagen; Voigt, Kristina; Kusmierz, Ralf

    2014-01-01

    The environmental impacts of nuclear energy are highly underestimated. Nuclear weapons, atomic bomb tests, and nuclear accidents are considered a danger for the environment and a human cancer risk. However, childhood leukemia is consistently elevated near nuclear power plants and the Chernobyl accident entailed elevated human birth sex ratios across Europe. We studied the annual sex ratio near nuclear facilities in Germany, France, and Switzerland at the municipality level. We will demonstrate that low doses of ionizing radiation cause effects in human beings. This is shown by strongly consistent spatial-temporal shifts in the human sex ratio trends in the vicinity of nuclear facilities. In the chosen countries complete official data on over 70 million gender specific annual births at the municipality level are available. By Lambert-93 coordinates (France) and GK3 coordinates (Germany, Switzerland) we determined the minimum distances of municipalities from major nuclear facilities. Spatial-temporal trend analyses of the annual sex ratio depending on municipalities' minimum distances from nuclear facilities were carried out. Applying ordinary linear logistic regression (jump or broken-stick functions) and non-linear logistic regression (Rayleigh functions) we demonstrate that the sex ratio at birth shows the influence of mutagenic ionizing radiation on human health. As important environmental chemical contaminants are also mutagenic, the usefulness of the sex ratio at birth as a genetic health indicator can be inferred by analogy.

  8. Nuclear energy. Danger only in case of accidents?

    Energy Technology Data Exchange (ETDEWEB)

    Scherb, Hagen; Voigt, Kristina; Kusmierz, Ralf [Helmholtz Zentrum Muenchen, Neuherberg (Germany). Inst. of Computational Biology

    2014-07-01

    The environmental impacts of nuclear energy are highly underestimated. Nuclear weapons, atomic bomb tests, and nuclear accidents are considered a danger for the environment and a human cancer risk. However, childhood leukemia is consistently elevated near nuclear power plants and the Chernobyl accident entailed elevated human birth sex ratios across Europe. We studied the annual sex ratio near nuclear facilities in Germany, France, and Switzerland at the municipality level. We will demonstrate that low doses of ionizing radiation cause effects in human beings. This is shown by strongly consistent spatial-temporal shifts in the human sex ratio trends in the vicinity of nuclear facilities. In the chosen countries complete official data on over 70 million gender specific annual births at the municipality level are available. By Lambert-93 coordinates (France) and GK3 coordinates (Germany, Switzerland) we determined the minimum distances of municipalities from major nuclear facilities. Spatial-temporal trend analyses of the annual sex ratio depending on municipalities' minimum distances from nuclear facilities were carried out. Applying ordinary linear logistic regression (jump or broken-stick functions) and non-linear logistic regression (Rayleigh functions) we demonstrate that the sex ratio at birth shows the influence of mutagenic ionizing radiation on human health. As important environmental chemical contaminants are also mutagenic, the usefulness of the sex ratio at birth as a genetic health indicator can be inferred by analogy.

  9. Iodine Prophylaxis and Nuclear Accidents

    International Nuclear Information System (INIS)

    Franic, Z.

    1998-01-01

    Iodine is a highly volatile element therefore being very mobile in the environment. It enters the metabolism of living organisms and is selectively taken up and concentrated in the thyroid gland. The plume (cloud-like formation) of radioactive material that might be released in the environment in the case of a serious nuclear accident, primarily consists of the radioactive isotopes of iodine. Among those, due to its decay properties, is the most important 131 I. The effective means of protecting the thyroid gland against exposure to radioactive iodine is an intake of stable iodine. Therefore, one of the central issues in the emergency planning is to determine whether and at which projected thyroid radiation dose stable iodine should be given to the population. The International Atomic Energy Agency (IAEA) set the generic optimized intervention value for iodine prophylaxis to 100 mGy of avertable committed dose to a thyroid.The prophylaxis is implemented by utilizing the pills of pills of potassium iodine (KI). The efficacy of KI in protecting the thyroid gland depends upon the time of intake relative to the start of exposure to radioactive iodine. The best results are obtained if KI is taken 1-2 hours before or immediately after the start of exposure. The recommended dosage, based upon the study performed by Il'in et.al. is 130 mg/day. KI should be taken at least three days after the acute exposure to radioiodine, to prevent accumulation in a thyroid gland of radioiodine excreted from the other compartments of the body. The largest epidemiological study on the effects of KI prophylaxis ever performed was the one in Poland after the Chernobyl accident. Stable iodine was given as single dose of KI solution to 10.5 million of children and 7 millions of adults. Among children no serious side effects were seen while only two adults (with previously recorded iodine sensitivity) had severe respiratory distresses. Polish experiences showed that rapid response to such

  10. Safety study on nuclear heat utilization system - accident delineation and assessment on nuclear steelmaking pilot plant

    International Nuclear Information System (INIS)

    Yoshida, T.; Mizuno, M.; Tsuruoka, K.

    1982-01-01

    This paper presents accident delineation and assessment on a nuclear steelmaking pilot plant as an example of nuclear heat utilization systems. The reactor thermal energy from VHTR is transported to externally located chemical process plant employing helium-heated steam reformer by an intermediate heat transport loop. This paper on the nuclear steelmaking pilot plant will describe (1) system transients under accident conditions, (2) impact of explosion and fire on the nuclear reactor and the public and (3) radiation exposure on the public. The results presented in this paper will contribute considerably to understanding safety features of nuclear heat utilization system that employs the intermediate heat transport loop and the helium-heated steam reformer

  11. Reinforcement of Defence-in-Depth: Modification Practice After the Fukushima Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Y.; Tang, H.; Mao, Q., E-mail: wangyuhong@cgnpc.com.cn [China Nuclear Power Design Co., Ltd Xia Meilin, Futian District, Shenzhen, Guangdong Province (China)

    2014-10-15

    The Fukushima Daiichi nuclear accident revealed the importance and demand for further reinforcement of defence in- depth. CGN (China General Nuclear Power Group) has made a complete safety assessment on CPR1000 nuclear power plants under construction in China. Dozens of modifications have been implemented based on the assessment findings and lessons learned from Fukushima nuclear accident, taking into account of PSA (Probabilistic Safety Analysis) and comparison analysis of the latest regulations and standards. These modifications help to enhance nuclear safety significantly for nuclear power plants under construction in China, and provide helpful modification guidance for nuclear power plants in operation of the same type. (author)

  12. The accident at the Chernobyl' nuclear power plant and its consequences

    International Nuclear Information System (INIS)

    1986-08-01

    The material is taken from the conclusions of the Government Commission on the causes of the accident at the fourth unit of the Chernobyl' nuclear power plant and was prepared by a team of experts appointed by the USSR State Committee on the Utilization of Atomic Energy. It contains general material describing the accident, its causes, the action taken to contain the accident and to alleviate its consequences, the radioactive contamination and health of the population and some recommendations for improving nuclear power safety. 7 annexes are devoted to the following topics: water-graphite channel reactors and operating experience with RBMK reactors, design of the reactor plant, elimination of the consequences of the accident and decontamination, estimate of the amount, composition and dynamics of the discharge of radioactive substances from the damaged reactor, atmospheric transport and radioactive contamination of the atmosphere and of the ground, expert evaluation and prediction of the radioecological state of the environment in the area of the radiation plume from the Chernobyl' nuclear power station, medical-biological problems. A separate abstract was prepared for each of these annexes. The slides presented at the post-accident review meeting are grouped in two separate volumes

  13. Assessment of risks of accidents and normal operation at nuclear power plants

    International Nuclear Information System (INIS)

    Savolainen, Ilkka; Vuori, Seppo.

    1977-01-01

    A probabilistic assessment model for the analysis of risks involved in the operation of nuclear power plants is described. With the computer code ARANO it is possible to estimate the health and economic consequences of reactor accidents both in probabilistic and deterministic sense. In addition the code is applicable to the calculation of individual and collective doses caused by the releases during normal operation. The estimation of release probabilities and magnitudes is not included in the model. (author)

  14. Measuring Risk Aversion for Nuclear Power Plant Accident: Results of Contingent Valuation Survey in Korea

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2015-01-01

    Within the evaluation of the external cost of nuclear energy, the estimation of the external cost of nuclear power plant (NPP) severe accident is one of the major topics to be addressed. For the evaluation of the external cost of NPP severe accident, the effect of public risk averse behavior against the group accidents, such as NPP accident, dam failure, must be addressed. Although the equivalent fatalities from a single group accident are not common and its risk is very small compared to other accidents, people perceive the group accident more seriously. In other words, people are more concerned about low probability/high consequence events than about high probability/low consequence events having the same mean damage. One of the representative method to integrate the risk aversion in the external costs of severe nuclear reactor accidents was developed by Eeckoudt et al., and he used the risk aversion coefficient, mainly based on the analysis of financial risks in the stock markets to evaluate the external cost of nuclear severe accident. However, the use of financial risk aversion coefficient to nuclear severe accidents is not appropriate, because financial risk and nuclear severe accident risk are entirely different. In this paper, the individual-level survey was conducted to measure the risk aversion coefficient and estimate the multiplication factor to integrate the risk aversion in the external costs of NPP severe accident. This study propose an integrated framework on estimation of the external cost associated with severe accidents of NPP considering public risk aversion behavior. The theoretical framework to estimate the risk aversion coefficient/multiplication factor and to assess economic damages from a hypothetical NPP accident was constructed. Based on the theoretical framework, the risk aversion coefficient can be analyzed by conducting public survey with a carefully designed lottery questions. Compared to the previous studies on estimation of the

  15. Measuring Risk Aversion for Nuclear Power Plant Accident: Results of Contingent Valuation Survey in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    Within the evaluation of the external cost of nuclear energy, the estimation of the external cost of nuclear power plant (NPP) severe accident is one of the major topics to be addressed. For the evaluation of the external cost of NPP severe accident, the effect of public risk averse behavior against the group accidents, such as NPP accident, dam failure, must be addressed. Although the equivalent fatalities from a single group accident are not common and its risk is very small compared to other accidents, people perceive the group accident more seriously. In other words, people are more concerned about low probability/high consequence events than about high probability/low consequence events having the same mean damage. One of the representative method to integrate the risk aversion in the external costs of severe nuclear reactor accidents was developed by Eeckoudt et al., and he used the risk aversion coefficient, mainly based on the analysis of financial risks in the stock markets to evaluate the external cost of nuclear severe accident. However, the use of financial risk aversion coefficient to nuclear severe accidents is not appropriate, because financial risk and nuclear severe accident risk are entirely different. In this paper, the individual-level survey was conducted to measure the risk aversion coefficient and estimate the multiplication factor to integrate the risk aversion in the external costs of NPP severe accident. This study propose an integrated framework on estimation of the external cost associated with severe accidents of NPP considering public risk aversion behavior. The theoretical framework to estimate the risk aversion coefficient/multiplication factor and to assess economic damages from a hypothetical NPP accident was constructed. Based on the theoretical framework, the risk aversion coefficient can be analyzed by conducting public survey with a carefully designed lottery questions. Compared to the previous studies on estimation of the

  16. Application of RASCAL code for multiunit accident in domestic nuclear sites

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Hyun; Jeong, Seung Young [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    All of domestic nuclear power plant sites are multiunit site (at least 5 - 6 reactors are operating), so this capability has to be quickly secured for nuclear licensee and institutes responsible for nuclear emergency response. In this study, source term and offsite dose from multiunit event were assessed using a computer code, RASCAL. An emergency exercise scenario was chosen to verify applicability of the codes to domestic nuclear site accident. Employing tools and new features of the code, such as merging more than two individual source terms and source term estimate for long term progression accident, main parameters and information in the scenario, release estimates and dose projections were performed. Radiological releases and offsite doses from multiunit accident were calculated using RASCAL.. A scenario, in which three reactors were damaged coincidently by a great natural disaster, was considered. Surrogate plants were chosen for the code calculation. Source terms of each damaged unit were calculated individually first, and then total source term and integrated offsite dose assessment data was acquired using a source term merge function in the code. Also comparison between LTSBO and LOCA source term estimate options was performed. Differences in offsite doses were caused by release characteristics. From LTSBO option, iodines were released much higher than LOCA. Also LTSBO source term release was delayed and the duration was longer than LOCA. This option would be useful to accidents which progress with much longer time frame than LOCA. RASCAL can be useful tool for radiological consequence assessment in domestic nuclear site accidents.

  17. 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

  18. Enlightenment on international cooperation for nuclear safety in China in light of Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Fu Jie; Feng Yi; Luan Haiyan; Meng Yue; Zhang Ou

    2013-01-01

    This thesis elaborates on the impact of Fukushima nuclear accident on global nuclear power development and subsequent international activities carried out by major countries. It analyses significance of international cooperation in ensuring nuclear safety and promoting nuclear power development and makes some suggestions to further strengthen the international cooperation on nuclear safety in China. (authors)

  19. Accident assessment under emergency situation in Daya Bay nuclear power station

    International Nuclear Information System (INIS)

    Yang Ling; Chen Degan; Lin Shumou; Fu Guohui

    2004-01-01

    The accident assessment under emergency situation includes the accident status evaluation and its consequence estimation. This paper introduces evaluation methods for accident status and its assistant computer system (SESAME-GNP) utilized during the emergency situation in Guangdong Daya Bay Nuclear Power Station (GNPS) in detail. At the same time, an improved accident consequence estimation system in GNPS (RACAS-GNP) is briefly described. With the improvement of the accident assessment systems, the capability of emergency response in GNPS is strengthened

  20. Organizational factors and reoccurrence protection on the JCO nuclear critical accident

    International Nuclear Information System (INIS)

    Takano, Kenichi

    2000-01-01

    A nuclear critical accident formed at a nuclear fuel conversion factory in Tokai-mura on September, 1999 became gradually clear not to be a simple human error formed at a level of workmen but to be an organizational error or accident relating to various organizational factors. As a nuclear power facility adopts a depth protection system fundamentally, a large accident with serious danger would not form only by a single trouble and a human error and unless some factors overlaps. By reviewing recent serious accidents and troubles, all of them seem to have a keyword of 'organizational factor'. In the JCO accident, there are some organizational factors such as a climate deviating from a manual, insufficient and loose check against change of procedure, reduction of operators from a reason of profit priority, attitude on priority of working efficiency, and so forth, which are partially common to the Chernobyl accident. Recently, accidents and troubles impossible to make them a cause of simple human error by a person but to have to say an organizational error, have increased. This trend seems to depend upon not only complication and scale-up of technology system but also graduate change of social and management systems operating them. Therefore, it seems to be necessary to introduce a concept of depth protection (multiple protection) in order to keep its reliability and safety when complicating and scaling-up of system. (G.K.)

  1. The role of nuclear reactor containment in severe accidents

    International Nuclear Information System (INIS)

    1989-04-01

    The containment is a structural envelope which completely surrounds the nuclear reactor system and is designed to confine the radioactive releases in case of an accident. This report summarises the work of an NEA Senior Group of Experts who have studied the potential role of containment in accidents exceeding design specifications (so-called severe accidents). Some possibilities for enhancing the ability of plants to reduce the risk of significant off-site consequences by appropriate management of the acident have been examined

  2. Support for Nuclear Explosive Safety Division, Department of Energy, Albuquerque Operations. Effects of a postulated uranium transportation accident

    International Nuclear Information System (INIS)

    Just, R.A.

    1997-10-01

    Transportation System Risk Assessments (TSRAs) document the degree of compliance of proposed DOE shipments of nuclear components with applicable federal regulations and the risk associated with the proposed shipments. TSRAs must often evaluate the consequences of possible transportation accidents involving uranium. If a relatively simple bounding analysis can show that the consequences resulting from a worst case scenario are acceptably low, a more time intensive and costly risk analysis can be avoided. A bounding consequence analysis has been prepared for a worst case noncriticality transportation accident involving the shipment of uranium. In the absence of a criticality incident, a fire or explosion are the only plausible mechanisms identified for dispersing significant amounts of solid hazardous material. Therefore, three very conservative bounding accidents are considered: (1) analysis of the postulated direct radiation exposure, (2) the airborne release of uranium due to a fire, and (3) the release of uranium into a waterway and uptake into drinking water. This report provides the equations, assumptions, and reference information used to predict the consequences of possible transportation accidents involving natural, depleted, and highly enriched uranium

  3. Examining accident reports involving autonomous vehicles in California.

    Directory of Open Access Journals (Sweden)

    Francesca M Favarò

    Full Text Available Autonomous Vehicle technology is quickly expanding its market and has found in Silicon Valley, California, a strong foothold for preliminary testing on public roads. In an effort to promote safety and transparency to consumers, the California Department of Motor Vehicles has mandated that reports of accidents involving autonomous vehicles be drafted and made available to the public. The present work shows an in-depth analysis of the accident reports filed by different manufacturers that are testing autonomous vehicles in California (testing data from September 2014 to March 2017. The data provides important information on autonomous vehicles accidents' dynamics, related to the most frequent types of collisions and impacts, accident frequencies, and other contributing factors. The study also explores important implications related to future testing and validation of semi-autonomous vehicles, tracing the investigation back to current literature as well as to the current regulatory panorama.

  4. Examining accident reports involving autonomous vehicles in California.

    Science.gov (United States)

    Favarò, Francesca M; Nader, Nazanin; Eurich, Sky O; Tripp, Michelle; Varadaraju, Naresh

    2017-01-01

    Autonomous Vehicle technology is quickly expanding its market and has found in Silicon Valley, California, a strong foothold for preliminary testing on public roads. In an effort to promote safety and transparency to consumers, the California Department of Motor Vehicles has mandated that reports of accidents involving autonomous vehicles be drafted and made available to the public. The present work shows an in-depth analysis of the accident reports filed by different manufacturers that are testing autonomous vehicles in California (testing data from September 2014 to March 2017). The data provides important information on autonomous vehicles accidents' dynamics, related to the most frequent types of collisions and impacts, accident frequencies, and other contributing factors. The study also explores important implications related to future testing and validation of semi-autonomous vehicles, tracing the investigation back to current literature as well as to the current regulatory panorama.

  5. A digest of the Nuclear Safety Division report on the Fukushima Dai-ichi accident seminar (4). Issues identified by the accident

    International Nuclear Information System (INIS)

    Moriyama, Kumiaki; Abe, Kiyoharu

    2013-01-01

    AESJ Nuclear Safety Division published 'Report on the Fukushima Dai-ichi Accident Seminar - what was wrong and what should been down in future-' which would be published as five special articles of the AESJ journal. The Fukushima Dai-ichi accident identified issues of several activities directly related with nuclear safety in the areas of safety design, severe accident management and safety regulations. PRA, operational experiences and safety research could not always contribute safety assurance of nuclear power plant so much. This article (4) summarized technical issues based on related facts of the accident as much as possible and discussed' what was wrong and what should be down in future'. Important issues were identified from defense-in-depth philosophy and lessons learned on safety design were obtained from accident progression analysis. Activities against external events and continuous improvements of safety standards based on latest knowledge were most indispensable. Strong cooperation among experts in different areas was also needed. (T. Tanaka)

  6. The Fukushima Daiichi Accident. Technical Volume 1/5. Description and Context of the Accident. 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

  7. ACCIDENTS AND UNSCHEDULED EVENTS ASSOCIATED WITH NON-NUCLEAR ENERGY RESOURCES AND TECHNOLOGY

    Science.gov (United States)

    Accidents and unscheduled events associated with non-nuclear energy resources and technology are identified for each step in the energy cycle. Both natural and anthropogenic causes of accidents or unscheduled events are considered. Data concerning these accidents are summarized. ...

  8. Iodine tablets and a nuclear accident

    International Nuclear Information System (INIS)

    Paile, W.

    1992-01-01

    Radioactive iodine is one of the major substances released during severe nuclear accidents. Radioactive iodine is easily gasified, and if present in fallout it can enter the lungs, and thereby the circulatory system, with the inhalation of air. Once in a body, radioactive iodine accumulates in the thyroid and may result in tumours in the thyroid and, in extreme cases, impaired thyroid function. Accumulation of radioactive iodine can be prevented by taking non-radioactive, 'cold' iodine as tablets. Iodine tablets dilute the radioactive iodine that has entered the body. A dose of iodine also paralyses the thyroid temporarily by saturating its iodine-carrying capacity. To be useful iodine tablets should be taken immediately when a radioactive emission has occurred. If the tablets are taken too early or too late, they give little protection. Iodine tablets should not be taken just to be on the safe side, since their use may involve harmful side effects. Dosing instructions should also be followed with care. (orig.)

  9. A Nordic approach to impact assessment of accidents with nuclear-propelled vessels

    International Nuclear Information System (INIS)

    Reistad, O.; Hustveit, S.; Palsson, S.E.; Hoe, S.; Lahtinen, J.

    2012-11-01

    The MareNuc project has identified the parameters in a graded approach to impact assessment for marine nuclear reactors. The graded approach is founded on the following elements: 1) More detailed understanding of previous accidents in nuclear-propelled vessels (initiating events, accident developments, release fractions), including release mechanisms (radionuclide retention in vessel construction); 2) Bench-marking of release scenarios using modelling tools applied in the Nordic countries, in addition to demonstration of generally accessible and free software developed by the IAEA; 3) Other systematic approaches to safety assessments of vessel port calls, and to the design and maintenance of emergency preparedness systems; More specifically, increased emphasis compared to earlier analysis after the Kursk accident is given to the engineered vessel barriers. Relevant standards from impact assessments for commercial nuclear power plants have been identified, such as from the NUREG series. The Nordic approaches to safety evaluation, impact assessments and emergency preparedness organisation was also reported as part of the project. The Canadian approach for international port calls was carefully reported and assessed as part of the project, and commended for its broad and comprehensive approach to reactor and vessel design for the nationalities involved, to the design and maintenance of emergency preparedness systems, and the well-structured and broad cooperation between civilian and military institutions. This approach goes beyond the current approach in the Nordic countries, also in the case of Norway, which experience regular port calls from allied nuclear navies. The overall result is a broader understanding in the Nordic countries for the importance of the various parameters for impact assessment of releases from marine reactors, and to the design and maintenance of an emergency preparedness organisation without detailed knowledge of the installation in question

  10. A Nordic approach to impact assessment of accidents with nuclear-propelled vessels

    Energy Technology Data Exchange (ETDEWEB)

    Reistad, O. [Institute for Energy Technology, Kjeller (Norway); Hustveit, S. [Norwegian Radiation Protection Authority, Oesteraes (Norway); Palsson, S.E. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Hoe, S. [Danish Emergency Management Agency, Birkeroed (Denmark); Lahtinen, J. [STUK, Helsinki (Finland)

    2012-11-15

    The MareNuc project has identified the parameters in a graded approach to impact assessment for marine nuclear reactors. The graded approach is founded on the following elements: 1) More detailed understanding of previous accidents in nuclear-propelled vessels (initiating events, accident developments, release fractions), including release mechanisms (radionuclide retention in vessel construction); 2) Bench-marking of release scenarios using modelling tools applied in the Nordic countries, in addition to demonstration of generally accessible and free software developed by the IAEA; 3) Other systematic approaches to safety assessments of vessel port calls, and to the design and maintenance of emergency preparedness systems; More specifically, increased emphasis compared to earlier analysis after the Kursk accident is given to the engineered vessel barriers. Relevant standards from impact assessments for commercial nuclear power plants have been identified, such as from the NUREG series. The Nordic approaches to safety evaluation, impact assessments and emergency preparedness organisation was also reported as part of the project. The Canadian approach for international port calls was carefully reported and assessed as part of the project, and commended for its broad and comprehensive approach to reactor and vessel design for the nationalities involved, to the design and maintenance of emergency preparedness systems, and the well-structured and broad cooperation between civilian and military institutions. This approach goes beyond the current approach in the Nordic countries, also in the case of Norway, which experience regular port calls from allied nuclear navies. The overall result is a broader understanding in the Nordic countries for the importance of the various parameters for impact assessment of releases from marine reactors, and to the design and maintenance of an emergency preparedness organisation without detailed knowledge of the installation in question

  11. Full scale simulations of accidents on spent-nuclear-fuel shipping systems

    International Nuclear Information System (INIS)

    Yoshimura, H.R.

    1978-01-01

    In 1977 and 1978, five first-of-a-kind full scale tests of spent-nuclear-fuel shipping systems were conducted at Sandia Laboratories. The objectives of this broad test program were (1) to assess and demonstrate the validity of current analytical and scale modeling techniques for predicting damage in accident conditions by comparing predicted results with actual test results, and (2) to gain quantitative knowledge of extreme accident environments by assessing the response of full scale hardware under actual test conditions. The tests were not intended to validate the present regulatory standards. The spent fuel cask tests fell into the following configurations: crashes of a truck-transport system into a massive concrete barrier (100 and 130 km/h); a grade crossing impact test (130 km/h) involving a locomotive and a stalled tractor-trailer; and a railcar shipping system impact into a massive concrete barrier (130 km/h) followed by fire. In addition to collecting much data on the response of cask transport systems, the program has demonstrated thus far that current analytical and scale modeling techniques are valid approaches for predicting vehicular and cask damage in accident environments. The tests have also shown that the spent casks tested are extremely rugged devices capable of retaining their radioactive contents in very severe accidents

  12. The IAEA Conventions on Early Notification of a Nuclear Accident and on Assistance in the Case of a Nuclear Accident or Radiological Emergency

    International Nuclear Information System (INIS)

    Moser, B.

    1989-01-01

    This article provides a comprehensive analysis of the provisions of both IAEA Conventions. Special attention is paid to the rules of the Convention on Early Notification which identify the events subject to notification and the content and addresses of the information to be provided with regard to a nuclear accident, as well as to the provisions of the Convention on Assistance concerning the request and grant of international assistance with regard to a nuclear accident and the duties attributed in this field to the IAEA. The author also considers the liability questions raised by that Convention. (NEA) [fr

  13. The official report of the Fukushima Nuclear Accident Independent Investigation Commission

    International Nuclear Information System (INIS)

    2012-07-01

    In October 2011, the Act regarding Fukushima Nuclear Accident Independent Investigation Commission was enacted to investigate the Fukushima accident with the authority to request documents and request the legislative branch to use its investigative powers to obtain any necessary documents or evidence required. In December 2011, chairman and nine other members were appointed. After a six-month investigation, Commission had concluded. 'In order to prevent future disasters, fundamental reforms must take place covering both the structure of electric power industry and the structure of related government and regulatory agencies as well as operation processes, for both normal and emergency situations'. Main parts of report consisted of overview, conclusions and recommendations, and six findings; (1) was the accident preventable?, (2) Escalation of the accident, (3) Emergency response to the accident, (4) Spread of the damage, (5) Organizational issues in accident prevention and response and (6) the legal system. Based on the above findings, Commission made seven recommendations regarding (1) Monitoring of the nuclear regulatory body by the National Diet, (2) Reform the crisis management system, (3) Government responsibility for public health and welfare, (4) Monitoring the operators, (5) Criteria for the new regulatory body, (6) Reforming laws related to nuclear energy and (7) Develop a system of independent investigation commissions. National Diet's thorough debate and deliberate on these recommendation was highly encouraged for the future. (T. Tanaka)

  14. The next nuclear power station generation: Beyond-design accident concepts, methods, and action sequence

    International Nuclear Information System (INIS)

    Asmolov, V.G.; Khakh, O.Ya.; Shashkov, M.G.

    1993-01-01

    The problem of beyond-design accidents at nuclear stations will not be solved unless a safety culture becomes a basic characteristic of all lines of activity. Only then can the danger of accidents as an objective feature of nuclear stations be eliminated by purposive skilled and responsible activities of those implementing safety. Nuclear-station safety is provided by the following interacting and complementary lines of activity: (1) the design and construction of nuclear stations by properly qualified design and building organizations; (2) monitoring and supervision of safety by special state bodies; (3) control of the station by the exploiting organization; and (4) scientific examination of safety within the above framework and by independent organizations. The distribution of the responsibilities, powers, and right in these lines should be defined by a law on atomic energy, but there is not such law in Russian. The beyond-design accident problem is a key one in nuclear station safety, as it clear from the serious experience with accidents and numerous probabilistic studies. There are four features of the state of this topic in Russia that are of major significance for managing accidents: the lack of an atomic energy law, the inadequacy of the technical standards, the lack of a verified program package for nuclear-station designs in order to calculate the beyond-design accidents and analyze risks, and a lack of approach by designers to such accidents on the basis of international recommendations. This paper gives a brief description of three-forming points in the scientific activity: the general concept of nuclear-station safety, methods of analyzing and providing accident management, and the sequence of actions developed by specialists at this institute in recent years

  15. Importance of risk communication during and after a nuclear accident.

    Science.gov (United States)

    Perko, Tanja

    2011-07-01

    Past nuclear accidents highlight communication as one of the most important challenges in emergency management. In the early phase, communication increases awareness and understanding of protective actions and improves the population response. In the medium and long term, risk communication can facilitate the remediation process and the return to normal life. Mass media play a central role in risk communication. The recent nuclear accident in Japan, as expected, induced massive media coverage. Media were employed to communicate with the public during the contamination phase, and they will play the same important role in the clean-up and recovery phases. However, media also have to fulfill the economic aspects of publishing or broadcasting, with the "bad news is good news" slogan that is a well-known phenomenon in journalism. This article addresses the main communication challenges and suggests possible risk communication approaches to adopt in the case of a nuclear accident. Copyright © 2011 SETAC.

  16. Nuclear accident: the EPR, the most dangerous reactor in the world

    International Nuclear Information System (INIS)

    Large, John

    2007-02-01

    After a brief description of the operation of a nuclear reactor, this document outlines the complexity of this machine and the problems which may happen and result in radioactive releases. It also briefly recalls past accidents (Chernobyl, Three Mile Island) and serious incidents (Fosmark in Sweden, Blayais in France). The author then describes how the nuclear industry and nuclear safety authorities tend to deny the risk, notably as far as the EPR is concerned. He outlines that the hypotheses retained by EDF and safety authorities for the quantity of radioactivity released in case of accident might be under-assessed as it appears when they are compared with data obtained by different models and in reality. The author considers that the use of MOX introduces difficulties to ensure nuclear safety, and that the EPR will therefore be the most dangerous nuclear reactor in the world. Based on a simulation, he shows that, in case of accident in of the EPR in Flamanville, radioactive fallouts will occur at the continental scale in less than two days. He proposes an assessment of consequences for the population in terms of deaths, cancers, evacuation. He indicates the different exposure modes for the population, and the countermeasures to be implemented in case of accident (he proposes an assessment of consequences in terms of morbidity with or without countermeasures)

  17. Accidents involving off-road motor vehicles in a northern community.

    Science.gov (United States)

    Hasselback, P; Wilding, H R

    1987-01-01

    The increasing number of accidents associated with off-road motor vehicles used for recreational purposes prompted this prospective study. During 1985 the records of victims of all motor vehicle accidents who were seen at the Hudson Bay Union Hospital, Hudson Bay, Sask., were studied; patients involved in on-road vehicle accidents were included for comparison. Emphasis was placed on age, vehicle type, mechanism of accident, injury severity and the use of safety features. Almost half of the victims of off-road vehicle accidents were under 16 years of age. The poor adherence to government legislation and manufacturer recommendations was evident in the number of people who did not wear helmets or use headlights. PMID:3651929

  18. Japan's compensation system for nuclear damage - As related to the TEPCO Fukushima Daiichi nuclear accidents

    International Nuclear Information System (INIS)

    Nomura, Toyohiro; Matsuura, Shigekazu; Takahashi, Yasufumi; Takenaka, Chihiro; Hokugo, Taro; Kamada, Toshihiko; Kamai, Hiroyuki

    2012-01-01

    Following the TEPCO Fukushima Daiichi nuclear power plant accident, extraordinary efforts were undertaken in Japan to implement a compensation scheme for the proper and efficient indemnification of the affected victims. This publication provides English translations of key Japanese legislative and administrative texts and other implementing guidance, as well as several commentaries by Japanese experts in the field of third party nuclear liability. The OECD Nuclear Energy Agency (NEA) has prepared this publication in co-operation with the government of Japan to share Japan's recent experience in implementing its nuclear liability and compensation regime. The material presented in the publication should provide valuable insights for those wishing to better understand the regime applied to compensate the victims of the accident and for those working on potential improvements in national regimes and the international framework for third party nuclear liability

  19. Emotional reactivity: Beware its involvement in traffic accidents.

    Science.gov (United States)

    M'bailara, Katia; Atzeni, Thierry; Contrand, Benjamin; Derguy, Cyrielle; Bouvard, Manuel-Pierre; Lagarde, Emmanuel; Galéra, Cédric

    2018-04-01

    Reducing risk attributable to traffic accidents is a public health challenge. Research into risk factors in the area is now moving towards identification of the psychological factors involved, particularly emotional states. The aim of this study was to evaluate the link between emotional reactivity and responsibility in road traffic accidents. We hypothesized that the more one's emotional reactivity is disturbed, the greater the likelihood of being responsible for a traffic accident. This case-control study was based on a sample of 955 drivers injured in a motor vehicle crash. Responsibility levels were determined with a standardized method adapted from the quantitative Robertson and Drummer crash responsibility instrument. Emotional reactivity was assessed with the MATHYS. Hierarchical cluster analysis discriminated four distinctive driver's emotional reactivity profiles: basic emotional reactivity (54%), mild emotional hyper-reactivity (29%), emotional hyper-reactivity (11%) and emotional hypo-reactivity (6%). Drivers who demonstrated emotional hypo-reactivity had a 2.3-fold greater risk of being responsible for a traffic accident than those with basic emotional reactivity. Drivers' responsibility in traffic accidents depends on their emotional status. The latter can change the ability of drivers, modifying their behavior and thus increasing their propensity to exhibit risk behavior and to cause traffic accidents. Copyright © 2017 Elsevier B.V. All rights reserved.

  20. Nuclear Security Summit and Workshop 2015: Preventing, Understanding and Recovering from Nuclear Accidents lessons learned from Chernobyl and Fukushima

    Science.gov (United States)

    2016-09-01

    Workshop 2015 "Preventing, Understanding and Recovering from Nuclear Accidents"--lessons learned from Chernobyl and Fukushima Distribution Statement...by the factor to get the U.S. customary unit. “Preventing, Understanding and Recovering from Nuclear Accidents” – lessons learned from Chernobyl ...and Fukushima NUCLEAR SECURITY SUMMIT & WORKSHOP 2015 2 Background The 1986 Chernobyl and the 2011 Fukushima accidents provoked world-wide concern

  1. Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results

    International Nuclear Information System (INIS)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

    1994-01-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the I nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

  2. Bibliography for nuclear criticality accident experience, alarm systems, and emergency management

    International Nuclear Information System (INIS)

    Putman, V.L.

    1995-09-01

    The characteristics, detection, and emergency management of nuclear criticality accidents outside reactors has been an important component of criticality safety for as long as the need for this specialized safety discipline has been recognized. The general interest and importance of such topics receives special emphasis because of the potentially lethal, albeit highly localized, effects of criticality accidents and because of heightened public and regulatory concerns for any undesirable event in nuclear and radiological fields. This bibliography lists references which are potentially applicable to or interesting for criticality alarm, detection, and warning systems; criticality accident emergency management; and their associated programs. The lists are annotated to assist bibliography users in identifying applicable: industry and regulatory guidance and requirements, with historical development information and comments; criticality accident characteristics, consequences, experiences, and responses; hazard-, risk-, or safety-analysis criteria; CAS design and qualification criteria; CAS calibration, maintenance, repair, and testing criteria; experiences of CAS designers and maintainers; criticality accident emergency management (planning, preparedness, response, and recovery) requirements and guidance; criticality accident emergency management experience, plans, and techniques; methods and tools for analysis; and additional bibliographies

  3. Thyroid blocking after nuclear accidents

    International Nuclear Information System (INIS)

    Rendl, J.; Reiners, C.

    1999-01-01

    Following the Chernobyl accident a marked increase in thyroid cancer incidence among the children in Belarus, the Ukraine and Russia has been detected, strongly suggesting a causal relationship to the large amounts of radioactive iodine isotopes in the resulting fallout. Taking into account the Chernobyl experience the German Committee on Radiation Protection decided to reduce the intervention levels on the basis of the 1989 WHO recommendations and adopted a new concept concerning thyroid blocking in response to nuclear power plant accidents. Experimental animal studies and theoretical considerations show that thyroid blocking with potassium iodide (KI) in a dose of about 1.4 mg per kg body weight is most effective in reducing irradiation to the thyroid from the intake of radioiodine nuclides, provided KI is given within 2 hours after exposure. According to the new concept, persons over 45 years of age should not take iodine tablets because the drug could cause a greater health risk due to prevalent functional thyroid autonomy in this age group than the radioactive iodine averted by KI. On the basis of accident analysis and the new philosophy suitable distribution strategies and logistics are proposed and discussed. (orig.) [de

  4. Source term estimation during incident response to severe nuclear power plant accidents

    International Nuclear Information System (INIS)

    McKenna, T.J.; Glitter, J.G.

    1988-10-01

    This document presents a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. 39 refs., 48 figs., 19 tabs

  5. Study on actions for social acceptance of a nuclear power plant incident/accident

    International Nuclear Information System (INIS)

    Kotani, Fumio; Tsukada, Tetsuya; Hiramoto, Mitsuru; Nishimura, Naoyuki

    1998-01-01

    When an incident/accident has occurred, dealing technically with it in an appropriate way is essential for social acceptance. One of the most important actions that are expected from the plant representative is to provide, without delay, each of the concerned authorities and organizations with full information concerning the incident/accident, while necessary technical measures are being implemented. While the importance of socially dealing with the incident/accident is widely recognized, up to now there have been no attempts to study previous incidents/accidents cases from the social sciences viewpoint. Therefore, in the present study is a case study of the incident/accident that occurred in 1991 at the No.2 Unit of the Mihama Nuclear Plant of Kansai Power Co., Ltd.. The data used in the present study is based on intensive interview of the staff involved in this incident/accident. The purpose of the study was to shed light on the conditions necessary for maintaining and improving the skill of the plant representative when dealing with social response in case of an incident/accident. The results of the present study has led to a fuller recognition of the importance of the following factors: On the personal level: 1) recognition of personal accountability, 2) complete disclosure of information concerning the incident/accident. On the organizational level: 1) acceptance of different approaches and viewpoints, 2) promoting risk-taking behavior, 3) top management's vision and commitment to providing a social response. (author)

  6. The External Cost Evaluation of the Nuclear Severe Accident Using CVM

    International Nuclear Information System (INIS)

    Lee, Yong Suk; Lee, Byung Chul

    2006-01-01

    The external cost of energy can be defined as 'the cost not included in the energy market price', such as air pollution, noise, etc. Within the evaluation of the external cost of nuclear energy, the estimation of the external cost of severe accident is one of the major topics to be addressed. For the evaluation of the external cost of severe accident, the effect of risk aversion of the public against the severe accident must be addressed, because people are more concerned about low probability - high consequence events than about high probability - low consequence events having the same mean damage. It is generally recognized that there is a discrepancy between the social acceptability of the risk and the average monetary value which corresponds in principle to the compensation of the consequences for each individual of the population affected by the accident. In this paper, the CVM (Contingent Valuation Method) is used to integrate the risk aversion in the external costs of nuclear severe accidents in Korea

  7. Assessment of PASS Effectiveness under Severe Accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, Yu Jung; Lee, Sung Bok; Kim, Hyeong Taek; Lee, Jin Yong

    2008-01-01

    Following the accident at Three Mile Island Unit 2 (TMI-2) on March 28, 1979, the USNRC formed a lessons-learned Task Force to identify and evaluate safety concerns originating with the TMI-2 accident. NUREG-0578 documented the results of the task force effort. One of the recommendations of the task force was for licensees to upgrade the capability to obtain samples from the reactor coolant system and containment atmosphere under high radioactivity conditions and to provide the capability for chemical and spectral analyses of high-level samples on site. NUREG-0737 contained the details of the TMI recommendations that were to be implemented by the licensees. Additional criteria for post accident sampling system(PASS) were issued by Regulatory Guide 1.97. As the results, PASS has been installed on nuclear power plants(NPPs) in Korea as well as United States. However, significant improvements have been achieved since the TMI-2 accident in the areas of understanding risks associated with nuclear plant operations and developing better strategies for managing the response to potential severe accidents at NPPs. Thus, the requirements for PASS have been re-evaluated in some reports. According to the reports, the samples and measurements from PASS do not contribute significantly to emergency management response to severe accidents due to the long analyzing time, 3 hours. Hence, this paper focused on the development of the quantitative analysis methodology to analyze the sequence of the severe accident in Yonggwang nuclear power plants (YGN) and presented the results of the analysis according to the developed methodology

  8. Catastrophes and nuclear accidents in the former USSR

    International Nuclear Information System (INIS)

    Robeau, D.

    2001-01-01

    In the former USSR, the nuclear safety, the environment protection and the preservation of workers and population health were not the first priority for the Soviet Union authorities. The fabrication of nuclear weapons, the construction of nuclear submarines and the production of an abundant energy source were the only goals at that time. This book describes and explains the circumstances of the nuclear catastrophes and accidents that have occurred during this era. It tries to estimate their impacts on populations and environment and their possible consequences in a near or far future. (J.S.)

  9. Study on integrated approach of Nuclear Accident Hazard Predicting, Warning, and Optimized Controlling System based on GIS

    International Nuclear Information System (INIS)

    Tang Lijuan; Huang Shunxiang; Wang Xinming

    2012-01-01

    The issue of nuclear safety becomes the attention focus of international society after the nuclear accident happened in Fukushima. Aiming at the requirements of the prevention and controlling of Nuclear Accident establishment of Nuclear Accident Hazard Predicting, Warning and optimized Controlling System (NAPWS) is a imperative project that our country and army are desiderating, which includes multiple fields of subject as nuclear physics, atmospheric science, security science, computer science and geographical information technology, etc. Multiplatform, multi-system and multi-mode are integrated effectively based on GIS, accordingly the Predicting, Warning, and Optimized Controlling technology System of Nuclear Accident Hazard is established. (authors)

  10. Normal Accident at Three Mile Island.

    Science.gov (United States)

    Perrow, Charles

    1981-01-01

    Discusses some aspects of the accident at the Three Mile Island nuclear power plant. Explains a number of factors involved including the type of accident, warnings, design and equipment failure, operator error, and negative synergy. Presents alternatives to systems with catastrophic potential. (MK)

  11. 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

  12. Stakeholder involvement in nuclear crisis management in Greece

    International Nuclear Information System (INIS)

    Ioannides, K.G.; Tzialla, C.E.; Papachristodoulou, C.A.; Papanikolaou, C.; Apostolopoulos, C.

    2005-01-01

    The setting up of the Greek Stakeholders Group in the framework of the EC Food and Agriculture Restoration Management Involving Networked Groups (FARMING) project is described. The Group included members from more than 20 governmental and non-governmental organisations, having interest and/or responsibilities in the management of a crisis following a nuclear accident. The stakeholders, during their meetings in 2002, discussed the agricultural countermeasures and rural waste disposal options which have been compiled by the EC Sustainable Restoration and Long-Term Management of Contaminated Rural, Urban and Industrial Ecosystems (STRATEGY) project. All stakeholders agreed that the most preferable were those options that ensure public acceptance, minimise environmental impact and maintain farming practices and acceptable living and working conditions. Their views are synoptically presented along with the major conclusions from the stakeholders meetings regarding nuclear crisis management

  13. Preliminary report about nuclear accident of Chernobylsk reactor

    International Nuclear Information System (INIS)

    Oliveira, A.R. de.

    1986-07-01

    The preliminary report of nuclear accident at Chernobyl, in URSS is presented. The Chernobyl site is located geographically and the RBMK type reactors - initials of russian words which mean high power pressure tube reactors are described. The conditions of reactor operation in beginning of accident, the events which lead to reactor destruction, the means to finish the fire, the measurements adopted by Russian in the accident location, the estimative of radioactive wastes, the meteorological conditions during the accident, the victims and medical assistence, the sanitary aspects and consequences for population, the evaluation of radiation doses received at small and medium distance and the estimative of reffered doses by population attained are presented. The official communication of Russian Minister Council and the declaration of IAEA general manager during a collective interview in Moscou are annexed. (M.C.K.) [pt

  14. The risk of accident in nuclear power plants - Quotes and questions. National debate on energy transition. Taking the risk of nuclear accident into account. Note to the 'scenarios' subgroup of the group of experts

    International Nuclear Information System (INIS)

    Laponche, Bernard

    2013-01-01

    After an overview of the production of electricity from nuclear energy and of its risks, the author discusses the issue of nuclear safety by distinguishing the different points of view, by describing the different levels between a severe and a major accident, and by recalling the statements made by the ASN and the IRSN on this issue. He describes the various reasons and consequences of accidents: types of accidents which could result in a core fusion, the containment failure as the major accident. He discusses the questions and comments about major issues like: strength of reactor vessels, hydrogen explosion, water vapour explosion, corium crossing the concrete sill plate, corium recovery, MOX as an aggravating situation for safety. In the last part, the author discusses the global assessment of a risk of a nuclear accident: probabilities and occurrences, significant accidents on PWRs, premonitory analysis, demonstration of nuclear safety

  15. The accident at TEPCO's Fukushima Dai-ichi Nuclear Power Station - occurrence of the accident, current situation and Future

    International Nuclear Information System (INIS)

    Hirose, K.

    2013-01-01

    In this presentation author analyse course of accident on Fukushima Dai-chi NPPs as well as consequences of this disaster. The following parts are presented: (1) Occurrence of the accident; (2) Evacuation of the residential people; (3) Deterioration and protraction of the accident; (4) Impact on society; (5) Situation of decontamination; (6) Long-term steps towards decommissioning; (7) Situation of other nuclear power stations; (8) Conclusions and lessons learned.

  16. Lessons of the accident at Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Veksler, L.M.

    1983-01-01

    Measures taken in the USA for improving safety of NPPs after the accident at ''Three Mile Island'' nuclear power plant are considered. Activities, related to elimination of accident consequences are analyzed. Perspectives of resuming the NPP operation are discussed

  17. Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

    OpenAIRE

    TANAKA, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety o...

  18. Study of typical nuclear containment purge valves in an accident environment

    International Nuclear Information System (INIS)

    Watkins, J.C.; Steele, R. Jr.; Hill, R.C.; DeWall, K.G.

    1986-08-01

    This report presents the results of the containment purge and vent valve test program, conducted under the sponsorship of the United States Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research. The test program investigated butterfly valve operability and leak integrity under light-water-reactor design basis and severe accident conditions. Three nuclear-designed butterfly valves typical of those used in domestic nuclear power plant containment purge and vent applications were tested. For a comparison of response, two valve of the same size with differing internal designs were tested. For extrapolation insights, a larger-sized valve similar to one of the smaller valves was also tested. Dynamic flow tests were performed over the range of design basis accident pressures. Leak integrity testing was also performed at both design basis and severe accident temperatures and pressures. The valve experiments were performed with various piping configurations and valve orientations to the flow to simulate the various installation options in field applications. Testing was also performed in a standard ANSI test section

  19. Fast Transient And Spatially Non-Homogenous Accident Analysis Of Two-Dimensional Cylindrical Nuclear Reactor

    International Nuclear Information System (INIS)

    Yulianti, Yanti; Su'ud, Zaki; Waris, Abdul; Khotimah, S. N.; Shafii, M. Ali

    2010-01-01

    The research about fast transient and spatially non-homogenous nuclear reactor accident analysis of two-dimensional nuclear reactor has been done. This research is about prediction of reactor behavior is during accident. In the present study, space-time diffusion equation is solved by using direct methods which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference discretization method is solved by using iterative methods ADI (Alternating Direct Implicit). The indication of accident is decreasing macroscopic absorption cross-section that results large external reactivity. The power reactor has a peak value before reactor has new balance condition. Changing of temperature reactor produce a negative Doppler feedback reactivity. The reactivity will reduce excess positive reactivity. Temperature reactor during accident is still in below fuel melting point which is in secure condition.

  20. Risks and benefits of the interventions aimed at minimizing nuclear damage in the Chernobyl accident

    International Nuclear Information System (INIS)

    Rossiello, L.A.; Failla, L.

    1997-01-01

    The damages that the absorption of ionizing radiation (i.r.) can cause to humans may be classified as 1) nonstochastic (somatic or deterministic) or 2) stochastic (probabilistic) , which result, for example, from high doses of i.r. absorbed after a serious nuclear accident. Though the Chernobyl case involved both kinds of damage, this paper deals only with stochastic damage risk, and confine our considerations to individuals who were directly Affected and received high i.r. doses. The purpose of this paper is to provide elements on which to base future decisions on the evacuation and return of populations affected by serious nuclear accidents. Unlike the abundant literature on the subject, and as a necessary complement thereto within the bounds of a strict synthesis, to identify the most significant parameters applicable to single individuals rather than to the population at large, and referring solely to risks of stochastic damage

  1. A defense in depth approach for nuclear power plant accident management

    Energy Technology Data Exchange (ETDEWEB)

    Chih-Yao Hsieh; Hwai-Pwu Chou [Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, TW (China)

    2015-07-01

    An initiating event may lead to a severe accident if the plant safety functions have been challenged or operators do not follow the appropriate accident management procedures. Beyond design basis accidents are those corresponding to events of very low occurrence probability but such an accident may lead to significant consequences. The defense in depth approach is important to assure nuclear safety even in a severe accident. Plant Damage States (PDS) can be defined by the combination of the possible values for each of the PDS parameters which are showed on the nuclear power plant simulator. PDS is used to identify what the initiating event is, and can also give the information of safety system's status whether they are bypassed, inoperable or not. Initiating event and safety system's status are used in the construction of Containment Event Tree (CET) to determine containment failure modes by using probabilistic risk assessment (PRA) technique. Different initiating events will correspond to different CETs. With these CETs, the core melt frequency of an initiating event can be found. The use of Plant Damage States (PDS) is a symptom-oriented approach. On the other hand, the use of Containment Event Tree (CET) is an event-oriented approach. In this study, the Taiwan's fourth nuclear power plants, the Lungmen nuclear power station (LNPS), which is an advanced boiling water reactor (ABWR) with fully digitized instrumentation and control (I and C) system is chosen as the target plant. The LNPS full scope engineering simulator is used to generate the testing data for method development. The following common initiating events are considered in this study: loss of coolant accidents (LOCA), total loss of feedwater (TLOFW), loss of offsite power (LOOP), station blackout (SBO). Studies have indicated that the combination of the symptom-oriented approach and the event-oriented approach can be helpful to find mitigation strategies and is useful for the accident

  2. Commitment of involved actors in the preparation of accidental and post-accident situations: European experiments

    International Nuclear Information System (INIS)

    Schneider, Th.

    2010-01-01

    The author briefly describes some approaches developed within the EURANOS European research programme between 2004 and 2009 which aims at promoting the building up of a European network (NERIS) for the management of nuclear accidental and post-accident situations. Notably, he comments the experiment which took place in the Montbeliard district where two types of radiological events have been modelled and simulated: an accident in the Fessenheim nuclear power plant with two scenarios of release, and a transportation accident with a release of radioactive caesium 137. He also evokes the Norwegian experience and some other actions in Finland, Great-Britain, Spain and Slovakia where reflections on the management of accidental and post-accident situations or crisis exercises have been organized

  3. Chemical and nuclear emergencies: Interchanging lessons learned from planning and accident experience

    International Nuclear Information System (INIS)

    Adler, V.; Sorensen, J.H.; Rogers, G.O.

    1989-01-01

    Because the goal of emergency preparedness for both chemical and nuclear hazards is to reduce human exposure to hazardous materials, this paper examines the interchange of lessons learned from emergency planning and accident experience in both industries. While the concerns are slightly different, sufficient similarity is found for each to draw implications from the others experience. Principally the chemical industry can learn from the dominant planning experience associated with nuclear power plants, while the nuclear industry can chiefly learn from the chemical industry's accident experience. 23 refs

  4. The estimation economic impacts from severe accidents of a nuclear power plant

    International Nuclear Information System (INIS)

    Jeong, J. T.; Jeong, W. D.

    2001-01-01

    The severe accidents of a nuclear power plant may cause health effects in the exposed population and societal economic impacts or costs. Techniques to assess the consequences of an accident in terms of cost may be applied in studies on the design of plant safety features and in examining countermeasure options as part of emergency planning or in decision making after an accident. In this study, the costs resulting from the severe accidents of a nuclear power plant were estimated for the different combinations of source term release parameters and meteorological data. Also, the costs were estimated for the different scenarios considering seasonal characteristics of Korea. The results can be used as essential inputs in costs/benefit analysis and in developing optimum risk reduction strategies

  5. Source term estimation during incident response to severe nuclear power plant accidents. Draft

    Energy Technology Data Exchange (ETDEWEB)

    McKenna, T J; Giitter, J

    1987-07-01

    The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. The goal is to present a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. (author)

  6. Source term estimation during incident response to severe nuclear power plant accidents. Draft

    International Nuclear Information System (INIS)

    McKenna, T.J.; Giitter, J.

    1987-01-01

    The various methods of estimating radionuclide release to the environment (source terms) as a result of an accident at a nuclear power reactor are discussed. The major factors affecting potential radionuclide releases off site (source terms) as a result of nuclear power plant accidents are described. The quantification of these factors based on plant instrumentation also is discussed. A range of accident conditions from those within the design basis to the most severe accidents possible are included in the text. A method of gross estimation of accident source terms and their consequences off site is presented. The goal is to present a method of source term estimation that reflects the current understanding of source term behavior and that can be used during an event. (author)

  7. Effects of the criticality accident at Tokai-mura on the public's attitude to nuclear power generation

    International Nuclear Information System (INIS)

    Kitada, Atsuko; Hayashi, Chikio

    2000-01-01

    The objective of our study was to clarify the effects on the public's attitude of nuclear power and the criticality accident that occurred at the JCO plant in Tokai-mura, Ibaraki Prefecture. For this purpose, we conducted an awareness survey in the Kansai and Kanto areas two months after the accident. Analysis was made on the basis of the comparison of the survey results with the data that the Institute of Nuclear Safety System had accumulated through continuous awareness surveys on nuclear power generation (regular surveys) since 1993. The public's reactions were twofold. On one hand, there were emotional reactions about accidents in nuclear facilities and a reduction in the sense of security. On the other hand, there were reactions concerning the image of nuclear power plant workers and demand on electricity utilities for enhanced employee education and training. The latter reactions correspond to the problems pointed out after the JCO accident. Regarding the utilization of nuclear power generation, the opinion that 'the utilization of nuclear power generation is unavoidable' accounts for 60% of those surveyed. With the opinion that 'nuclear power generation should be utilized' added, 70% of those surveyed take an affirmative attitude to nuclear power utilization. This situation has remained about the same since 1998, the year before the JCO accident. Using the quantification method III to analyze a number of questionnaires about nuclear power generation such as the anxiety about it, we determined overall attitude indexes regarding nuclear power to perform a time sequence comparison. The comparison shows that the attitude after the JCO accident tended to be more negative than in 1998. However, no significant difference in the overall indexes is seen between 1993 and 1998. Judging the comparison results on the basis of the time span starting in 1993 allows us to conclude that the JCO accident has not greatly contributed to worsening the attitude towards nuclear

  8. Severe accidents and terrorist threats at nuclear reactors

    International Nuclear Information System (INIS)

    Pollack, G.L.

    1987-01-01

    Some of the key areas of uncertainty are the nature of the physical and chemical interactions of released fission products and of the interactions between a molten core and concrete, the completeness and validity of the computer codes used to predict accidents, and the behavior of the containment. Because of these and other uncertainties, it is not yet possible to reliably predict the consequences of reactor accidents. It is known that for many accident scenarios, especially less severe ones or where the containment is not seriously compromised, the amount of radioactive material expected to escape the reactor is less, even much less, than was previously calculated. For such accidents, the predictions are easier and more reliable. With severe accidents, however, there is considerable uncertainty as to the predicted results. For accidents of the type that terrorists might cause - for example, where the sequence of failure would be unexpected or where redundant safety features are caused to fail together - the uncertainties are still larger. The conclusion, then, is that there are potential dangers to the public from terrorist actions at a nuclear reactor; however, because of the variety of potential terrorist threats and the incompleteness of the knowledge about the behavior of reactor components and fission products during accidents, the consequences cannot yet be assessed quantitatively

  9. New public commons and network of nuclear site regions for the post-Fukushima accident re-vitalization

    International Nuclear Information System (INIS)

    Sawada, Tetsuo

    2012-01-01

    Due to the Fukushima NPP accidents on 11 March 2011, we have deadly lost the regional ties among local people, electricity consumers, and people involved in the nuclear research, development and businesses. Now we need the method to reconstruct the ties and further the activation of locals in accordance to the concept of 'New Public Commons'. And it is the most important key to recover the people's confidence for the nuclear business and promote the new siting and replacement of nuclear power stations. More than forty years have past since the earliest stage of invitation of nuclear power stations to regional areas in Japan. For this period, the efforts for the development of regional industries and the improvement of regional life obtained a level of results. However, now a new turn is required in the regional development, as the perception of wealthy has been gradually changed. The primary objective of this study is to make a network among regional areas where nuclear power stations and related facilities are located. It should further the understanding for nuclear energy, stimulate the 'emergence' through the cooperative works among regional areas. As a result, such efforts will enhance the Social Responsibility of conducts related to the nuclear energy. i.e., Nuclear SR (NSR). The basic frame of the NSR should be re-estimated in the reflection of 3.11 Fukushima NPP accidents. (author)

  10. TEPCO's costs and risks which invited the nuclear power plant accident

    International Nuclear Information System (INIS)

    Soeda, Takashi

    2017-01-01

    The National Diet of Japan Fukushima Nuclear Accident Independent Investigation Commission (Diet Accident Investigation Commission) considered two patterns against the tsunami risk of nuclear plant: (1) Risk management for the purpose of safety (Pattern A), and (2) Risk management for the purpose of utilization rate and cost of nuclear reactor (Pattern B). Pattern B emphasizes avoiding 'countermeasure cost generation' and 'operation shutdown' rather than preparing for a tsunami that we do not know when to come. Diet Accident Investigation Commission analyzed that the behavioral principles concerning the crisis response of Tokyo Electric Power Company (TEPCO) had the stronger tendency of Pattern B. Regarding the accident of TEPCO, there were class actions that asked the responsibility of TEPCO and the government. This paper examined the contents of the opinions of government-side experts submitted for this issue. The government-side experts argued that there was no 'scientific consensus' for tsunami forecast, and that preliminary measures against unexpected tsunami was impossible. However, both of these government's arguments are irrational due to difference from the fact. TEPCO president at the time of accident insisted in the firm that 'cost cut in another dimension' was indispensable and reduced expenses. TEPCO and the government had continued Pattern B, even knowing that tsunami risk measures were insufficient from more than ten years ago. (A.O.)

  11. Developing and assessing accident management plans for nuclear power plants

    International Nuclear Information System (INIS)

    Hanson, D.J.; Johnson, S.P.; Blackman, H.S.; Stewart, M.A.

    1992-07-01

    This document is the second of a two-volume NUREG/CR that discusses development of accident management plans for nuclear power plants. The first volume (a) describes a four-phase approach for developing criteria that could be used for assessing the adequacy of accident management plans, (b) identifies the general attributes of accident management plans (Phase 1), (c) presents a prototype process for developing and implementing severe accident management plans (Phase 2), and (d) presents criteria that can be used to assess the adequacy of accident management plans. This volume (a) describes results from an evaluation of the capabilities of the prototype process to produce an accident management plan (Phase 3) and (b), based on these results and preliminary criteria included in NUREG/CR-5543, presents modifications to the criteria where appropriate

  12. Consequences of severe nuclear accidents in Europe

    Science.gov (United States)

    Seibert, Petra; Arnold, Delia; Mraz, Gabriele; Arnold, Nikolaus; Gufler, Klaus; Kromp-Kolb, Helga; Kromp, Wolfgang; Sutter, Philipp

    2013-04-01

    A first part of the presentation is devoted to the consequences of the severe accident in the 1986 Chernobyl NPP. It lead to a substantial radioactive contaminated of large parts of Europe and thus raised the awareness for off-site nuclear accident consequences. Spatial patterns of the (transient) contamination of the air and (persistent) contamination of the ground were studied by both measurements and model simulations. For a variety of reasons, ground contamination measurements have variability at a range of spatial scales. Results will be reviewed and discussed. Model simulations, including inverse modelling, have shown that the standard source term as defined in the ATMES study (1990) needs to be updated. Sensitive measurements of airborne activities still reveal the presence of low levels of airborne radiocaesium over the northern hemisphere which stems from resuspension. Over time scales of months and years, the distribution of radionuclides in the Earth system is constantly changing, for example relocated within plants, between plants and soil, in the soil, and into water bodies. Motivated by the permanent risk of transboundary impacts from potential major nuclear accidents, the multidisciplinary project flexRISK (see http://flexRISK.boku.ac.at) has been carried out from 2009 to 2012 in Austria to quantify such risks and hazards. An overview of methods and results of flexRISK is given as a second part of the presentation. For each of the 228 NPPs, severe accidents were identified together with relevant inventories, release fractions, and release frequencies. Then, Europe-wide dispersion and dose calculations were performed for 2788 cases, using the Lagrangian particle model FLEXPART. Maps of single-case results as well as various aggregated risk parameters were produced. It was found that substantial consequences (intervention measures) are possible for distances up to 500-1000 km, and occur more frequently for a distance range up to 100-300 km, which is in

  13. Nuclear Accidents Intervention Levels for Protection of the Public

    International Nuclear Information System (INIS)

    1989-01-01

    The impact of the 1986 Chernobyl accident called attention to the need to improve international harmonization of the principles and criteria for the protection of the public in the event of a nuclear accident. This report provides observations and guidance related to the harmonization of radiological protection criteria, and is intended to be of use to national authorities and international organizations examining the issue of emergency response planning and intervention levels

  14. To What Extent International Law Constitutes an Appropriate Answer to Nuclear Accidents?

    International Nuclear Information System (INIS)

    Durand-Poudret, E.

    2015-01-01

    Regulating high risks activities has always been an ambitious task as the regime shall both prevent and compensate the potential damage of such activities. It becomes even more complex with nuclear energy as radioactivity possesses this transboundary character which implies an international cooperation. The need for an appropriate framework for nuclear energy started to raise in the 60s, when States realise that the classic liability system was not relevant for that kind of activity. The Paris and Vienna conventions were subsequently adopted in order to fill this legal gap. Nonetheless, the real turning point remains the Chernobyl accident which resulted in a considerable number of new international instruments as 5 conventions were adopted in the fields of safety and emergency preparedness within a 11 years period: the Convention on Early Notification of a Nuclear Accident, the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the Convention on Nuclear Safety, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and the Convention on Supplementary Compensation for Nuclear Damage. This catastrophe was also the occasion to identify and mitigate the shortcomings of the existing regime in undertaking a revision process through several supplementary protocols, the Joint Protocol Relating to the Application of the Vienna Convention and the Paris Convention, the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage. 25 years after Chernobyl, another tragic nuclear event occurred in Fukushima. Once again it challenged the efficiency of the existing international regime and raises the question as to whether international law represents a relevant solution to such accident. (author)

  15. Review of progress on enhanced accident tolerant fuel

    International Nuclear Information System (INIS)

    McCoy, K.; Dunn, B.; Kochendarfer, R.

    2015-01-01

    The accident at Fukushima has resulted in renewed interest in understanding the performance of nuclear power plants under accident conditions. Part of that interest is directed toward determining how to improve the performance of fuel during an accident that involves long exposures of the fuel to high temperatures. This paper describes the method being used by AREVA to select and evaluate approaches for improving the accident tolerance of nuclear fuel. The method involves starting with a large number of approaches that might enhance accident tolerance, and reviewing how well each approach satisfies a set of engineering requirements and goals. Among the approaches investigated we have the development of fuel pellets that contain a second phase to improve thermal conductivity, the use of molybdenum alloy tubing as fuel cladding, the use of oxidation-resistant coatings to zirconium cladding, and the use of nanoparticles in the coolant to improve heat transfer

  16. Building of communication system for nuclear accident emergency disposal based on IP multimedia subsystem

    Science.gov (United States)

    Wang, Kang; Gao, Guiqing; Qin, Yuanli; He, Xiangyong

    2018-05-01

    The nuclear accident emergency disposal must be supported by an efficient, real-time modularization and standardization communication system. Based on the analysis of communication system for nuclear accident emergency disposal which included many functions such as the internal and external communication, multiply access supporting and command center. Some difficult problems of the communication system were discussed such as variety access device type, complex composition, high mobility, set up quickly, multiply business support, and so on. Taking full advantages of the IP Multimedia Subsystem (IMS), a nuclear accident emergency communication system was build based on the IMS. It was studied and implemented that some key unit and module functions of communication system were included the system framework implementation, satellite access, short-wave access, load/vehicle-mounted communication units. The application tests showed that the system could provide effective communication support for the nuclear accident emergency disposal, which was of great practical value.

  17. Children's reactions to the threat of nuclear plant accidents

    International Nuclear Information System (INIS)

    Schwebel, M.; Schwebel, B.

    1981-01-01

    In the wake of Three Mile Island nuclear plant accident, questionnaire and interview responses of children in elementary and secondary schools revealed their perceptions of the dangers entailed in the continued use of nuclear reactors. Results are compared with a parallel study conducted close to 20 years ago, and implications for mental health are examined

  18. Generalities on nuclear accidents and their short-dated and middle-dated management

    International Nuclear Information System (INIS)

    2003-03-01

    All the nuclear activities present a radiation risk. The radiation exposure of the employees or the public, may occur during normal activity or during an accident. The IRSN realized a document on this radiation risk and the actions of protection. The sanitary and medical aspects of a radiation accident are detailed. The actions of the population protection during an accident and the post accident management are also discussed. (A.L.B.)

  19. Proceedings of the International conference on nuclear accidents and crisis management

    International Nuclear Information System (INIS)

    Stefenson, B.; Landahl, P.A.; Ritchey, T.

    1993-06-01

    This booklet presents the proceedings of the international conference on nuclear accidents and crisis management, held in Stockholm 16-18 March, 1993. It consists of a collection of lectures and discussion notes. The overall purpose of the conference was to promote a greater awareness of crisis management problems during a nuclear accident of potential international scope. Emphasis was placed on information and cooperation, and on experience of different forms of emergency planning and crisis management. The foreign participants in the conference were scientists and representatives from different levels of authority in Denmark, Finland, Germany, Latvia, Lithuania, Norway, Russia, and USA. The second half of the conference was reserved for Swedish national issues. Several additional themes were discussed here, inter alia: *problems of local, regional and central government cooperation. *the need for special laws and directives concerning nuclear accidents. *the need for more research. The lectures and discussion notes from the second part of the conference are in Swedish

  20. 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

  1. Medical emergency planning in case of severe nuclear power plant accidents

    International Nuclear Information System (INIS)

    Ohlenschlaeger, L.

    1980-01-01

    This paper is an attempt to discuss a three-step-plan on medical emergency planning in case of severe accidents at nuclear power plants on the basis of own experiences in the regional area as well as on the basis of recommendations of the Federal Minister of the Interior. The medical considerations take account of the severity and extension of an accident whereby the current definitions used in nuclear engineering for accident situations are taken as basis. A comparison between obligatory and actual state is made on the possibilities of medical emergency planning, taking all capacities of staff, facilities, and equipment available in the Federal Republic of Germany into account. To assure a useful and quick utilization of the existing infra-structure as well as nation-wide uniform training of physicians and medical assistants in the field of medical emergency in case of a nuclear catastrophe, a federal law for health protection is regarded urgently necessary. (orig.) [de

  2. Legal responsibility in case of a nuclear accident

    International Nuclear Information System (INIS)

    Nabhane, M. F.

    1988-01-01

    Numerous laws have been elaborated in order to determine the legal responsibility in case of a nuclear accident. These laws were made necessary because of intervention of the factor 'error' in the nuclear accident. The legal definition of 'error' assumes that it results from non-respect or negligence of established norms on the part of the persons who manipulate the instruments of radioactive production. Nuclear research should not be undertaken in a country without the formal engagement of the central authorities to take the necessary dispositions to ensure the security and safety of the populations and their possessions. The world community should not admit a scientific activity in the nuclear field in the absence of guarantees for the safety and the security of man. The state that permits the production of nuclear energy is legally responsible for any failure that might result in radioactive spills. Considering the possibility of error and the dangers attached to the manipulation of radioactive material, the legislators have elaborated a series of laws, which take into consideration two principles: a)The inalienable right of man to life as conceived in the monotheistic religions and proclaimed by positive law; and b)The responsibility of the state for the safety and security of its citizens. Of course, error is human; but if man may make an error of judgement in ordinary normal life, he does not have the right to make the least miscalculation when this might lead to a nuclear disaster. (author)

  3. Comparison of the Chernobyl and Fukushima nuclear accidents: A review of the environmental impacts

    Energy Technology Data Exchange (ETDEWEB)

    Steinhauser, Georg, E-mail: georg.steinhauser@colostate.edu; Brandl, Alexander; Johnson, Thomas E.

    2014-02-01

    The environmental impacts of the nuclear accidents of Chernobyl and Fukushima are compared. In almost every respect, the consequences of the Chernobyl accident clearly exceeded those of the Fukushima accident. In both accidents, most of the radioactivity released was due to volatile radionuclides (noble gases, iodine, cesium, tellurium). However, the amount of refractory elements (including actinides) emitted in the course of the Chernobyl accident was approximately four orders of magnitude higher than during the Fukushima accident. For Chernobyl, a total release of 5300 PBq (excluding noble gases) has been established as the most cited source term. For Fukushima, we estimated a total source term of 520 (340–800) PBq. In the course of the Fukushima accident, the majority of the radionuclides (more than 80%) was transported offshore and deposited in the Pacific Ocean. Monitoring campaigns after both accidents reveal that the environmental impact of the Chernobyl accident was much greater than of the Fukushima accident. Both the highly contaminated areas and the evacuated areas are smaller around Fukushima and the projected health effects in Japan are significantly lower than after the Chernobyl accident. This is mainly due to the fact that food safety campaigns and evacuations worked quickly and efficiently after the Fukushima accident. In contrast to Chernobyl, no fatalities due to acute radiation effects occurred in Fukushima. - Highlights: • The environmental effects of Chernobyl and Fukushima are compared. • Releases of radionuclides from Chernobyl exceeded Fukushima by an order of magnitude. • Chernobyl caused more severe radiation-related health effects. • Overall, Chernobyl was a much more severe nuclear accident than Fukushima. • Psychological effects are neglected but important consequences of nuclear accidents.

  4. 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.

  5. Reliability analysis of emergency decay heat removal system of nuclear ship under various accident conditions

    International Nuclear Information System (INIS)

    Matsuoka, Takeshi

    1984-01-01

    A reliability analysis is given for the emergency decay heat removal system of the Nuclear Ship ''Mutsu'' and the emergency sea water cooling system of the Nuclear Ship ''Savannah'', under ten typical nuclear ship accident conditions. Basic event probabilities under these accident conditions are estimated from literature survey. These systems of Mutsu and Savannah have almost the same reliability under the normal condition. The dispersive arrangement of a system is useful to prevent the reduction of the system reliability under the condition of an accident restricted in one room. As for the reliability of these two systems under various accident conditions, it is seen that the configuration and the environmental condition of a system are two main factors which determine the reliability of the system. Furthermore, it was found that, for the evaluation of the effectiveness of safety system of a nuclear ship, it is necessary to evaluate its reliability under various accident conditions. (author)

  6. The assessment of environmental consequences of nuclear reactor accidents

    International Nuclear Information System (INIS)

    Beattie, J.R.

    1981-01-01

    Thorough measures are taken throughout all stages of design, construction and operation of nuclear power reactors, and therefore no accident producing any significant environmental impact is likely to occur. Nevertheless as a precaution, such accidents have been the subject of intensive scientific predictive studies. After a historical review of theoretical papers on reactor accidents and their imagined environmental impacts and of those accidents that have indeed occurred, this paper gives an outline of fission products or other radioactive substances that may or may not be released by an accident, and of their possible effects after dispersion in the atmosphere. This general introduction is followed by sections describing what are sometimes called 'design basis accidents' for four of the main reactor types (magnox, AGR, PWR and CDFR), the precautions against these accidents and the probable degree of environmental impact likely. The paper concludes with a reference to those very low probability accidents which might have more serious environmental impacts, and proceeds from there to show that both the individual and community risks from such accidents are numerically moderate compared to other risks apparently accepted by society. A brief reflection on the relevance of numerical values and perceived risk concludes the paper. (author)

  7. Core fusion accidents in nuclear power reactors. Knowledge review

    International Nuclear Information System (INIS)

    Bentaib, Ahmed; Bonneville, Herve; Clement, Bernard; Cranga, Michel; Fichot, Florian; Koundy, Vincent; Meignen, Renaud; Corenwinder, Francois; Leteinturier, Denis; Monroig, Frederique; Nahas, Georges; Pichereau, Frederique; Van-Dorsselaere, Jean-Pierre; Cenerino, Gerard; Jacquemain, Didier; Raimond, Emmanuel; Ducros, Gerard; Journeau, Christophe; Magallon, Daniel; Seiler, Jean-Marie; Tourniaire, Bruno

    2013-01-01

    This reference document proposes a large and detailed review of severe core fusion accidents occurring in nuclear power reactors. It aims at presenting the scientific aspects of these accidents, a review of knowledge and research perspectives on this issue. After having recalled design and operation principles and safety principles for reactors operating in France, and the main studied and envisaged accident scenarios for the management of severe accidents in French PWRs, the authors describe the physical phenomena occurring during a core fusion accident, in the reactor vessel and in the containment building, their sequence and means to mitigate their effects: development of the accident within the reactor vessel, phenomena able to result in an early failure of the containment building, phenomena able to result in a delayed failure with the corium-concrete interaction, corium retention and cooling in and out of the vessel, release of fission products. They address the behaviour of containment buildings during such an accident (sizing situations, mechanical behaviour, bypasses). They review and discuss lessons learned from accidents (Three Mile Island and Chernobyl) and simulation tests (Phebus-PF). A last chapter gives an overview of software and approaches for the numerical simulation of a core fusion accident

  8. 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

  9. Thyroid side effects prophylaxis in front of nuclear power plant accidents.

    Science.gov (United States)

    Agopiantz, Mikaël; Elhanbali, Ouifak; Demore, Béatrice; Cuny, Thomas; Demarquet, Léa; Ndiaye, Cumba; Barbe, Françoise; Brunaud, Laurent; Weryha, Georges; Klein, Marc

    2016-02-01

    The better knowledge of the mechanisms of nuclear incidents and lessons learned from accidents in the recent past to improve the effectiveness of measures taken following a nuclear accident exposure to fallout of radioactive iodine isotopes. Thus, immediate, passive measures, such as containment, and stopping consumption of contaminated products are paramount. The earliest possible administration of stable iodine as potassium iodide (KI) reduces significantly (up to 90% if taken at the same time of the accident) thyroid radioactive contamination. These tablets should be given in priority to children and pregnant women. The side effects are minor. KI is not recommended for persons aged over 60 years, or for adults suffering from cardiovascular disorders. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

  10. An investigation of awareness on the Fukushima nuclear accident and Radioactive contamination

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jeong Chul; Song, Young Ju [Dept. of Consumer Safety, Korea Consumer Agency, Eumseong (Korea, Republic of)

    2016-05-15

    The objective of this study was to investigate Korean people's awareness about impact of the Fukushima nuclear power plant accident in Japan and radioactive contamination caused by it. The respondents of the survey were 600 adults who resided in the Seoul metropolitan area. The survey results show that the majority of respondents were concerned about impact of radiation leakage that might have an effect on our environment. They were worried about radioactive contamination of foodstuffs, particularly fishery products and preferred to acquire information through TV(49.8%) or the Internet(31.3%). Meanwhile, respondents mentioned that the information on the Fukushima nuclear accident and radioactive contamination had not been sufficient and they didn't know well about the follow-up measures of the government on the accident. Most respondents answered that information on radioactive contamination levels and safety of foods and environment was most needed. The results of this study could be useful to enhance awareness on radioactivity and improve risk communication on nuclear power plant accidents.

  11. Severe accident considerations in Canadian nuclear power reactors

    International Nuclear Information System (INIS)

    Omar, A.M.; Measures, M.P.; Scott, C.K.; Lewis, M.J.

    1990-08-01

    This paper describes a current study on severe accidents being sponsored by the Atomic Energy Control Board (AECB) and provides background on other related Canadian work. Scoping calculations are performed in Phase I of the AECB study to establish the relative consequences of several permutations resulting from six postulated initiating events, nine containment states, and a selection of meteorological conditions and health effects mitigating criteria. In Phase II of the study, selected accidents sequences would be analyzed in detail using models suitable for the design features of the Canadian nuclear power reactors

  12. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hae Kyun; Kim, Sang Nyung [Kyung Hee Univ., Yongin (Korea, Republic of)

    2013-10-15

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was

  13. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Park, Hae Kyun; Kim, Sang Nyung

    2013-01-01

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was conservatively calculated

  14. Flood control construction of Shidao Bay nuclear power plant and safety analysis for hypothetical accident of HTR-PM

    International Nuclear Information System (INIS)

    Chen Yongrong; Zhang Keke; Zhu Li

    2014-01-01

    A series of events triggered by tsunami eventually led to the Fukushima nuclear accident. For drawing lessons from the nuclear accident and applying to Shidao Bay nuclear power plant flood control construction, we compare with the state laws and regulations, and prove the design of Shidao Bay nuclear power plant flood construction. Through introducing the history of domestic tsunamis and the national researches before and after the Fukushima nuclear accident, we expound the tsunami hazards of Shidao Bay nuclear power plant. In addition, in order to verify the safety of HTR-PM, we anticipate the contingent accidents after ''superposition event of earthquake and extreme flood'', and analyse the abilities and measures of HTR-PM to deal with these beyond design basis accidents (BDBA). (author)

  15. Accident sequences simulated at the Juragua nuclear power plant

    International Nuclear Information System (INIS)

    Carbajo, J.J.

    1998-01-01

    Different hypothetical accident sequences have been simulated at Unit 1 of the Juragua nuclear power plant in Cuba, a plant with two VVER-440 V213 units under construction. The computer code MELCOR was employed for these simulations. The sequences simulated are: (1) a design-basis accident (DBA) large loss of coolant accident (LOCA) with the emergency core coolant system (ECCS) on, (2) a station blackout (SBO), (3) a small LOCA (SLOCA) concurrent with SBO, (4) a large LOCA (LLOCA) concurrent with SBO, and (5) a LLOCA concurrent with SBO and with the containment breached at time zero. Timings of important events and source term releases have been calculated for the different sequences analyzed. Under certain weather conditions, the fission products released from the severe accident sequences may travel to southern Florida

  16. Should evacuation conditions after a nuclear accident be revised?

    International Nuclear Information System (INIS)

    Nifenecker, H.

    2011-01-01

    The author proposes to draw lessons from the Fukushima accident, notably in the field of post-accident management. He discusses the definition of an as widely understandable as possible method of description of risks related to irradiations after a nuclear accident. As these irradiations are mainly low dose ones which have a carcinogenic effect, he proposes to assess the average life expectancy loss due to an irradiation. Then, this risk can be easily compared with other risks like air pollution, smoking and passive smoking, and so on. Then, once this risk assessment method is well defined, it is possible to associate the inhabitants of contaminated areas to the post-accident management. They could then decide to go back to their homes or not with full knowledge of the facts

  17. Examining accident reports involving autonomous vehicles in California

    Science.gov (United States)

    Nader, Nazanin; Eurich, Sky O.; Tripp, Michelle; Varadaraju, Naresh

    2017-01-01

    Autonomous Vehicle technology is quickly expanding its market and has found in Silicon Valley, California, a strong foothold for preliminary testing on public roads. In an effort to promote safety and transparency to consumers, the California Department of Motor Vehicles has mandated that reports of accidents involving autonomous vehicles be drafted and made available to the public. The present work shows an in-depth analysis of the accident reports filed by different manufacturers that are testing autonomous vehicles in California (testing data from September 2014 to March 2017). The data provides important information on autonomous vehicles accidents’ dynamics, related to the most frequent types of collisions and impacts, accident frequencies, and other contributing factors. The study also explores important implications related to future testing and validation of semi-autonomous vehicles, tracing the investigation back to current literature as well as to the current regulatory panorama. PMID:28931022

  18. Absorbed dose by thyroid in case of nuclear accidents

    International Nuclear Information System (INIS)

    Campos, Laelia; Attie, Marcia Regina Pereira; Amaral, Ademir

    2011-01-01

    Radioisotopes of iodine are produced in abundance in nuclear fission reactions, and great amounts of radioiodine may be released into the environment in case of a nuclear reactor accident. Thyroid gland is among the most radiosensitive organs due to its capacity to concentrate iodine. The aim of this work was to evaluate the importance of contributions of internally deposited iodines ( 131 I, 132 I, 133 I, 134 I and 135 I) to the dose absorbed to thyroid follicle and to the whole organ, after internal contamination by those isotopes. For internal dose calculation, the code of particles transport MCNP4C was employed. The results showed that, in case of nuclear accidents, the contribution of short-lived iodines for total dose is about 45% for thyroid of newborn and about 40% for thyroid of adult. Thus, these contributions should not be neglected in a prospective evaluation of risks associated to internal contamination by radioactive iodine. (author)

  19. Development on Dose Assessment Model of Northeast Asia Nuclear Accident Simulator

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ju Yub; Kim, Ju Youl; Kim, Suk Hoon; Lee, Seung Hee; Yoon, Tae Bin [FNC Techology, Yongin (Korea, Republic of)

    2016-05-15

    In order to support the emergency response system, the simulator for overseas nuclear accident is under development including source-term estimation, atmospheric dispersion modeling and dose assessment. The simulator is named NANAS (Northeast Asia Nuclear Accident Simulator). For the source-term estimation, design characteristics of each reactor type should be reflected into the model. Since there are a lot of reactor types in neighboring countries, the representative reactors of China, Japan and Taiwan have been selected and the source-term estimation models for each reactor have been developed, respectively. For the atmospheric dispersion modeling, Lagrangian particle model will be integrated into the simulator for the long range dispersion modeling in Northeast Asia region. In this study, the dose assessment model has been developed considering external and internal exposure. The dose assessment model has been developed as a part of the overseas nuclear accidents simulator which is named NANAS. It addresses external and internal pathways including cloudshine, groundshine and inhalation. Also, it uses the output of atmospheric dispersion model (i.e. the average concentrations of radionuclides in air and ground) and various coefficients (e.g. dose conversion factor and breathing rate) as an input. Effective dose and thyroid dose for each grid in the Korean Peninsula region are printed out as a format of map projection and chart. Verification and validation on the dose assessment model will be conducted in further study by benchmarking with the measured data of Fukushima Daiichi Nuclear Accident.

  20. Decision making process and emergency management in different phases of a nuclear accident

    International Nuclear Information System (INIS)

    Duranova, T.

    2005-01-01

    EVATECH, Information Requirements and Countermeasure Evaluation Techniques in Nuclear Emergency Management, was a research project in the key action 'Nuclear Fission' of the fifth EURATOM Framework Programme (FP5). The overall objective of the project was to enhance the quality and coherence of response to nuclear emergencies in Europe by improving the decision support methods, models and processes in ways that take into account the expectations and concern of the many different parties involved - stake holders both in managing the emergency response and those who are affected by the consequences of nuclear emergencies. The project had ten partners from seven European countries. The development of the real-time online decision support system RODOS has been one of the major items in the area of radiation protection within the European Commission's Framework Programmes. The main objectives of the RODOS project have been to develop a comprehensive and integrated decision support system that is generally applicable across Europe and to provide a common framework for incorporating the best features of existing decision support systems and future developments. Furthermore the objective has been to provide greater transparency in the decision process to: improve public understanding and acceptance of off-site emergency measures, to facilitate improved communication between countries of monitoring data, predictions of consequences, etc., in the event of any future accident, and to promote, through the development and use of the system, a more coherent, consistent and harmonised response to any future accident that may affect Europe. (authors)

  1. Policy on stable iodine prophylaxis following nuclear reactor accidents (1989)

    International Nuclear Information System (INIS)

    1989-09-01

    This policy considers the alleviation of possible hazards that may arise from any radioiodines inhaled from a plume of fission products emanating from a nuclear reactor accident. Such a nuclear reactor may be land or ship-based. In any accident that releases radioiodines to the environment, one countermeasure that may need to be considered to reduce the effect of inhalation of radioiodines by persons downwind of the point of release is to provide those persons with tablets containing stable iodine. Both potassium iodide (KI) and potassium iodate (KIO 3 ) are recommended as effective prophylactics tablets for this purpose in Australia. Action levels, doses and contraindicatories are briefly outlined

  2. Recent Perspective on the Severe Accident Management Programme for Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kim, Manwoong; Lee, Sukho; Lee, Jungjae; Chung, Kuyoung

    2017-01-01

    Severe Accident Management Guidelines (SAMGs), has been developed to help operators to prevent or mitigate the impacts of accidents at nuclear power plants. Severe accident management was first introduced in the 1990s with the creation of SAMGs following recognition that post-Three Mile Island Emergency Operating Procedures (EOPs) did not adequately address severe core damage conditions. Establishing and maintaining multiple layers of defence against any internal/external hazards is an important measure to reduce radiological risks to the public and environment. This study is intended to suggest future regulatory perspectives to strengthen the prevention and mitigation strategies for severe accidents by review of the current status of revision of IAEA Safety Standard on Severe Accident Management Programmes for Nuclear Power Plants and the combined PWR SAMG. This new IAEA Safety Guide will address guidelines for preparation, development, implementation and review of severe accident management programs during all operating conditions for both reactor and spent fuel pool. This Guide is used by operating organizations of nuclear power plants and their support organizations. It may also be used by national regulatory bodies and technical support organizations as a reference for developing their relevant safety requirements and for conducting reviews and safety assessments for SAMP including SAMG. The Pressurized Water Reactor Owner’s Group (PWROG) is upgrading the original generic Severe Accident Management Guidelines (SAMGs) into single Severe Accident Guidelines (SAGs) for the PWR SAMG aims to consolidate the advantages of each of the separate vendor severe accident (SA) mitigation methods. This new PWROG SAGs changes the SAMG process to be made that can improve SA response. Changes have been made that guidance is available for control room operators when the TSC is not activated thus allowing for timely accident response. Other changes were made to the guidance

  3. Decision-making guide for management of agriculture in the case of a nuclear accident

    International Nuclear Information System (INIS)

    Fourrie, Laetitia; Grosjean, Francois; Adam, Didier; Pretet, Caroline; Michel, Aurelie; Fostier, Bernard; Bertrand, Sophie; Cessac, Bruno; Reales, Nicolas IRSN; Aubert, Claude

    2007-05-01

    For several years, agricultural and nuclear professionals in France have been working on how to manage the agricultural situation in the event of a nuclear accident. This work resulted in measures at both the national (Aube nuclear safety exercises in 2003, INEX3 in 2005) and international levels (EURATOM Programmes). Following on from the European FARMING (FP5) and EURANOS (FP6) works, ACTA', IRSN and six agricultural technical institutes which are specialized in agricultural production and processing network (arable crop [especially cereals, maize, pulses, potatoes and forage crops], fruits and vegetables, vine and wine, livestock farming [cattle, sheep, goats, pigs, poultry]), created a resource adapted to the French context: the Decision-aiding Tool for the Management of Agriculture in case of a Nuclear Accident. Devised for the Ministry of Agriculture services supporting state officials in a radiation emergency, this manual focuses on the early phase following the accident when the state of emergency would make discussion on countermeasures with a large stakeholder panel impossible. Supported by the Ministry of Agriculture and Fisheries and the French Nuclear Safety Authority, this project increased knowledge of post-accident management strategies and made an important contribution to the national think tank set up within the framework of the French Steering Committee for managing the post-event phase of a nuclear accident (CODIRPA). This article describes how the manual evolved throughout the project and the development of new resources

  4. Decision-making guide for management of agriculture in the case of a nuclear accident

    International Nuclear Information System (INIS)

    Reales, N.; Fourrie, L.; Quinio, C.; Grastilleur, Ch.

    2008-01-01

    For several years, agricultural and nuclear professionals in France have been working on how to manage the agricultural situation in the event of a nuclear accident. This work resulted in measures at both the national (Aube nuclear safety exercises in 2003, INEX3 in 2005) and international levels (EURATOM Programmes). Following on from the European FARMING (FP5) and EURANOS (FP6) works, ACTA', IRSN and six agricultural technical institutes which are specialized in agricultural production and processing network (arable crop [especially cereals, maize, pulses, potatoes and forage crops], fruits and vegetables, vine and wine, livestock farming [cattle, sheep, goats, pigs, poultry]), created a resource adapted to the French context: the Decision-aiding Tool for the Management of Agriculture in case of a Nuclear Accident. Devised for the Ministry of Agriculture services supporting state officials in a radiation emergency, this manual focuses on the early phase following the accident when the state of emergency would make discussion on countermeasures with a large stakeholder panel impossible. Supported by the Ministry of Agriculture and Fisheries and the French Nuclear Safety Authority, this project increased knowledge of post-accident management strategies and made an important contribution to the national think tank set up within the framework of the French Steering Committee for managing the post-event phase of a nuclear accident (CODIRPA). This article describes how the manual evolved throughout the project and the development of new resources. (authors)

  5. 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.

  6. Quantifying the social costs of nuclear energy: Perceived risk of accident at nuclear power plants

    International Nuclear Information System (INIS)

    Huhtala, Anni; Remes, Piia

    2017-01-01

    The preferences expressed in voting on nuclear reactor licenses and the risk perceptions of citizens provide insights into social costs of nuclear power and decision making in energy policy. We show analytically that these costs consist of disutility caused by unnecessary anxiety - due to misperceived risks relating to existing reactors - and where licenses for new nuclear reactors are not granted, delayed or totally lost energy production. Empirical evidence is derived from Finnish surveys eliciting explicitly the importance of risk perceptions on preferences regarding nuclear power and its environmental and economic impacts. We show that the estimated marginal impact of a high perceived risk of nuclear accident is statistically significant and that such a perception considerably decreases the probability of a person supporting nuclear power. This result holds across a number of robustness checks including an instrumental variable estimation and a model validation by observed voting behavior of the members of Parliament. The public's risk perceptions translate into a significant social cost, and are likely to affect the revenues, costs and financing conditions in the nuclear power sector in the future. - Highlights: • Survey on preferences regarding nuclear power and its environmental and economic impacts utilized. • A high perceived risk of nuclear accident decreases support for nuclear power. • The public's risk perceptions translate into a significant social cost.

  7. Community response against the nuclear accident. Confusion in Sweden after the Chernobyl nuclear accident and its features

    International Nuclear Information System (INIS)

    Sato, Yoshihiro

    2014-01-01

    The Chernobyl nuclear accident, which occurred in April 1986, became popular in Sweden after two days, and Sweden was hit by a big mess immediately after that. This paper introduces various actions taken in Sweden at that time. The authors analyzed the situation based on the following materials to tell the situation at that time: (1) materials summarized by researchers upon request of the administrative organs of the country, (2) two diaries that were written by Sven Aner, who was a former reporter of a major daily newspaper published after the accident and an activist of antinuclear groups, and Sven Lofvegerg, who handled the accident as a technical officer at Radiation Protection Agency, and (3) newspaper articles at that time. The situations that was revealed after the accident were summarized from the following viewpoints: (1) governmental remarks toward safety standards and effects on residents, and the anxiety of residents, (2) grazing ban on livestock as an important industry and its lifting, (3) correspondence of antinuclear activists, (4) anxiety against the effects of radiation on humans, and counseling on the safety addressed to the Headquarters for Disaster Control, (5) roles of regional radio stations, (6) defects of bureaucracy, (7) criticism against the actions of the Headquarters for Disaster Control, and (8) influence of extreme experts. (A.O.)

  8. The role of chemistry in nuclear accidents

    International Nuclear Information System (INIS)

    Johnson, C.E.; Johnson, I.

    1986-01-01

    An accurate description of the chemical state of fission products is required for quick response in assessing the impact of nuclide release during a nuclear accident. The chemical state of the fission products is certain to change in response to their local environment. More specifically, fission products released from fuel will change their composition on contact with high-temperature steam, and these changes will determine their behavior with regard to either transport, deposition, aerosol formation, or reaction with structural components. The local oxygen potential is a key parameter in establishing the chemical state of the fission products and their release and transport mechanisms. Knowledge of the relationship of this parameter and thermal hydraulics is needed for prediction of fission product behavior in degraded core accidents. The behavior of key fission products in various stages of an accident, based on experimental results and appropriate calculations founded on fundamental thermodynamic information, will be discussed

  9. 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)

  10. Assessing the consequences in a nuclear accident scenario at Cernavoda NPP

    International Nuclear Information System (INIS)

    Margeanu, Sorin; Angelescu, Tatiana

    2004-01-01

    Having in view a possible nuclear incident, considerable planning is necessary to reduce at manageable levels the types of decisions leading to effective responses concerning the public protection. One of the most important parts of an emergency response plan is the computerized system which allows to predict the radiological impact of the accident and to provide information in a manageable and effective form for evaluating alternative countermeasure strategies in the various stages of the accident. In this paper the PC-COSYMA results for early containment failure of a CANDU reactor are presented. The deterministic health effects arising in nuclear accident situation are also presented. As source term we have used the core inventory obtained with ORIGEN computer code. The essential input parameters for PC-COSYMA computer code are also done. (authors)

  11. Discussion on several issues of the accidents management of nuclear power plants in operation

    International Nuclear Information System (INIS)

    Cao Xuewu; Wang Zhe; Zhang Yingzhen

    2009-01-01

    This article discusses several issues of the accident management of nuclear power plants in operation, for example: the necessity, implementation principle of accident management and accident management program etc. For conducting accident management for beyond design basis accidents, this article thinks that the accident management program should be developed and implemented to ensure that the plant and its personnel with responsibilities for accident management are adequately prepared to take effective on-site actions to prevent or mitigate the consequences of severe accident. (authors)

  12. Defining criteria related to wastes for use in multi-criteria decision tool for nuclear accidents

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo N.G.; Guimaraes, Jean R.D., E-mail: dneves@biof.ufrj.br, E-mail: jeanrdg@biof.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto de Biofisica Carlos Chagas Filho; Rochedo, Elaine R.R.; De Luca, Christiano, E-mail: elainerochedo@gmail.com, E-mail: christiano_luca@hotmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Rochedo, Pedro R.R., E-mail: rochedopedro@gmail.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto Alberto Luiz Coimbra de Pos-Graduacao e Pesquisa de Engenharia

    2013-07-01

    The selection of protective measures and strategies for remediation of contaminated areas after a nuclear accident must be based on previously established criteria in order to prevent stress of the population and the unnecessary exposure of workers. After a nuclear accident resulting in environmental contamination, decisions on remediation of areas is complex due to the large numbers of factors involved in decontamination processes. This work is part of a project which aims to develop a multi-criteria tool to support a decision-making process in cases of a radiological or a nuclear accident in Brazil. First, a database of remediation strategies for contaminated areas was created. In this process, the most relevant aspects for the implementation of these strategies were considered, including technical criteria regarding aspects related to the generation of wastes in a reference urban area, which are discussed in this paper. The specific objective of this study is to define criteria for the aspects of radioactive wastes, resulted by the implementation of some urban measures, in order to be incorporated in a multi-criteria decision tool. Main aspects considered were the type, the amount and the type of treatment necessary for each procedure. The decontamination procedures are then classified according to the selected criteria in order to feed the multi-criteria decision tool. This paper describes the steps for the establishment of these criteria and evaluates the potential for future applications in order to improve predictions and to support the decisions to be made. (author)

  13. Defining criteria related to wastes for use in multi-criteria decision tool for nuclear accidents

    International Nuclear Information System (INIS)

    Silva, Diogo N.G.; Guimaraes, Jean R.D.; Rochedo, Elaine R.R.; De Luca, Christiano; Rochedo, Pedro R.R.

    2013-01-01

    The selection of protective measures and strategies for remediation of contaminated areas after a nuclear accident must be based on previously established criteria in order to prevent stress of the population and the unnecessary exposure of workers. After a nuclear accident resulting in environmental contamination, decisions on remediation of areas is complex due to the large numbers of factors involved in decontamination processes. This work is part of a project which aims to develop a multi-criteria tool to support a decision-making process in cases of a radiological or a nuclear accident in Brazil. First, a database of remediation strategies for contaminated areas was created. In this process, the most relevant aspects for the implementation of these strategies were considered, including technical criteria regarding aspects related to the generation of wastes in a reference urban area, which are discussed in this paper. The specific objective of this study is to define criteria for the aspects of radioactive wastes, resulted by the implementation of some urban measures, in order to be incorporated in a multi-criteria decision tool. Main aspects considered were the type, the amount and the type of treatment necessary for each procedure. The decontamination procedures are then classified according to the selected criteria in order to feed the multi-criteria decision tool. This paper describes the steps for the establishment of these criteria and evaluates the potential for future applications in order to improve predictions and to support the decisions to be made. (author)

  14. Influence on UK Nuclear Regulation from the Fukushima Daiichi Accident

    International Nuclear Information System (INIS)

    Savage, R.

    2016-01-01

    This paper provides an overview of the UKs response to the Fukushima Daiichi Accident and highlights the influence that this has had on UK nuclear regulation since March 2011. ONR’s Incident Suite was staffed from the first day of the accident and remained active on a 24 hours basis for over two weeks. The purpose was to provide advice to the UK government specifically prompt assurance of why this accident couldn’t take place in the UK and practical advice in relation to the 17,000 UK nationals in Japan at that time. In the early phase of the accident ONR took part in international cooperation with the US, Canadian and French regulators in order to determine the actual technical status of the Fukushima Daiichi power plant units. The UK Secretary of State requested that the ONR Chief Inspector identify any lessons to be learnt by the UK nuclear industry and in doing so cooperate and coordinate with international colleagues. The Interim report was produced (May 2011) this focused on civil NPP’s, provided background to radiation, technology and regulations. This report compared the Japan situation with the UK and identified 11 conclusions and 26 recommendations.

  15. Impact of the Three Mile Island accident on research and development programs

    International Nuclear Information System (INIS)

    Zammite, R.

    1989-10-01

    The influence of the Three Mile Island (TMI) accident, on the evolution of the nuclear safety engineering concepts, are analyzed. An overview of the nuclear safety studies performed before and after the accident is presented. Before the TMI accident, the research programs were mainly centered on dimensional problems involving factors, such as explosions and earthquakes. The TMI accident demonstrated that the fusion of the reactor's core could actually hoppen. It was also realized that the safety of nuclear power plants depended on accurate research programs, also extended to factors beyond dimensional analysis [fr

  16. Probability estimation of potential harm to human health and life caused by a hypothetical nuclear accident at the nuclear power plant

    International Nuclear Information System (INIS)

    Soloviov, Vladyslav; Pysmenniy, Yevgen

    2015-01-01

    This paper describes some general methodological aspects of the assessment of the damage to human life and health caused by a hypothetical nuclear accident at the nuclear power plant (NPP). Probability estimation of death (due to cancer and non-cancer effects of radiation injury), disability and incapacity of individuals were made by taking into account the regulations of Ukraine. According to the assessment, the probability of death due to cancer and non-cancer effects of radiation damage to individuals who received radiation dose of 1 Sv is equal to 0.09. Probability of disability of 1, 2 or 3 group regardless of the radiation dose is 0.009, 0.0054, 0.027, respectively. Probability of temporary disability of the individual who received dose equal to 33 mSv (the level of potential exposure in a hypothetical nuclear accident at the NPP) is equal 0.16. This probability estimation of potential harm to human health and life caused by a hypothetical nuclear accident can be used for NPP in different countries using requirements of regulations in these countries. And also to estimate the amount of insurance payments due to the nuclear damage in the event of a nuclear accident at the NPP or other nuclear industry enterprise. (author)

  17. Applying Functional Modeling for Accident Management of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lind, Morten; Zhang Xinxin [Harbin Engineering University, Harbin (China)

    2014-08-15

    The paper investigate applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow Modeling is given and a detailed presentation of the foundational means-end concepts is presented and the conditions for proper use in modelling accidents are identified. It is shown that Multilevel Flow Modeling can be used for modelling and reasoning about design basis accidents. Its possible role for information sharing and decision support in accidents beyond design basis is also indicated. A modelling example demonstrating the application of Multilevel Flow Modelling and reasoning for a PWR LOCA is presented.

  18. Severe Accidents: French Regulatory Practice for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Colin, M.

    1997-01-01

    In the framework of a continuous and iterative process, the French Safety Authority asks the utility EDF to implement equipment and procedure modifications on the operating reactors, in order to cope with the most likely Severe Accident sequences. As a result of Probabilistic Safety Assessments published in 1990, important equipment and procedure modifications are being implemented on the French PWRs to improve the safety in shutdown states. The implementation of another set of modifications against some reactivity accident sequences is also in progress. More recently, the Safety Authority expressed specific Severe Accident requirements in terms of instrumentation, equipment qualification, high pressure core melt accidents and hydrogen risk prevention. In that respect, EDF was asked to implement hydrogen recombiners on its reactors. On the other hand, the French Safety authority is involved with its German counterpart in the assessment process of the European Pressurized Water Reactor Project. In consistency with the common recommendations of the Safety Authorities involved, Severe Accident provisions for this reactor are being taken into account at the design stage

  19. Measures for preventing and mitigating severe accidents of nuclear power plants

    International Nuclear Information System (INIS)

    Lin Chengge

    1993-01-01

    Safety goals, integrity of the containment, accident management, functions of existing equipment and measures and emergency preparedness are discussed as technical basis for implementing the new safety code on the nuclear power plant safety design (HAF-0200(91)). The main quantitative safety goals are presented as core melt frequency -5 /ry for new plants and -4 /ry for existing or constructed plants, and 0.1% I, Cs release frequency -6 /ry. To keep the integrity of the containment, main efforts should be placed on the prevention of early failure of the containment and by pass or isolation failures. Should a late failure of the containment occur at a high probability, measures such as filtering vent should be considered. The leak rate of the containment could be higher than the previous 0.1-0.5 wt%/day, depending on the source term and dose results. But, a limiting leak rate of 1 wt%/day is defined. Accident management involves emergency operating procedures, training and retraining for the AM and adding some supporting equipment and display and diagnostic system for the AM. Those requirements are described. Emergency preparedness and measures can reduced the risk significantly. In the most case of accidents, sheltering is preferred as an effective protective actions

  20. Implications of the Fukushima accident of nuclear safety in Finland

    International Nuclear Information System (INIS)

    Valtonen, Keijo

    2012-01-01

    A severe accident took place in Japan at Fukushima Dai-ichi nuclear power plant in March 2011. The immediate cause of the accident was a tsunami caused by the earthquake and the fact that the consequences of large tsunamis were not adequately considered in the design of the plant. Although tsunamis are not considered a real threat in Europe, the European Council requested on 25 March 2011 the European Nuclear Safety Regulators' Group (ENSREG) and the European Commission to undertake a comprehensive and transparent risk and safety assessment (''stress test'') of European nuclear power plants [ENSREG 2011A]. This report is prepared to evaluate the safety provisions of Finnish Nuclear Power Plants as specified in the European ''stress tests''. The technical description is based on the Licensees' reports on the issues within these specifications [Fortum 2011; TVO 2011]. Furthermore, evaluation on the current situation carried out by Radiation and Nuclear Safety Authority (STUK) is provided, and the possibilities to further enhance safety in the Finnish NPPs are presented. According to the ENSREG specifications, earthquakes, flooding and extreme weather conditions were studied in the stress tests. In addition, consequences of losses of some safety functions and finally management of severe accidents were studied, irrespective of their probabilities. The European stress tests cover in Finland all the operating nuclear power plants (Loviisa 1 and 2, Olkiluoto 1 and 2) and the unit under construction (Olkiluoto 3). The intermediate storages of spent fuel in Loviisa and in Olkiluoto are included in the stress tests. The new NPP units to be constructed which do not yet have a construction license, (Fennovoima 1, Olkiluoto 4) are not considered in the European stress tests. (orig.)

  1. Worst accident in the world. Chernobyl: the end of the nuclear dream

    Energy Technology Data Exchange (ETDEWEB)

    Hawkes, N; Lean, G; Leigh, D; McKie, R; Pringle, P; Wilson, A

    1986-01-01

    This is the full story of Chernobyl, before, during and after the reactor accident in April 1986. The scene is set at Chernobyl in the Ukraine. The nature of radioactivity, the risks and the health hazards posed by radioactivity and the world-wide nuclear energy scene are then discussed, followed by the particular nuclear situation in Russia. This includes the background to the nuclear power industry in Russia - its history, personnel and management, and ultimately the building of the Chernobyl nuclear power plant. The accident itself is then explained, minute by minute. The consequences, both short-term and long-term, on the immediate area and the rest of Europe are discussed. These are the medical effects on humans, the effects on the environment and the effect on the nuclear policies of the whole world.

  2. Collaboration within the United Nations system - General matters. Conventions concerning nuclear accidents

    International Nuclear Information System (INIS)

    1988-03-01

    The texts of the Convention on Early Notification of a Nuclear Accident (CENNA) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) are preceded by brief remarks on their origin. The World Health Organization is bound to carry out the activities envisaged, by virtue or its constitutional responsibility for ''promoting, developing, assisting and coordinating international health work''. The Executive Board thus recommends that the WHO accede to both conventions

  3. Anatomy of Sodium Hypochlorite Accidents Involving Facial Ecchymosis – A Review

    Science.gov (United States)

    Zhu, Wan-chun; Gyamfi, Jacqueline; Niu, Li-na; Schoeffel, G. John; Liu, Si-ying; Santarcangelo, Filippo; Khan, Sara; Tay, Kelvin C-Y.; Pashley, David H.; Tay, Franklin R.

    2013-01-01

    Objectives Root canal treatment forms an essential part of general dental practice. Sodium hypochlorite (NaOCl) is the most commonly used irrigant in endodontics due to its ability to dissolve organic soft tissues in the root canal system and its action as a potent antimicrobial agent. Although NaOCl accidents created by extrusion of the irrigant through root apices are relatively rare and are seldom life-threatening, they do create substantial morbidity when they occur. Methods To date, NaOCl accidents have only been published as isolated case reports. Although previous studies have attempted to summarise the symptoms involved in these case reports, there was no endeavor to analyse the distribution of soft tissue distribution in those reports. In this review, the anatomy of a classical NaOCl accident that involves facial swelling and ecchymosis is discussed. Results By summarising the facial manifestations presented in previous case reports, a novel hypothesis that involves intravenous infusion of extruded NaOCl into the facial vein via non-collapsible venous sinusoids within the cancellous bone is presented. Conclusions Understanding the mechanism involved in precipitating a classic NaOCl accident will enable the profession to make the best decision regarding the choice of irrigant delivery techniques in root canal débridement, and for manufacturers to design and improve their irrigation systems to achieve maximum safety and efficient cleanliness of the root canal system. PMID:23994710

  4. Nuclear Power Reactor Core Melt Accidents. Current State of Knowledge

    International Nuclear Information System (INIS)

    Bentaib, Ahmed; Bonneville, Herve; Clement, Bernard; Cranga, Michel; Fichot, Florian; Koundy, Vincent; Meignen, Renaud; Corenwinder, Francois; Leteinturier, Denis; Monroig, Frederique; Nahas, Georges; Pichereau, Frederique; Van-Dorsselaere, Jean-Pierre; Cenerino, Gerard; Jacquemain, Didier; Raimond, Emmanuel; Ducros, Gerard; Journeau, Christophe; Magallon, Daniel; Seiler, Jean-Marie; Tourniaire, Bruno

    2013-01-01

    For over thirty years, IPSN and subsequently IRSN has played a major international role in the field of nuclear power reactor core melt accidents through the undertaking of important experimental programmes (the most significant being the Phebus- FP programme), the development of validated simulation tools (the ASTEC code that is today the leading European tool for modelling severe accidents), and the coordination of the SARNET (Severe Accident Research Network) international network of excellence. These accidents are described as 'severe accidents' because they can lead to radioactive releases outside the plant concerned, with serious consequences for the general public and for the environment. This book compiles the sum of the knowledge acquired on this subject and summarises the lessons that have been learnt from severe accidents around the world for the prevention and reduction of the consequences of such accidents, without addressing those from the Fukushima accident, where knowledge of events is still evolving. The knowledge accumulated by the Institute on these subjects enabled it to play an active role in informing public authorities, the media and the public when this accident occurred, and continues to do so to this day

  5. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

  6. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    International Nuclear Information System (INIS)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established

  7. Application and inspiration of risk control in dose control in Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Yu Shaoqing; Chen Yan; Chai Jianshe; Zhang Chunming

    2013-01-01

    The article introduced the basic concept of risk and risk control methods. Using the risk control methods, we analyzed and evaluated the actions to control dose of public and occupational radiation exposure in the Fukushima Dai-ichi nuclear power plant accident, especially found out the weak points of these actions, and finally discussed the application of the risk control methods in dose management during nuclear accidents. (authors)

  8. Regulatory requirements on accident management and emergency preparedness - concept of nuclear and radiation safety during beyond-design-basis accidents

    International Nuclear Information System (INIS)

    Yanke, R.

    2002-01-01

    Actual practice the and proposals for further activities in the field of Accident Management (AM) in the member countries of the Co-operation Forum of WWER regulators and in Western countries have been assessed. Further the results of the last working group on AM , the overview of interactions of severe accident research and the regulatory positions in various countries, IAEA reports, practice in Switzerland and Finland, were taken into consideration. From this information, the working group derived recommendations on Accident Management. The general proposals correspond to the present state of the art on AM. They do not describe the whole spectra of recommendations on AM for NPPs with WWER reactors. A basis for the implementation of an AM program is given, which could be extended in a follow-up working group. The developments and research concerning AM have to be continued. The positions of various countries with regard to the 'Interactions of severe accident research and the regulatory positions' are given. On the basis of the working group proposals, the WWER regulators could set regulatory requirements and support further developments of AM strategies, making use of the benefits of common features of NPPs with WWER reactors. Concerted actions in the field of AM between the WWER regulators would bundle the development of a unified concept of recommendations and speed up the implementation of AM measures in order to minimise the risks involved in nuclear power generation

  9. Integrating geographical information and augmented reality techniques for mobile escape guidelines on nuclear accident sites

    International Nuclear Information System (INIS)

    Tsai, Ming-Kuan; Lee, Yung-Ching; Lu, Chung-Hsin; Chen, Mei-Hsin; Chou, Tien-Yin; Yau, Nie-Jia

    2012-01-01

    During nuclear accidents, when radioactive materials spread into the environment, the people in the affected areas should evacuate immediately. However, few information systems are available regarding escape guidelines for nuclear accidents. Therefore, this study constructs escape guidelines on mobile phones. This application is called Mobile Escape Guidelines (MEG) and adopts two techniques. One technique is the geographical information that offers multiple representations; the other is the augmented reality that provides semi-realistic information services. When this study tested the mobile escape guidelines, the results showed that this application was capable of identifying the correct locations of users, showing the escape routes, filtering geographical layers, and rapidly generating the relief reports. Users could evacuate from nuclear accident sites easily, even without relief personnel, since using slim devices to access the mobile escape guidelines is convenient. Overall, this study is a useful reference for a nuclear accident emergency response.

  10. Evaluation of nuclear accidents consequences. Risk assessment methodologies, current status and applications

    International Nuclear Information System (INIS)

    Rodriguez, J.M.

    1996-01-01

    General description of the structure and process of the probabilistic methods of assessment the external consequences in the event of nuclear accidents is presented. attention is paid in the interface with Probabilistic Safety Analysis level 3 results (source term evaluation) Also are described key issues in accident consequence evaluation as: effects evaluated (early and late health effects and economic effects due to countermeasures), presentation of accident consequences results, computer codes. Briefly are presented some relevant areas for the applications of Accident Consequence Evaluation

  11. Technique of research of severe accidents and substantiation of safety of nuclear systems

    International Nuclear Information System (INIS)

    Ivanov, E.A.; Tchenov, S.V.

    2001-01-01

    Work is devoted to development of possible ways of solution of the problems of nuclear safety substantiation. We believe that safety in severe accidents is one of significant factors, which restrict value of nuclear industry in future power production. In connection with it we can conclude followed items: -) Substantiation of safety in severe accidents in nuclear system should be built on a deterministic way of guaranteed exception of heavy consequences; -) It is easy that this aim can be achieved by modeling in functions of common type; -) Main purpose of this work is to show that it is possible to estimate physical allowed state of system in emergency and find of trajectory of heaviest scenarios by optimization procedure; and -) In this work we have developed new method and computer code purposed for study of accident conditions of water cooled un-managed nuclear systems such as cooling ponds of spent fuel, experimental facilities etc. (authors)

  12. Study on the code system for the off-site consequences assessment of severe nuclear accident

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sora; Mn, Byung Il; Park, Ki Hyun; Yang, Byung Mo; Suh, Kyung Suk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    The importance of severe nuclear accidents and probabilistic safety assessment (PSA) were brought to international attention with the occurrence of severe nuclear accidents caused by the extreme natural disaster at Fukushima Daiichi nuclear power plant in Japan. In Korea, studies on level 3 PSA had made little progress until recently. The code systems of level 3 PSA, MACCS2 (MELCORE Accident Consequence Code System 2, US), COSYMA (COde SYstem from MAria, EU) and OSCAAR (Off-Site Consequence Analysis code for Atmospheric Releases in reactor accidents, JAPAN), were reviewed in this study, and the disadvantages and limitations of MACCS2 were also analyzed. Experts from Korea and abroad pointed out that the limitations of MACCS2 include the following: MACCS2 cannot simulate multi-unit accidents/release from spent fuel pools, and its atmospheric dispersion is based on a simple Gaussian plume model. Some of these limitations have been improved in the updated versions of MACCS2. The absence of a marine and aquatic dispersion model and the limited simulating range of food-chain and economic models are also important aspects that need to be improved. This paper is expected to be utilized as basic research material for developing a Korean code system for assessing off-site consequences of severe nuclear accidents.

  13. Study on the code system for the off-site consequences assessment of severe nuclear accident

    International Nuclear Information System (INIS)

    Kim, Sora; Mn, Byung Il; Park, Ki Hyun; Yang, Byung Mo; Suh, Kyung Suk

    2016-01-01

    The importance of severe nuclear accidents and probabilistic safety assessment (PSA) were brought to international attention with the occurrence of severe nuclear accidents caused by the extreme natural disaster at Fukushima Daiichi nuclear power plant in Japan. In Korea, studies on level 3 PSA had made little progress until recently. The code systems of level 3 PSA, MACCS2 (MELCORE Accident Consequence Code System 2, US), COSYMA (COde SYstem from MAria, EU) and OSCAAR (Off-Site Consequence Analysis code for Atmospheric Releases in reactor accidents, JAPAN), were reviewed in this study, and the disadvantages and limitations of MACCS2 were also analyzed. Experts from Korea and abroad pointed out that the limitations of MACCS2 include the following: MACCS2 cannot simulate multi-unit accidents/release from spent fuel pools, and its atmospheric dispersion is based on a simple Gaussian plume model. Some of these limitations have been improved in the updated versions of MACCS2. The absence of a marine and aquatic dispersion model and the limited simulating range of food-chain and economic models are also important aspects that need to be improved. This paper is expected to be utilized as basic research material for developing a Korean code system for assessing off-site consequences of severe nuclear accidents

  14. Considering lessons learned about safety culture and their reflection to activity. After Fukushima Daiichi Nuclear Power Plant accident experience

    International Nuclear Information System (INIS)

    Obu, Etsuji; Hamada, Jun; Fukano, Takuya

    2011-01-01

    Fukushima Daiichi Nuclear Power Plant accident forced neighboring residents to evacuate for a long time and gave Public anxieties greatly and significant effects to social activities in Japan. Public trust of nuclear power was lost by not preventing the accident and future of nuclear power became reconsidered, which nuclear industry people regretted deeply. Japan Nuclear Technology Institute (JANTI) had conducted activities enhancing safety culture in nuclear industry. It would be necessary to consider improvements of accident prevention and mitigation measures after evaluating the accident in a viewpoint of 'safety culture'. Based on published information and knowledge accumulated by activities of JANTI, the accident was examined taking account of greatness of nuclear accident and its effects from the side of safety culture. Lessons learned about safety culture were pointed out as; (1) reconfirmation of specialty of nuclear technology. (2) reinforcement of questioning and learning attitudes and (3) improvement of evaluation capability of nuclear safety and safety assurance against external event. These were reflected in activities such as; (1) reconsideration of safety culture assessment, (2) strengthening further support to improve safety culture consciousness and (3) improvement of peer review activity. (T. Tanaka)

  15. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Appendix I. Accident definition and use of event trees

    International Nuclear Information System (INIS)

    1975-10-01

    Information is presented concerning accident definition and use of event trees, event tree methodology, potential accidents covered by the reactor safety study, analysis of potential accidents involving the reactor core, and analysis of potential accidents not involving the core

  16. Evaluation of severe accident environmental conditions taking accident management strategy into account for equipment survivability assessments

    International Nuclear Information System (INIS)

    Lee, Byung Chul; Jeong, Ji Hwan; Na, Man Gyun; Kim, Soong Pyung

    2003-01-01

    This paper presents a methodology utilizing accident management strategy in order to determine accident environmental conditions in equipment survivability assessments. In case that there is well-established accident management strategy for specific nuclear power plant, an application of this tool can provide a technical rationale on equipment survivability assessment so that plant-specific and time-dependent accident environmental conditions could be practically and realistically defined in accordance with the equipment and instrumentation required for accident management strategy or action appropriately taken. For this work, three different tools are introduced; Probabilistic Safety Assessment (PSA) outcomes, major accident management strategy actions, and Accident Environmental Stages (AESs). In order to quantitatively investigate an applicability of accident management strategy to equipment survivability, the accident simulation for a most likely scenario in Korean Standard Nuclear Power Plants (KSNPs) is performed with MAAP4 code. The Accident Management Guidance (AMG) actions such as the Reactor Control System (RCS) depressurization, water injection into the RCS, the containment pressure and temperature control, and hydrogen concentration control in containment are applied. The effects of these AMG actions on the accident environmental conditions are investigated by comparing with those from previous normal accident simulation, especially focused on equipment survivability assessment. As a result, the AMG-involved case shows the higher accident consequences along the accident environmental stages

  17. Analysis on tank truck accidents involved in road hazardous materials transportation in china.

    Science.gov (United States)

    Shen, Xiaoyan; Yan, Ying; Li, Xiaonan; Xie, Chenjiang; Wang, Lihua

    2014-01-01

    Due to the sheer size and capacity of the tanker and the properties of cargo transported in the tank, hazmat tanker accidents are more disastrous than other types of vehicle accidents. The aim of this study was to provide a current survey on the situation of accidents involving tankers transporting hazardous materials in China. Detailed descriptions of 708 tanker accidents associated with hazmat transportation in China from 2004 to 2011 were analyzed to identify causes, location, types, time of occurrence, hazard class for materials involved, consequences, and the corresponding probability. Hazmat tanker accidents mainly occurred in eastern (38.1%) and southwest China (12.3%). The most frequent hazmat tanker accidents involved classes 2, 3, and 8. The predominant accident types were rollover (29.10%), run-off-the-road (16.67%), and rear-end collisions (13.28%), with a high likelihood of a large spill occurring. About 55.93% of the accidents occurred on freeways and class 1 roads, with the spill percentage reaching 75.00% and the proportion of spills that occurred in the total accidents amounting to 77.82%, of which 61.72% are considered large spills. The month with the highest accident probability was July (12.29%), and most crashes occurred during the early morning (4:00-6:00 a.m.) and midday (10:00 a.m.-12:00 p.m.) hours, 19.63% versus 16.10%. Human-related errors (73.8%) and vehicle-related defects (19.6%) were the primary reasons for hazmat tanker crashes. The most common outcomes of a hazmat tanker accident was a spill without further events (55.51%), followed by a release with fire (7.77%), and release with an explosion (2.54%). The safety situation of China's hazmat tanker transportation is grim. Such accidents not only have high spill percentages and consistently large spills but they can also cause serious consequences, such as fires and explosions. Improving the training of drivers and the quality of vehicles, deploying roll stability aids, enhancing

  18. A statistical description of the types and severities of accidents involving tractor semi-trailers

    International Nuclear Information System (INIS)

    Clauss, D.B.; Wilson, R.K.; Blower, D.F.; Campbell, K.L.

    1994-06-01

    This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. Several accident databases were reviewed to determine their suitability to the task. The TIFA (Trucks Involved in Fatal Accidents) database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports for selected TIFA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, fire temperature, fire size, fire separation, and fire duration

  19. The accident of the Three Mile Island nuclear power plant

    International Nuclear Information System (INIS)

    Llory, M.

    1999-01-01

    This book questions which statement can be made twenty years after the accident of the Three Mile Island reactor (USA) on the performances of complex reactor safety systems and on their evolutions and improvements. It questions also todays limits of reactors security and how such a reactor accident can be possible today. It presents also an analysis of the organizations which propose new perspectives in nuclear safety. (J.S.)

  20. To improve nuclear plant safety by learning from accident's experience

    International Nuclear Information System (INIS)

    Matsumoto, Hidezo; Kida, Masanori; Kato, Hiroyuki; Hara, Shin-ichi

    1994-01-01

    The ultimate goal of this study is to produce an expert system that enables the experience (records and information) gained from accidents to be put to use towards improving nuclear plant safety. A number of examples have been investigated, both domestic and overseas, in which experience gained from accidents was utilized by utilities in managing and operating their nuclear power stations to improve safety. The result of investigation has been used to create a general 'basic flow' to make the best use of experience. The ultimate goal is achieved by carrying out this 'basic flow' with artificial intelligence (AI). To do this, it is necessary (1) to apply language analysis to process the source information (primary data base; domestic and overseas accident's reports) into the secondary data base, and (2) to establish an expert system for selecting (screening) significant events from the secondary data base. In the processing described in item (1), a multi-lingual thesaurus for nuclear-related terms become necessary because the source information (primary data bases) itself is multi-lingual. In the work described in item (2), the utilization of probabilistic safety assessment (PSA), for example, is a candidate method for judging the significance of events. Achieving the goal thus requires developing various new techniques. As the first step of the above long-term study project, this report proposes the 'basic flow' and presents the concept of how the nuclear-related AI can be used to carry out this 'basic flow'. (author)

  1. Integrating geographical information and augmented reality techniques for mobile escape guidelines on nuclear accident sites.

    Science.gov (United States)

    Tsai, Ming-Kuan; Lee, Yung-Ching; Lu, Chung-Hsin; Chen, Mei-Hsin; Chou, Tien-Yin; Yau, Nie-Jia

    2012-07-01

    During nuclear accidents, when radioactive materials spread into the environment, the people in the affected areas should evacuate immediately. However, few information systems are available regarding escape guidelines for nuclear accidents. Therefore, this study constructs escape guidelines on mobile phones. This application is called Mobile Escape Guidelines (MEG) and adopts two techniques. One technique is the geographical information that offers multiple representations; the other is the augmented reality that provides semi-realistic information services. When this study tested the mobile escape guidelines, the results showed that this application was capable of identifying the correct locations of users, showing the escape routes, filtering geographical layers, and rapidly generating the relief reports. Users could evacuate from nuclear accident sites easily, even without relief personnel, since using slim devices to access the mobile escape guidelines is convenient. Overall, this study is a useful reference for a nuclear accident emergency response. Copyright © 2012 Elsevier Ltd. All rights reserved.

  2. The Three Mile Island accident, a world premiere for nuclear energy

    International Nuclear Information System (INIS)

    Bouvier, Yves

    2015-01-01

    When it happened on 28 March 1979, the accident at the Three Mile Island nuclear power station in Pennsylvania took experts and operators by surprise. Although human losses were minor, this world shaking media event significantly changed public attitudes towards nuclear energy and put a definitive stop to the development of nuclear power in the USA. (author)

  3. Biological and medical consequences of nuclear accidents

    International Nuclear Information System (INIS)

    Latarjet, R.

    1988-01-01

    The study of the medical and biological consequences of the nuclear accidents is a vast program. The Chernobyl accident has caused some thirty deceases: Some of them were rapid and the others occurred after a certain time. The particularity of these deaths was that the irradiation has been associated to burns and traumatisms. The lesson learnt from the Chernobyl accident is to treat the burn and the traumatism before treating the irradiation. Contrary to what the research workers believe, the first wave of deaths has passed between 15 and 35 days and it has not been followed by any others. But the therapeutic lesson drawn from the accident confirm the research workers results; for example: the radioactive doses band that determines where the therapy could be efficacious or not. the medical cares dispensed to the irradiated people in the hospital of Moscow has confirmed that the biochemical equilibrium of proteinic elements of blood has to be maintained, and the transfusion of the purified elements are very important to restore a patient to health, and the sterilization of the medium (room, food, bedding,etc...) of the patient is indispensable. Therefore, it is necessary to establish an international cooperation for providing enough sterilized rooms and specialists in the irradiation treatment. The genetic consequences and cancers from the Chernobyl accident have been discussed. It is impossible to detect these consequences because of their negligible percentages. (author)

  4. International seminar on Post nuclear accident from May 5 and 6, 2011 - The CODIRPA progresses

    International Nuclear Information System (INIS)

    Birraux, Claude; Lacoste, Andre-Claude; Lachaume, Jean-Luc; Mehl-Auget, Isabelle; Godet, Jean-Luc; Dandrieux, Geraldine; Delmestre, Alain; Gallay, Florence; Niel, Jean-Christophe; Bataille, Christian; Dederen, Guillaume; Guenon, Catherine; Repussard, Jacques; Cessac, Bruno; Champion, Didier; Miniere, Dominique; Andrieux, Jean-Luc; Bernard, Herve; Delalonde, Jean-Claude; Calafat, Alexis; Demet, Michel; Barbey, Pierre; Janssens, Augustin; Lazo, Ted; Ahier, Brian; Ugletveit, Finn; Guerson, Nathalie; Riou, Jeanine; Robert, Joel; Pirard, Philippe; Gerbeaux, Jerome; Foix, Olivier; Le Gac, Alain; Lahaye, Thierry; Wiest, Annick; Crouail, Pascal; Lochard, Jacques; Villers, Anita; Eberbach, Friedrich; Murith, Christophe; Samain, Jean-Paul; Javanni, Jean; Averin, Viktor; Trafimchik, Zoia; Liland, Astrid; Durand, Francois

    2011-01-01

    The objective of the seminar is the anticipation of the radiological emergency situations to limit the consequences of nuclear accidents. The Steering Committee to manage the post-accident of a Nuclear Accident or Radiological Emergency (CODIRPA) was started in June 2005 by the French nuclear safety authority (ASN), and was charged with developing French policy for the management of the post-accident phase of a nuclear or radiological accident situation. An ambitious program mobilising more than 200 people was put in place, including representatives of relevant national administrations and their local representatives, utility and industrial representatives, technical service organisations, nuclear safety authorities from bordering countries to France, NGOs and local elected officials. On December 2007, the previous seminar had constructively challenged the work of CODIRPA with international experiences and analysis. The 2011 seminar, organized by ASN with the support of the Parliamentary Office for the Evaluation of Scientific Choices and Technologies (OPECST), reports on the progress of the national doctrine's construction. The National Preparedness Guide for Exiting the Emergency Phase and drawn lessons concerning its local adaptation by regional and local community governmental organizations was presented at this occasion. The parliamentary mission headed by OPECST on the safety of nuclear installations holds its first public hearing on May 5, 2011. The seminar provides an opportunity for members of the parliamentary mission to learn about crisis management and post-accident of the major nuclear accident occurred in Japan at Fukushima. This document comprises a complete FR/EN detailed synthesis of the seminar followed by the recommendations of CODIRPA (in French) and by the slides of the available presentations for each session: Opening of the meeting; Session 1: National Preparedness Guide for Exiting the Emergency Phase; Session 2: Development of the

  5. The consequences of the Chernobyl nuclear accident in Greece - Report No. 2

    International Nuclear Information System (INIS)

    1986-12-01

    In this report a realistic estimate of the radioactive fallout on Greece from the Chernobyl nuclear accident is described. The measurements performed on environmental samples and samples of the food chain, as well as some realistic estimations for the population doses and 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.)

  6. Report on the preliminary fact finding mission following the accident at the nuclear fuel processing facility in Tokaimura, Japan

    International Nuclear Information System (INIS)

    1999-01-01

    Following the accident on 30 September 1999 at the nuclear fuel processing facility at Tokaimura, Japan, the IAEA Emergency Response Centre received numerous requests for information about the event's causes and consequences from Contact Points under the Conventions on Early Notification of a Nuclear Accident and on Assistance in the Case of a Nuclear Accident or Radiological Emergency. Although the lack of transboundary consequences of the accident meant that action under the Early Notification Convention was not triggered, the Emergency Response Centre issued several advisories to Member States which drew on official reports received from Japan. After discussions with the Government of Japan, the IAEA dispatched a team of three experts from the Secretariat on a fact finding mission to Tokaimura from 13 to 17 October 1999. The present preliminary report by that team documents key technical information obtained during the mission. At this stage, the report can in no way provide conclusive judgements on the causes and consequences of the accident. Investigations are proceeding in Japan and more information is expected to be made available after access has been gained to the building where the accident occurred. Moreover, much of the information already made available will be revised as more accurate assessments are made, for example of the radiation doses to the three individuals who received the highest exposures. Notwithstanding the preliminary nature of this report, it is clear that the accident was not one involving widespread contamination of the environment as in the 1986 Chernobyl accident. Although there was little risk off the site once the accident had been brought under control, the authorities evacuated the population living within a few hundred metres and advised people within about 10 km of the facility to take shelter for a period of about one day. The event at Tokaimura was nevertheless a serious industrial accident. The results of the detailed

  7. Integration of risk aversion in the evaluation of the external cost of a nuclear accident

    International Nuclear Information System (INIS)

    Eeckhoudt, L.; Schieber, C.; Schneider, Th.

    1998-01-01

    Full text of publication follows: the external costs of fuel cycles used in the production of electricity are those imposed on society and environment that are not accounted for by the producers and consumers of energy. Within the evaluation of the external cost of the nuclear fuel cycle, the evaluation of a nuclear accident has to be addressed. For this purpose, the basic approach consists in calculating the expected value of various occident scenarios. the main criticism of this approach is that there is a discrepancy between the social acceptability of the risk and the average monetary value which corresponds in principle to the compensation of the consequences for each individual of the population affected by the accident. The aim of this paper is to propose a methodology for the integration of risk aversion, relying on the expected utility approach, as well as a numerical application based on the French data for the external cost of a nuclear accident. Although a huge range of values has been published for the relative risk aversion coefficient, it seems reasonable to adopt a value of 2 for the specific case of nuclear accident. This leads to an estimated multiplying coefficient approximately equal to 20 to be applied to the expected external cost of a nuclear accident corresponding to a release of about 1% of the core. In this case, the external cost of the nuclear accident is estimated to 0.046 mECU/kWh (i.e. about 50% of the total external costs of the nuclear fuel cycle estimated at 0.1 mECU/kWh with a 3% discount rate), instead of 0.0023 mECU/kWh without taking into account risk aversion. (authors)

  8. The water role in a nuclear accident - Measures to be taken

    International Nuclear Information System (INIS)

    Ambroggi, R.

    1988-01-01

    In case of nuclear accidents or natural disasters, the contaminated water plays a large part in the environment contamination. This is illustrated by two examples: Agadir earthquake and Chernobyl accident. In Agadir earthquake, the contamination of the water was caused by the mutiple breaking down of the water pipes, and in Chernobyl accident it was derived from: -The reactor cooling water; -The radioactive fallout; -The radioactive clouds. The water concentrates incessantly the radioactivity proceeding by the hydrological cycle: Evaporation, precipitation, flowing. The radio-activity concentration by the water and the atmosphere contamination are explained in this paper. In USSR, the radioactive contamination has affected several Ukranian rivers and the artificial lake of Kiev. The measures that have been taken in USSR and in the next countries to prevent the radioactive contamination propagation by water have been discussed. The reparation of chernobyl accident damages is estimated to three milliard $. Theoretically, every nation, using nuclear energy, has a protection system for the accidental situations but none of them has a second protection system for the accidental situations occuring in the distance. The measures to be taken for the latter situations, particularly in Morocco, have been cited. The lessons learnt from the chernobyl accident have served to broaden the inter-national cooperation fields. 15 figs., 1 tab. (author)

  9. Mitigation of severe accidents in Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Soederman, E.

    1987-01-01

    Sweden is the first country to build filtered venting systems, the first one became operable at Barsebaeck nuclear power plant in 1985. In new concepts, now being installed in Sweden, an enhanced containment spray system is the basic element and the filtered venting is only the secondary mitigating system. The filter is a new design, a submerged multi venturi scrubber. The Swedish strategy has been built on three basics: improved knowledge through research; containment integrity through mitigating systems; and accident management to prevent severe accidents. 2 figs

  10. Current state of the communications program concerning nuclear energy following the JCO accident

    International Nuclear Information System (INIS)

    Mitsui, Rie

    2001-01-01

    Full text: Public trust in nuclear energy was significantly affected by a criticality accident that occurred in September 1999 at JCO's uranium re-conversion plant in Tokai-mura Village, Ibaraki Prefecture, some 120 kilometres north-east of Tokyo. An opinion survey was taken with local citizens in December that year, asking them how their views on nuclear energy changed after the accident. The survey findings indicate a grave fact that the citizens, who had lived in harmony with nuclear energy for the past 40 years, lost their confidence in this energy source because of the accident. The mishap also led to severer public opinion on nuclear energy at the nation-wide level, bringing forth a serious impediment to such projects as the siting of new nuclear power plants, the use of plutonium in light water reactors, intermediate storage of spent nuclear fuel, and the promotion of high-level radioactive waste disposal. Japan Atomic Energy Relations Organisation analysed the critical situation surrounding nuclear energy development in the country. Based on the analysis results, JAERO is now actively promoting an interactive, participatory program that meets people's needs, in an effort to regain public trust in nuclear energy. We, at JAERO, believe that greater importance should be attached to the offer of relevant information to the rising generation that will play a leading role in future society. The most typical of JAERO activities for junior and senior high school students include an Essay Content launched in 1968 in commemoration of Atomic Energy Day on October 26 every year and a Radiation Workshop established in 1978. Through more than 11,000 essays collected from junior and senior high school students across the county, this report discusses how these young people think of the JCO criticality accident and what they expect of nuclear energy development in the years ahead. Amid growing public concern with radiation following the JCO accident, the report also

  11. Third IAEA nuclear accident intercomparison experiment

    Energy Technology Data Exchange (ETDEWEB)

    Miric, I; Ubovic, Z

    1974-05-15

    The purpose of this report is to present the results of the International Atomic Energy Agency intercomparison experiments held at the 'Boris Kidric' Institute, Vinca, in May 1973. The experiments are parts of a multilaboratory intercomparison programme sponsored by the IAEA for the evaluation of nuclear accident dosimetry systems and eventually recommendation of dosimetry systems that will provide adequate informations in the event of a criticality accident. The previous two studies were held at the Valduc Centre near Dijon (France) in June 1970 and at the ORNL in Oak Ridge (USA), in May 1971. Parts of the intercomparison studies were coordination meetings. The topics and conclusions of the Third coordination meeting are given in the Chairman's Report of F.F. Haywood. This paper will deal, therefore, only with data concerning the Third intercomparison experiments in which the RB reactor at Vinca was used as a source of mixed radiation. (author)

  12. Third IAEA nuclear accident intercomparison experiment

    International Nuclear Information System (INIS)

    Miric, I.; Ubovic, Z.

    1974-05-01

    The purpose of this report is to present the results of the International Atomic Energy Agency intercomparison experiments held at the 'Boris Kidric' Institute, Vinca, in May 1973. The experiments are parts of a multilaboratory intercomparison programme sponsored by the IAEA for the evaluation of nuclear accident dosimetry systems and eventually recommendation of dosimetry systems that will provide adequate informations in the event of a criticality accident. The previous two studies were held at the Valduc Centre near Dijon (France) in June 1970 and at the ORNL in Oak Ridge (USA), in May 1971. Parts of the intercomparison studies were coordination meetings. The topics and conclusions of the Third coordination meeting are given in the Chairman's Report of F.F. Haywood. This paper will deal, therefore, only with data concerning the Third intercomparison experiments in which the RB reactor at Vinca was used as a source of mixed radiation. (author)

  13. Effects of the criticality accident at Tokai-mura on the public's attitude to nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Kitada, Atsuko [Institute of Social Research, Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Hayashi, Chikio [The Institute of Statistical Mathematics, Tokyo (Japan)

    2000-09-01

    The objective of our study was to clarify the effects on the public's attitude of nuclear power and the criticality accident that occurred at the JCO plant in Tokai-mura, Ibaraki Prefecture. For this purpose, we conducted an awareness survey in the Kansai and Kanto areas two months after the accident. Analysis was made on the basis of the comparison of the survey results with the data that the Institute of Nuclear Safety System had accumulated through continuous awareness surveys on nuclear power generation (regular surveys) since 1993. The public's reactions were twofold. On one hand, there were emotional reactions about accidents in nuclear facilities and a reduction in the sense of security. On the other hand, there were reactions concerning the image of nuclear power plant workers and demand on electricity utilities for enhanced employee education and training. The latter reactions correspond to the problems pointed out after the JCO accident. Regarding the utilization of nuclear power generation, the opinion that 'the utilization of nuclear power generation is unavoidable' accounts for 60% of those surveyed. With the opinion that 'nuclear power generation should be utilized' added, 70% of those surveyed take an affirmative attitude to nuclear power utilization. This situation has remained about the same since 1998, the year before the JCO accident. Using the quantification method III to analyze a number of questionnaires about nuclear power generation such as the anxiety about it, we determined overall attitude indexes regarding nuclear power to perform a time sequence comparison. The comparison shows that the attitude after the JCO accident tended to be more negative than in 1998. However, no significant difference in the overall indexes is seen between 1993 and 1998. Judging the comparison results on the basis of the time span starting in 1993 allows us to conclude that the JCO accident has not greatly contributed to worsening

  14. Economic risks of nuclear power reactor accidents

    International Nuclear Information System (INIS)

    Burke, R.P.; Aldrich, D.C.

    1984-04-01

    Models to be used for analyses of economic risks from events which occur during US LWR plant operation are developed in this study. The models include capabilities to estimate both onsite and offsite costs of LWR events ranging from routine plant forced outages to severe core-melt accidents resulting in large releases of radioactive material to the environment. The models have been developed for potential use by both the nuclear power industry and regulatory agencies in cost/benefit analyses for decision-making purposes. The new onsite cost models estimate societal losses from power production cost increases, plant capital losses, plant decontamination costs, and plant repair costs which may be incurred after LWR operational events. Early decommissioning costs, plant worker health impact costs, electric utility business costs, nuclear power industry costs, and litigation costs are also addressed. The newly developed offsite economic consequence models estimate The costs of post-accident population protective measures and public health impacts. The costs of population evacuation and temporary relocation, agricultural product disposal, land and property decontamination, and land interdiction are included in the economic models for population protective measures. Costs of health impacts and medical care costs are also included in the models

  15. US nuclear industry approach to severe accident management guidance development and implementation

    International Nuclear Information System (INIS)

    Modeen, D.; Walsh, L.; Oehlberg, R.

    1992-01-01

    The purpose of this paper is to discuss the US nuclear industry activities, occurring under the auspices of Nuclear Management and Resources Council (NUMARC), to define, develop and implement enhancements to utility accident management capabilities. This effort consists of three major parts: (1) Development of a practical framework for evaluation of plant-specific accident management capabilities and the subsequent implementation of selected enhancements. (2) Development of specific technical guidance that address arresting core damage if it begins, either in-vessel or ex-vessel, and maintaining containment integrity. Preventing inadequate core cooling or minimizing the consequences of offsite releases, while considered to be candidate areas for accident management enhancements, have been the subject of intense previous study and development. (3) Plant-specific implementation of accident management enhancements in three areas: (a) personnel resources (organization, training, communications); (b) systems and equipment (restoration and repair, instrumentation, use of alternatives); and (c) information resources (procedures and guidance, technical information, process information)

  16. The impact of the Fukushima nuclear accident on European energy policy

    International Nuclear Information System (INIS)

    Wittneben, Bettina B.F.

    2012-01-01

    The disaster that struck the Fukushima Daiichi nuclear plant in Japan has reignited the international debate on the future of nuclear energy. Interestingly, the incident has been used to both justify nuclear power generation and reconsider past decisions made on established or planned nuclear power sites. Geographically removed from the radioactive fallout, Europe's response to the massive nuclear accident differed greatly among the member states. The UK and Germany stand out as examples of the wide spread of policy response to the Fukushima Daiichi nuclear accident. In the UK, policy makers remained firm on their decision to increase nuclear power generation in the near future, whereas in Germany, the federal government decided to at least temporarily shut down the old generation of nuclear reactors and re-examine the safety of all national nuclear power facilities. Furthermore, a regional voter backlash, fuelled by resentment of the Merkel government's previous commitment to nuclear power, dealt a serious blow to the ruling coalition parties. How can national policy responses to the same event be so divergent in two European countries? This article attempts to answer this question in five arguments. I argue that in contrast to the UK, the German public faced imminent elections, stronger media reporting, increasing trust in renewable technologies, a history of nuclear resistance and a feeling of close cultural proximity to the Japanese.

  17. A DOE-STD-3009 hazard and accident analysis methodology for non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    MAHN, JEFFREY A.; WALKER, SHARON ANN

    2000-01-01

    This paper demonstrates the use of appropriate consequence evaluation criteria in conjunction with generic likelihood of occurrence data to produce consistent hazard analysis results for nonreactor nuclear facility Safety Analysis Reports (SAR). An additional objective is to demonstrate the use of generic likelihood of occurrence data as a means for deriving defendable accident sequence frequencies, thereby enabling the screening of potentially incredible events ( -6 per year) from the design basis accident envelope. Generic likelihood of occurrence data has been used successfully in performing SAR hazard and accident analyses for two nonreactor nuclear facilities at Sandia National Laboratories. DOE-STD-3009-94 addresses and even encourages use of a qualitative binning technique for deriving and ranking nonreactor nuclear facility risks. However, qualitative techniques invariably lead to reviewer requests for more details associated with consequence or likelihood of occurrence bin assignments in the test of the SAR. Hazard analysis data displayed in simple worksheet format generally elicits questions about not only the assumptions behind the data, but also the quantitative bases for the assumptions themselves (engineering judgment may not be considered sufficient by some reviewers). This is especially true where the criteria for qualitative binning of likelihood of occurrence involves numerical ranges. Oftentimes reviewers want to see calculations or at least a discussion of event frequencies or failure probabilities to support likelihood of occurrence bin assignments. This may become a significant point of contention for events that have been binned as incredible. This paper will show how the use of readily available generic data can avoid many of the reviewer questions that will inevitably arise from strictly qualitative analyses, while not significantly increasing the overall burden on the analyst

  18. A neutron dosemeter for nuclear criticality accidents.

    Science.gov (United States)

    d'Errico, F; Curzio, G; Ciolini, R; Del Gratta, A; Nath, R

    2004-01-01

    A neutron dosemeter which offers instant read-out has been developed for nuclear criticality accidents. The system is based on gels containing emulsions of superheated dichlorodifluoromethane droplets, which vaporise into bubbles upon neutron irradiation. The expansion of these bubbles displaces an equivalent volume of gel into a graduated pipette, providing an immediate measure of the dose. Instant read-out is achieved using an array of transmissive optical sensors which consist of coupled LED emitters and phototransistor receivers. When the gel displaced in the pipette crosses the sensing region of the photomicrosensors, it generates a signal collected on a computer through a dedicated acquisition board. The performance of the device was tested during the 2002 International Accident Dosimetry Intercomparison in Valduc, France. The dosemeter was able to follow the initial dose gradient of a simulated accident, providing accurate values of neutron kerma; however, the emulsion was rapidly depleted of all its drops. A model of the depletion effects was developed and it indicates that an adequate dynamic range of the dose response can be achieved by using emulsions of smaller droplets.

  19. A neutron dosemeter for nuclear criticality accidents

    International Nuclear Information System (INIS)

    D'Errico, F.; Curzio, G.; Ciolini, R.; Del Gratta, A.; Nath, R.

    2004-01-01

    A neutron dosemeter which offers instant read-out has been developed for nuclear criticality accidents. The system is based on gels containing emulsions of superheated dichlorodifluoromethane droplets, which vaporise into bubbles upon neutron irradiation. The expansion of these bubbles displaces an equivalent volume of gel into a graduated pipette, providing an immediate measure of the dose. Instant read-out is achieved using an array of transmissive optical sensors which consist of coupled LED emitters and phototransistor receivers. When the gel displaced in the pipette crosses the sensing region of the photo microsensors, it generates a signal collected on a computer through a dedicated acquisition board. The performance of the device was tested during the 2002 International Accident Dosimetry Intercomparison in Valduc (France)). The dosemeter was able to follow the initial dose gradient of a simulated accident, providing accurate values of neutron kerma; however, the emulsion was rapidly depleted of all its drops. A model of the depletion effects was developed and it indicates that an adequate dynamic range of the dose response can be achieved by using emulsions of smaller droplets. (authors)

  20. Three Mile Island nuclear accident and its effect on the surrounding population

    International Nuclear Information System (INIS)

    Tokuhata, G.K.

    1985-01-01

    Although the effect of psychological stress is difficult to predict, these public health concerns should be addressed. The author discusses taking a precautionary route by carefully documenting both the exposed population and its health experiences after the nuclear accident. The already established TMI Population Registry and the TMI Mother-Child Registry provides reliable data bases for longterm followup studies of the health effects (physical, psychological and behavioral), if any, from the TMI nuclear accident for both the general population and for the special cohort of pregnant women and their in-utero exposed children. Causes of death and cancer diagnoses will be routinely ascertained by linkage to the State mortality and cancer incidence files. Data for other physical, psychological and behavioral health indices will be collected every five years, on the basis of a random sample through prospective followup surveys for both cohorts. Regardless of the results of a variety of short-term and long-term studies undertaken, the primary mission of the TMI Health Research Program is to fulfill the need to respond to the much publicised, potentially important public health concerns. Because of the uniqueness of the TMI nuclear accident, thus its historical significance, as well as the scientific need to document health effects of very low dose radiation in humans, the rare opportunity presented by the TMI nuclear accident should not be lost in the pursuit of these important epidemiologic studies

  1. Public attitudes toward nuclear power and the TMI accident

    International Nuclear Information System (INIS)

    Kanga, B.K.

    1983-01-01

    This paper which examines the Three Mile Island accident in the context of public reactions to the plant in the surrounding area emphasises that public attitudes to nuclear power should be discussed according to two time frames - short and long range. Public perception of safety, reliability and economy may be different in the future and the role of the nuclear industry is to operate plants safely and ensure that the public gains a clearer understanding of the essential part played by nuclear reactors in generating electricity. (NEA) [fr

  2. Nuclear accident dosimetry. Revision of emergency data sheets

    International Nuclear Information System (INIS)

    Delafield, H.J.

    1976-09-01

    The Emergency Data Sheets on Nuclear Accident Dosimetry have been revealed following the publication of a three part manual on this subject (Delafield, Dennis and Gibson, AERE-R 7485/6/7, 1973). This memo provides an explanation of the action levels adopted for the initial segregation of irradiated persons following a criticality accident, by monitoring the activity of indium foils contained in personnel dosimeters and the induced body sodium activity. The data sheets are given as an Appendix. They provide basic information on; the segregation of irradiated persons, the estimation of radiation exposure, and the assessment of personnel γ-ray and neutron doses. (author)

  3. Severe accident risks: An assessment for five US nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

    This report summarizes an assessment of the risks from severe accidents in five commercial nuclear power plants in the United State. These risks are measured in a number of ways, including: the estimated frequencies of core damage accidents from internally initiated accidents and externally initiated accidents for two of the plants; the performance of containment structures under severe accident loadings; the potential magnitude of radionuclide releases and offsite consequences of such accidents; and the overall risk (the product of accident frequencies and consequences). Supporting this summary report are a large number of reports written under contract to NRC that provide the detailed discussion of the methods used and results obtained in these risk studies. This report, Volume 3, contains two appendices. Appendix D summarizes comments received, and staff responses, on the first (February 1987) draft of NUREG-1150. Appendix E provides a similar summary of comments and responses, but for the second (June 1989) version of the report

  4. Research of the way of communicating information to the mass media by comparison with the media coverage about nuclear accidents. Analysis of the three main cases of accidents and troubles

    International Nuclear Information System (INIS)

    Tsuchida, Tatsuro; Kimura, Hiroshi

    2011-01-01

    Media coverage plays an important role in delivering information to the public in a rapid and easy-to-understand manner in terms of the subjects of nuclear energy. The mass media has so far covered nuclear accidents that occurred in nuclear facilities. The media coverage usually gains the attention of the public through the news media, such as TV and newspapers. In this study, three main cases of nuclear accidents were quantitatively examined by using the database of a newspaper. In addition, various comments of journalists whom the author interviewed were added for the evaluation of the three cases. As a result, it was revealed that the amount of media reporting commonly reached a maximum just after the nuclear accidents occurred. It became also clear that the smoothness of the information flow from the nuclear industry to the mass media affected the trend of the media coverage from the viewpoints of the duration and number of news reports. Most of the journalists considered that it was significant for the nuclear industry to strengthen the initial reaction on the occasion of nuclear accidents. The nuclear industry should understand the characteristics that are typical of the media coverage on nuclear accidents in the future. (author)

  5. Safety of Ikata Nuclear Power Station from the accident of Three Mile Island

    International Nuclear Information System (INIS)

    Nonaka, Hiroshi

    1979-01-01

    The leak of radioactive substances occurred on March 28, 1979, in the No. 2 plant of Three Mile Island Nuclear Power Station, and this accident must be put to use to prevent similar accidents and to secure safety hereafter in the nuclear power stations being operated in Japan. In the TMI accident, too many problems concerning the operation management seemed to exist in a series of events. In this paper, a few matters related to the TMI accident among the aspects of the operation management in Ikata Nuclear Power Station are reported. As the problems of operation management, it is considered that the operation of the TMI plant was continued as the exit valve of auxiliary feed line was closed, that it took long time to close the root valve for a pressurizer relief valve manually, and that the ECCS was stopped manually. In TMI, the abnormal phenomenon of losing main feed water has occurred 6 times since the attainment of criticality in March, 1978, and the opening and sticking of pressurizer relief valves occurred at least twice in about 150 times of their actuation in the nuclear reactors designed by Babcock and Wilcox Co. In Ikata Nuclear Power Station, these problems are detected early and the suitable measures are taken immediately, therefore it never happens to continue the operation as the problems are left as they are. It is not conceivable that similar troubles occur many times. (Kako, I.)

  6. Changing information needs of social impact of nuclear power plant siting. Through a comparison before and after the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    Kashiwa, Takako; Kawamoto, Yoshimi

    2013-01-01

    In the light of the Fukushima Daiichi nuclear power plant accident, we need to consider a symbiosis method based on the diminution of the nuclear power industry. To find a region that does not excessively depend on the nuclear power industry, it is necessary to examine and discuss the social impact of nuclear-related industries. In this study, we compared people's changing information needs of social impact before and after the Fukushima Daiichi nuclear power plant accident. It was found that the need for information increased after the accident. In particular, there were three research areas where the need for information increased: the consideration of building nuclear power plants, the influence of harmful rumors on the region, and influence on the nuclear power industry. Next, attempts were made to understand whether there is a difference between information needs of social impact by attributes, such as age, sex and knowledge of nuclear power. The information needs of the following categories of people increased after the accident: people aged between 10 and 50 years, women, people who do not have a clear opinion about the use of a nuclear power plant, and people who do not have any knowledge of nuclear power. (author)

  7. Nuclear accident dosimetry intercomparison studies at the Health Physics Research Reactor: a summary (1965-1978)

    International Nuclear Information System (INIS)

    Sims, C.S.; Dickson, H.W.

    1979-01-01

    Fifteen nuclear accident dosimetry intercomparison studies utilizing the fast pulsed Health Physics Research Reactor at the Oak Ridge National Laboratory have been conducted since 1965. These studies have provided a growing number of participants with a forum for discussing and learning more about accident dosimetry systems and with opportunity to test their systems under simulated nuclear accident conditions and to compare their results with those of others making measurements under identical conditions. Shielded and unshielded measurements of the neutron and the gamma doses to phantoms and at area monitoring stations have been made with a wide variety of dosimeter types. The large amount of data available from these measurements throughout the years is summarized, analyzed and discussed. The information in this summary provides an indication of the status of and trends in nuclear accident dosimetry. (author)

  8. Direct measurements of employees involved in the Fukushima Daiichi Nuclear Power Station accident for internal dose estimates. JAEA's experiences

    Energy Technology Data Exchange (ETDEWEB)

    Kurihara, Osamu; Kanai, Katsuta; Nakagawa, Takahiro; Takada, Chie; Momose, Takumaro; Furuta, Sadaaki [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

    2012-11-15

    Japan Atomic Energy Agency (JAEA) performed internal dose measurements of employees involved in the Fukushima Daiichi nuclear power station accident. Nuclear Fuel Cycle Engineering Laboratories (NFCEL), one of the JAEA's core centers, examined 560 of these employees by direct (in vivo) measurements during the period from April 20 to August 5 in 2011. These measurements consisted of whole-body counting for radiocesium and thyroid counting for radioiodine. The whole-body counting was conducted with two types of whole-body counters (WBCs): a standing-type WBC with two large NaI(Tl) detectors (Fastscan{sup TM}, Canberra Inc.) and a chair-type WBC with HPGe detectors (GC5021, Canberra Inc.) installed in a shielded chamber made of 20-cm-thick steel. The thyroid counting was mainly performed using one of the two HPGe detectors equipped with the chair-type WBC. The subjects examined in this work were divided into two groups: Group 1 was the first 39 subjects who were measured up to June 17, 2011 and Group 2 was the remaining 521 subjects who were measured on and after June 18, 2011. The performance of our direct measurements was validated by comparing measurement results of the Group 1 subjects using two different methods (e.g., the standing-type WBC vs. the chair-type WBC). Tentative internal dose estimates of the subjects of Group 1 were also performed based on the assumption of a single intake scenario on either March 12, when the first hydrogen explosion occurred at the station or the first day of work after the accident. It was found that the contribution of {sup 131}I to the total internal dose greatly exceeded those of {sup 134}Cs and {sup 137}Cs, the other major nuclides detected in the measurements. The maximum committed effective dose (CED) was found in a male subject whose thyroid content of {sup 131}I was 9760 Bq on May 23, 2011; the CED of this subject was estimated to be 600 mSv including a small contribution of {sup 134}Cs and {sup 137}Cs. The typical

  9. 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.

  10. 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.

  11. Implementation of accident management programmes in nuclear power plants

    International Nuclear Information System (INIS)

    2004-01-01

    According to the generally established defence in depth concept in nuclear safety, consideration in plant operation is also given to highly improbable severe plant conditions that were not explicitly addressed in the original design of currently operating nuclear power plants (NPPs). Defence in depth is achieved primarily by means of four successive barriers which prevent the release of radioactive material (fuel matrix, cladding, primary coolant boundary and containment), and these barriers are primarily protected by three levels of design measures: prevention of abnormal operation and failures (level 1), control of abnormal operation and detection of failures (level 2) and control of accidents within the design basis (level 3). If these first three levels fail to ensure the structural integrity of the core, e.g. due to beyond the design basis multiple failures, or due to extremely unlikely initiating events, additional efforts are made at level 4 to further reduce the risks. The objective at the fourth level is to ensure that both the likelihood of an accident entailing significant core damage (severe accident) and the magnitude of radioactive releases following a severe accident are kept as low as reasonably achievable. Finally, level 5 includes off-site emergency response measures, with the objective of mitigating the radiological consequences of significant releases of radioactive material. The implementation of the emergency response is usually dependent upon the type and magnitude of the accident. Good co-ordination between the operator and the responding organizations is needed to ensure the appropriate response. Accident management is one of the key components of effective defence in depth. In accordance with defence in depth, each design level should be protected individually, independently of other levels. This report focuses on the fourth level of defence in depth, including the transitions from the third level and into the fifth level. It describes

  12. Economic and social impacts of nuclear accidents on the agricultural sector

    International Nuclear Information System (INIS)

    Brenot, J.; Hubert, P.

    1997-01-01

    The economic and social impact of a major nuclear accident on the agricultural sector are reviewed. The associated costs are evaluated by more or less proper methods depending on the duration and severity of the post accident situation. Calculating such costs is necessary in order to allow farmers, farm-food enterprises, and public authorities to define the indemnification levels as well as to identify means of minimizing the accident consequences. The indemnification procedures are described in a section dedicated to liability issues and the costs due to Chernobyl accident. Concerning the limitation of accident consequences the responsibility falls upon the public authorities. In regard for decision making the existent methods vary according to the situation complexity and proposed objectives. Examples are given to point out the costs and social impact

  13. The impact of accident attention, ideology, and environmentalism on American attitudes toward nuclear energy.

    Science.gov (United States)

    Besley, John C; Oh, Sang-Hwa

    2014-05-01

    This study involves the analysis of three waves of survey data about nuclear energy using a probability-based online panel of respondents in the United States. Survey waves included an initial baseline survey conducted in early 2010, a follow-up survey conducted in 2010 following the Deepwater Horizon oil spill in the Gulf of Mexico, and an additional follow-up conducted just after the 2011 Fukushima, Japan, nuclear accident. The central goal is to assess the degree to which changes in public views following an accident are contingent on individual attention and respondent predispositions. Such results would provide real-world evidence of motivated reasoning. The primary analysis focuses on the impact of Fukushima and how the impact of individual attention to energy issues is moderated by both environmental views and political ideology over time. The analysis uses both mean comparisons and multivariate statistics to test key relationships. Additional variables common in the study of emerging technologies are included in the analysis, including demographics, risk and benefit perceptions, and views about the fairness of decisionmakers in both government and the private sector. © 2013 Society for Risk Analysis.

  14. Considerations on radiation protection and accidents in nuclear medicine

    International Nuclear Information System (INIS)

    Lima, Carla Flavia de; Avelar, Artur Canella; Campos, Tarcisio P.R.

    2001-01-01

    The present study presents the radiation protection in the services of nuclear medicine in relation to the design of the services, manipulation of sources, cares with the patient, accomplishment of procedures and definition of accidents and incidents; besides approaching the CNEN requirements

  15. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne, Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of systematizing

  16. Systematic approach for assessment of accident risks in chemical and nuclear processing; Abordagem sistematica para avaliacao de riscos de acidentes em instalacoes de processamento quimico e nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Senne Junior, Murillo

    2003-07-15

    The industrial accidents which occurred in the last years, particularly in the 80's, contributed a significant way to draw the attention of the government, industry and the society as a whole to the mechanisms for preventing events that could affect people's safety and the environment quality. Techniques and methods extensively used the nuclear, aeronautic and war industries so far were adapted to performing analysis and evaluation of the risks associated to other industrial activities, especially in the petroleum, chemistry and petrochemical areas. The risk analysis in industrial facilities is carried out through the evaluation of the probability or frequency of the accidents and their consequences. However, no systematized methodology that could supply the tools for identifying possible accidents likely to take place in an installation is available in the literature. Neither existing are methodologies for the identification of the models for evaluation of the accidents' consequences nor for the selection of the available techniques for qualitative or quantitative analysis of the possibility of occurrence of the accident being focused. The objective of this work is to develop and implement a methodology for identification of the risks of accidents in chemical and nuclear processing facilities as well as for the evaluation of their consequences on persons. For the development of the methodology, the main possible accidents that could occur in such installations were identified and the qualitative and quantitative techniques available for the identification of the risks and for the evaluation of the consequences of each identified accidents were selected. The use of the methodology was illustrated by applying it in two case examples adapted from the literature, involving accidents with inflammable, explosives, and radioactive materials. The computer code MRA - Methodology for Risk Assessment was developed using DELPHI, version 5.0, with the purpose of

  17. The accident at the Chernobyl' nuclear power plant and its consequences. Pt. 1. General material

    International Nuclear Information System (INIS)

    1986-01-01

    The report contains a presentation of the Chernobyl' nuclear power station and of the RBMK-1000 reactor, including its principal physical characteristics, the safety systems and a description of the site and of the surrounding region. After a chronological account of the events which led to the accident and an analysis of the accident using a mathematical model it is concluded that the prime cause of the accident was an extremely improbable combination of violations of instructions and operating rules committed by the staff of the unit. Technical and organizational measures for improving the safety of nuclear power plants with RBMK reactors have been taken. A detailed description of the actions taken to contain the accident and to alleviate its consequences is given and includes the fire fighting at the nuclear power station, the evaluation of the state of the fuel after the accident, the actions taken to limit the consequences of the accident in the core, the measures taken at units 1, 2 and 3 of the nuclear power station, the monitoring and diagnosis of the state of the damaged unit, the decontamination of the site and of the 30 km zone and the long-term entombment of the damaged unit. The measures taken for environmental radioactive contamination monitoring, starting by the assessment of the quantity, composition and dynamics of fission products release from the damaged reactor are described, including the main characteristics of the radioactive contamination of the atmosphere and of the ground, the possible ecological consequences and data on the exposure of plant and emergency service personnel and of the population in the 30 km zone around the plant. The last part of the report presents some recommendations for improving nuclear power safety, including scientific, technical and organizational aspects and international measures. Finally, an overview of the development of nuclear power in the USSR is given

  18. Emergency response planning and preparedness for transport accidents involving radioactive material

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of this Guide is to provide assistance to public authorities and others (including consignors and carriers of radioactive materials) who are responsible for ensuring safety in establishing and developing emergency response arrangements for responding effectively to transport accidents involving radioactive materials. This Guide is concerned mainly with the preparation of emergency response plans. It provides information which will assist those countries whose involvement with radioactive materials is just beginning and those which have already developed their industries involving radioactive materials and attendant emergency plans, but may need to review and improve these plans. The need for emergency response plans and the ways in which they are implemented vary from country to country. In each country, the responsible authorities must decide how best to apply this Guide, taking into account the actual shipments and associated hazards. In this Guide the emergency response planning and response philosophy are outlined, including identification of emergency response organizations and emergency services that would be required during a transport accident. General consequences which could prevail during an accident are described taking into account the IAEA Regulations for the Safe Transport of Radioactive Material. 43 refs, figs and tabs

  19. Fukushima Nuclear Accident Recorded in Tibetan Plateau Snow Pits

    Science.gov (United States)

    Wang, Ninglian; Wu, Xiaobo; Kehrwald, Natalie; Li, Zhen; Li, Quanlian; Jiang, Xi; Pu, Jianchen

    2015-01-01

    The β radioactivity of snow-pit samples collected in the spring of 2011 on four Tibetan Plateau glaciers demonstrate a remarkable peak in each snow pit profile, with peaks about ten to tens of times higher than background levels. The timing of these peaks suggests that the high radioactivity resulted from the Fukushima nuclear accident that occurred on March 11, 2011 in eastern Japan. Fallout monitoring studies demonstrate that this radioactive material was transported by the westerlies across the middle latitudes of the Northern Hemisphere. The depth of the peak β radioactivity in each snow pit compared with observational precipitation records, suggests that the radioactive fallout reached the Tibetan Plateau and was deposited on glacier surfaces in late March 2011, or approximately 20 days after the nuclear accident. The radioactive fallout existed in the atmosphere over the Tibetan Plateau for about one month. PMID:25658094

  20. Loss of cooling accident simulation of nuclear power station spent-fuel pool

    Energy Technology Data Exchange (ETDEWEB)

    Lee, M.; Liang, K-S., E-mail: mlee@ess.nthu.edu.tw, E-mail: ksliang_1@hotmail.com [National Tsing Hua Univ., Hsinchu, Taiwan (China); Lin, K-Y., E-mail: syrup760914@gmail.com [Taiwan Power Company, Taiwan (China)

    2014-07-01

    The core melt down accident of Fukushima Nuclear Power Station on March 11th, 2011 alerted nuclear industry that the long term loss of cooling of spent fuel pool may need some attention. The target plant analyzed is the Chinshan Nuclear Power Station of Taiwan Power Company. The 3-Dimensional RELAP5 input deck of the spent fuel pool of the station is built. The results indicate that spent fuel of Chinshan Nuclear Power Station is uncovered at 6.75 days after an accident of loss cooling takes place and cladding temperature rises above 2,200{sup o}F around 8 days. The time is about 13 hours earlier than the results predicted using simple energy balance method. The results also show that the impact of Counter Current Flow Limitation (CCFL) and radiation heat transfer model is marginal. (author)

  1. Agricultural implications of the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Nakanishi, Tomoko M.; Tanoi, Keitaro

    2013-01-01

    Since the Fukushima Daiichi nuclear power plant accident in March 2011, contamination of places and foods has been a matter of concern. Unfortunately, agricultural producers have few sources of information and have had to rely on the lessons from the Chernobyl accident in 1986 or on information obtained from the International Atomic Energy Agency. However, as of this writing, data on the specific consequences of the Fukushima accident on Japanese agriculture remain limited. More than 80% of the land that suffered from the accident was related to agriculture or was in forests and meadows. The in fluence of the accident on agriculture was the most difficult to study because the activity in nature had to be dealt with. For example, when contaminated rice is harvested, scientists working on rice plants and soils and the study of watercourses or mountains have to collaborate to analyze or determine the vehicle by which the radioactivity accumulated and through which it spread in nature. At the request of agriculturists in Fukushima, we at the Graduate School of Agricultural and Life Sciences at The University of Tokyo have been urgently collecting reliable data on the contamination of soil, plants, milk, and crops. Based on our data, we would like to comment on or propose an effective way of resuming agricultural activity. Because obtaining research results based on in situ experiments is time-consuming, we have been periodically holding research report meetings at our university every 3-4 months for lay people, showing them how the contamination situation has changed or what type of effect can be estimated. Although our research is still ongoing, we would like to summarize in this book our observations made during the one and a half years after the accident. (author)

  2. Assessment of environmental public exposure from a hypothetical nuclear accident for Unit-1 Bushehr nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sohrabi, M.; Ghasemi, M.; Amrollahi, R.; Khamooshi, C.; Parsouzi, Z. [Amirkabir University of Technology, Health Physics and Dosimetry Research Laboratory, Department of Physics, Tehran (Iran, Islamic Republic of)

    2013-05-15

    Unit-1 of the Bushehr nuclear power plant (BNPP-1) is a VVER-type reactor with 1,000-MWe power constructed near Bushehr city at the coast of the Persian Gulf, Iran. The reactor has been recently operational to near its full power. The radiological impact of nuclear power plant (NPP) accidents is of public concern, and the assessment of radiological consequences of any hypothetical nuclear accident on public exposure is vital. The hypothetical accident scenario considered in this paper is a design-basis accident, that is, a primary coolant leakage to the secondary circuit. This scenario was selected in order to compare and verify the results obtained in the present paper with those reported in the Final Safety Analysis Report (FSAR 2007) of the BNPP-1 and to develop a well-proven methodology that can be used to study other and more severe hypothetical accident scenarios for this reactor. In the present study, the version 2.01 of the PC COSYMA code was applied. In the early phase of the accidental releases, effective doses (from external and internal exposures) as well as individual and collective doses (due to the late phase of accidental releases) were evaluated. The surrounding area of the BNPP-1 within a radius of 80 km was subdivided into seven concentric rings and 16 sectors, and distribution of population and agricultural products was calculated for this grid. The results show that during the first year following the modeled hypothetical accident, the effective doses do not exceed the limit of 5 mSv, for the considered distances from the BNPP-1. The results obtained in this study are in good agreement with those in the FSAR-2007 report. The agreement obtained is in light of many inherent uncertainties and variables existing in the two modeling procedures applied and proves that the methodology applied here can also be used to model other severe hypothetical accident scenarios of the BNPP-1 such as a small and large break in the reactor coolant system as well

  3. Cooperation in the Event of Nuclear Accidents; Cooperation en Matiere d'Accidents Nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Bresson, G. [CEA, Centre d' etudes nucleaires, de Fontenay-aux-Roses (France)

    1969-10-15

    This paper is concerned only with the action to be taken in respect of an individual directly affected by an accident and not with the more general measures relating to the population as a whole. Keeping the same sequence of ideas, the paper deals with nuclear establishments and cites criteria for classifying them; hence only the relationship between the establishment and the hospital, and between the radiation protection experts and medical personnel, is discussed. The complex organization of emergency measures, reception of the victim of the accident, and the treatment possibly required should be based on standard practice and published material, both national and international, allowance being made for the characteristics of each sector. A ''flexible'' plan of co-ordination is given as an illustration. Action must be taken in such cases at the site of the accident, inside and outside the establishment, and above all at the hospital. All categories of persons are involved in the process, i.e. fellow-workers, management, specialized services, and medical personnel, each with their own part to play. The manpower and equipment brought into service therefore vary, and depend upon the internal and external relations maintained by the establishment. The measures envisaged should provide for the transport, reception and treatment of those involved in the accident. An existing organization of this kind is described as an illustration. Finally, no action can be of value without full knowledge of the facts and thorough training of the personnel. Some clearly defined ideas on the.subject are considered under this heading. (author) [French] Le memoire ne traite que de la conduite a tenir envers un accidente et non du probleme, plus general, des mesures relatives a une population. Dans le meme ordre d'idees, l'etude porte sur les etablissements nucleaires et leurs criteres de classement; il ne s'agit donc que des liaisons entre retablissement et l'hopital et entre les

  4. Legislative framework on establishing emergency response plan in the case of a nuclear accident

    International Nuclear Information System (INIS)

    Novosel, N.; Valcic, I.; Biscan, R.

    2000-01-01

    To give an overview of the legislative framework, which defined emergency planning in Croatia in the case of a nuclear accident, it's necessary to look at all international recommendations and obligations and the national legislation, acts and regulations. It has to be emphasized that Croatia signed three international conventions in this field, and by that took over some responsibilities and obligations. Beside that, it is also in Croatian interest to follow the recommendations of international institutions such as International Atomic Energy Agency (IAEA standards and technical documents). On the other hand, national legislation in this field consists of several laws, which cover nuclear safety measures, governmental organization, natural disasters and acts (decree, decisions) of responsible authority for emergency planning in the case of a nuclear accident (Ministry of Economy). This paper presents an overview of the international and Croatian legislation which influenced the emergency planning in the case of a nuclear accident. (author)

  5. A simplified model for calculating early offsite consequences from nuclear reactor accidents

    International Nuclear Information System (INIS)

    Madni, I.K.; Cazzoli, E.G.; Khatib-Rahbar, M.

    1988-07-01

    A personal computer-based model, SMART, has been developed that uses an integral approach for calculating early offsite consequences from nuclear reactor accidents. The solution procedure uses simplified meteorology and involves direct analytic integration of air concentration equations over time and position. This is different from the discretization approach currently used in the CRAC2 and MACCS codes. The SMART code is fast-running, thereby providing a valuable tool for sensitivity and uncertainty studies. The code was benchmarked against both MACCS version 1.4 and CRAC2. Results of benchmarking and detailed sensitivity/uncertainty analyses using SMART are presented. 34 refs., 21 figs., 24 tabs

  6. Benchmarking severe accident computer codes for heavy water reactor applications

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J.H. [International Atomic Energy Agency, Vienna (Austria)

    2010-07-01

    Consideration of severe accidents at a nuclear power plant (NPP) is an essential component of the defence in depth approach used in nuclear safety. Severe accident analysis involves very complex physical phenomena that occur sequentially during various stages of accident progression. Computer codes are essential tools for understanding how the reactor and its containment might respond under severe accident conditions. International cooperative research programmes are established by the IAEA in areas that are of common interest to a number of Member States. These co-operative efforts are carried out through coordinated research projects (CRPs), typically 3 to 6 years in duration, and often involving experimental activities. Such CRPs allow a sharing of efforts on an international basis, foster team-building and benefit from the experience and expertise of researchers from all participating institutes. The IAEA is organizing a CRP on benchmarking severe accident computer codes for heavy water reactor (HWR) applications. The CRP scope includes defining the severe accident sequence and conducting benchmark analyses for HWRs, evaluating the capabilities of existing computer codes to predict important severe accident phenomena, and suggesting necessary code improvements and/or new experiments to reduce uncertainties. The CRP has been planned on the advice and with the support of the IAEA Nuclear Energy Department's Technical Working Groups on Advanced Technologies for HWRs. (author)

  7. Safety demonstration analyses at JAERI for severe accident during overland transport of fresh nuclear fuel

    International Nuclear Information System (INIS)

    Nomura, Yasushi; Kitao, Kohichi; Karasawa, Kiyonori; Yamada, Kenji; Takahashi, Satoshi; Watanabe, Kohji; Okuno, Hiroshi; Miyoshi, Yoshinori

    2005-01-01

    It is expected in the near future that more and more fresh nuclear fuel will be transported in a variety of transport packages to cope with increasing demand from nuclear fuel cycle facilities. Accordingly, safety demonstration analyses are planned and conducted at JAERI under contract with the Ministry of Economy, Trade and Industry of Japan. These analyses are conducted in a four year plan from 2001 to 2004 to verify integrity of packaging against leakage of radioactive material in the case of a severe accident postulated to occur during transportation, for the purpose of gaining acceptance of such nuclear fuel activities. In order to create the accident scenarios, actual transportation routes were surveyed, accident or incident records were tracked, international radioactive material transport regulations such as IAEA rules were investigated and thus, accident conditions leading to mechanical damages and thermal failure were determined to characterize the scenarios. As a result, the worst-case conditions of run-off-the-road accidents were set up to define the impact against a concrete or asphalt surface. For fire accident scenarios to be set up, collisions were assumed to occur with an oil tanker carrying lots of inflammable material in open air, or with a commonly used two-ton-truck inside a tunnel without ventilation. Then the cask models were determined for these safety demonstration analyses to represent those commonly used for fresh nuclear fuel transported throughout Japan. Following the postulated accident scenarios, the mechanical damages were analyzed by using the general-purpose finite element code LS-DYNA with three-dimensional elements. It was found that leak tightness of the package be maintained even in the severe impact scenario. Then the thermal safety was analyzed by using the general-purpose finite element code ABAOUS with three-dimensional elements to describe cask geometry. As a result of the thermal analyses, the integrity of the containment

  8. 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

  9. The Greenpeace book of the nuclear age

    International Nuclear Information System (INIS)

    May, John

    1989-01-01

    This is a comprehensive popular account of both civil and military nuclear accidents. It documents major reactor accidents in certain categories such as where significant injury of death occurred, where there was considerable radioactivity release offsite or where there was actual or suspected core damage. Military accidents on nuclear submarines or involving nuclear weapons and civil incidents such as those involving radioactive waste are also included. the book is organised chronologically from the 1940s through succeeding decades to the 1980s. A concluding chapter gives Greenpeace's own perspective on the state of the nuclear age. (author)

  10. 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

  11. [A spatially explicit analysis of traffic accidents involving pedestrians and cyclists in Berlin].

    Science.gov (United States)

    Lakes, Tobia

    2017-12-01

    In many German cities and counties, sustainable mobility concepts that strengthen pedestrian and cyclist traffic are promoted. From the perspectives of urban development, traffic planning and public healthcare, a spatially differentiated analysis of traffic accident data is decisive. 1) The identification of spatial and temporal patterns of the distribution of accidents involving cyclists and pedestrians, 2) the identification of hotspots and exploration of possible underlying causes and 3) the critical discussion of benefits and challenges of the results and the derivation of conclusions. Spatio-temporal distributions of data from accident statistics in Berlin involving pedestrians and cyclists from 2011 to 2015 were analysed with geographic information systems (GIS). While the total number of accidents remains relatively stable for pedestrian and cyclist accidents, the spatial distribution analysis shows, however, that there are significant spatial clusters (hotspots) of traffic accidents with a strong concentration in the inner city area. In a critical discussion, the benefits of geographic concepts are identified, such as spatially explicit health data (in this case traffic accident data), the importance of the integration of other data sources for the evaluation of the health impact of areas (traffic accident statistics of the police), and the possibilities and limitations of spatial-temporal data analysis (spatial point-density analyses) for the derivation of decision-supported recommendations and for the evaluation of policy measures of health prevention and of health-relevant urban development.

  12. Japanese authorities inform IAEA about accident at nuclear plant

    International Nuclear Information System (INIS)

    2004-01-01

    Full text: The IAEA today received information from Japanese nuclear regulatory authorities about an accident in the steam generator turbine circuit of the Mihama Nuclear Power Plant (unit 3). According to the Japanese nuclear authorities this is a non-radioactive part of the plant. The regulatory body has reported that four contract employees died and 7 were injured, and stated that there was no release of radioactivity. The IAEA continues to be in contact with Japanese authorities and expects to receive updates on a continuous basis. No request for IAEA assistance has been received at this time. (IAEA)

  13. Radioactive Waste Management In The Chernobyl Exclusion Zone - 25 Years Since The Chernobyl Nuclear Power Plant Accident

    International Nuclear Information System (INIS)

    Farfan, E.; Jannik, T.

    2011-01-01

    Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures

  14. A CD-ROM About Radiation Protection Aspects of a Nuclear Accident: Towards more Openness and Transparency

    International Nuclear Information System (INIS)

    Oudiz, Andre

    2003-01-01

    Many players are involved in managing a nuclear accident apart from radiation protection and nuclear safety experts. In an emergency response situation, the decision making process involves many non-technical players who nonetheless have a major role to play: in France these may include the 'Prefet', the emergency and civil defence services, the health services, the police, the 'gendarmerie' and local councillors, with advice from the safety and radiological protection authorities and expert evaluation organisations. Within the post-accident response, other players will be involved alongside those already described : professional bodies, particularly farming organisations, residents' associations, those responsible for environmental decontamination, agencies responsible for compensating victims, etc., etc. In both the short and the long-term phases of the crisis management process, it is essential to enable participants who may have very different -backgrounds and professional experience to work together with co-operation and mutual understanding. If non-technical players are to contribute effectively, there needs to be a minimum level of mutual understanding between them and the technical. players on what the nuclear risk really is and what is the rationale of the short and long term counter-measures aimed at protecting the public and restoring the contaminated environment. Local communities also need to share this basic understanding because their cooperation is required in order to implement the countermeasures properly. Conversely, if the experts are to advise the local authorities properly, they need to understand the criteria on which these local authorities and communities base their decisions: what psycho sociological factors apply, what logistical support is needed, what are the concerns of the local communities? The CD-ROM should help in gradually building up a shared interpretation or culture of the nuclear risk. This forum should promote debate that is

  15. Mothers' knowledge of domestic accident prevention involving children in Baghdad City.

    Science.gov (United States)

    Lafta, Riyadh K; Al-Shatari, Sahar A; Abass, Seba

    2013-01-01

    Accidental injuries are the most common cause of death in children over the age of one. Every year, millions of children are permanently disabled or disfigured because of accidents. To assess the level of knowledge of women with respect to children's domestic accidents, and to determine its association with some demographic factors. This cross-sectional study was conducted in both sides of Baghdad City during the period from April through to August 2013. The targeted population were women attending the primary health care centers (PHCCs). A random sample of 20 PHCCs was taken through a stratified random sampling technique by dividing Baghdad City into its two main parts Karkh and Russafa. Ten centers were then chosen from each sector by a simple random sampling technique. A well-structured questionnaire was developed that constituted of questions on four main types of accidents involving children (poisoning by chemicals and detergents, electric shock, injuries from sharp instruments in the kitchen, and burns). The total number of women enrolled in this study was 1032 aged from 15-50 years. The results revealed that only 9.2% of the mothers acquired a good level of knowledge in prevention of injuries from chemicals and detergents, and more than 90% were found to have poor knowledge. The same was found regarding knowledge about preventing electrical accidents caused by power sockets and electrical appliances where only 10.2% of the mothers were found to have a good level of knowledge. The results were not much better regarding accidents caused by fire, only 11.6% of the mothers scored well. With respect to dealing with accidents caused by sharp instruments in the kitchen, only 6.3% of the mothers obtained a score that indicated a good level of knowledge. Older mothers were statistically found to have a better level of knowledge than younger mothers. Higher educated mothers' were statistically associated with a lower level of knowledge in accident prevention. Mothers

  16. Review of Cytogenetic analysis of restoration workers for Fukushima Daiichi nuclear power station accident

    International Nuclear Information System (INIS)

    Suto, Yumiko

    2016-01-01

    Japan faced with the nuclear accident of the Fukushima Daiichi Nuclear Power Station (NPS) caused by the combined disaster of the Great East Japan Earthquake and the subsequent tsunamis on 11 March 2011. National Institute of Radiological Sciences received all nuclear workers who were engaged in emergency response tasks at the NPS and suspected of being overexposed to acute radiation. Biological dosimetry by dicentric chromosome assay was helpful for medical triage and management of the workers. When an unplanned radiation exposure occurs, biological dosimetry based on cytogenetic assays has been used to estimate the absorbed dose in the exposed individual to get useful information for the medical management of radiological casualties with suspected acute radiation syndrome (ARS). Nowadays, more cytogenetic assays to measure chromosomal aberrations, such as micronuclei in bi-nucleated cells, prematurely condensed chromosomes (PCCs) and inter-chromosomal exchanges detected by fluorescence in situ hybridization (FISH) techniques, are available. However, the dicentric chromosome assay (DCA) using peripheral blood lymphocytes is still considered to be the 'gold standard' of biological dosimetry for the radiation emergency medicine. Experimental protocols of DCA has been standardized and shared among laboratories all over the world. In fact, DCA was useful in previous radiation accidents, e.g. the Chernobyl accident in 1986, the Goiania accident in 1987, the JCO criticality accident in 1999 and the Tokyo electric power company (TEPCO) Fukushima Daiichi Nuclear Power Station (NPS) accident in 2011. The recent development of microscopic image analysis system with automatic metaphase finding and capturing functions was helpful for rapid detection of dicentric chromosomes to perform DCA for the Fukushima NPS restoration workers. (author)

  17. REACTOR: an expert system for diagnosis and treatment of nuclear reactor accidents

    International Nuclear Information System (INIS)

    Nelson, W.R.

    1982-01-01

    REACTOR is an expert system under development at EG and G Idaho, Inc., that will assist operators in the diagnosis and treatment of nuclear reactor accidents. This paper covers the background of the nuclear industry and why expert system technology may prove valuable in the reactor control room. Some of the basic features of the REACTOR system are discussed, and future plans for validation and evaluation of REACTOR are presented. The concept of using both event-oriented and function-oriented strategies for accident diagnosis is discussed. The response tree concept for representing expert knowledge is also introduced

  18. Real and mythical consequences of Chernobyl accident

    International Nuclear Information System (INIS)

    Osmachkin, V.S.

    1999-01-01

    This presentation describes the public Unacceptance of Nuclear Power as a consequence of Chernobyl Accident, an accident which was a severest event in the history of the nuclear industry. It was a shock for everybody, who has been involved in nuclear power programs. But nobody could expect that it was also the end romantic page in the nuclear story. The scale of the detriment was a great, and it could be compared with other big technological man-made catastrophes. But immediately after an accident mass media and news agencies started to transmit an information with a great exaggerations of the consequences of the event. In a report on the Seminar T he lessons of the Chernobyl - 1' in 1996 examples of such incorrect information, were cited. Particularly, in the mass media it was declared that consequences of the accident could be compared with a results of the second world war, the number of victims were more than hundred thousand people, more than million of children have the serious health detriments. Such and other cases of the misconstruction have been called as myths. The real consequences of Chernobyl disaster have been summed on the International Conference 'One decade after Chernobyl' - 2, in April 1996. A very important result of the Chernobyl accident was a dissemination of stable unacceptance of the everything connected with 'the atom'. A mystic horror from invisible mortal radiation has been inspired in the masses. And from such public attitude the Nuclear Power Programs in many countries have changed dramatically. A new more pragmatic and more careful atomic era started with a slogan: 'Kernkraftwerk ? Nein, danke'. No doubt, a Chernobyl accident was a serious technical catastrophe in atomic industry. The scale of detriment is connected with a number of involved peoples, not with a number of real victims. In comparison with Bhopal case, earthquakes, crashes of the airplanes, floods, traffic accidents and other risky events of our life - the Chernobyl is

  19. Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This Safety Guide provides guidance on various aspects of emergency planning and preparedness for dealing effectively and safely with transport accidents involving radioactive material, including the assignment of responsibilities. It reflects the requirements specified in Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, and those of Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Framework for planning and preparing for response to accidents in the transport of radioactive material; 3. Responsibilities for planning and preparing for response to accidents in the transport of radioactive material; 4. Planning for response to accidents in the transport of radioactive material; 5. Preparing for response to accidents in the transport of radioactive material; Appendix I: Features of the transport regulations influencing emergency response to transport accidents; Appendix II: Preliminary emergency response reference matrix; Appendix III: Guide to suitable instrumentation; Appendix IV: Overview of emergency management for a transport accident involving radioactive material; Appendix V: Examples of response to transport accidents; Appendix VI: Example equipment kit for a radiation protection team; Annex I: Example of guidance on emergency response to carriers; Annex II: Emergency response guide.

  20. Environmental Impact Assessment following a Nuclear Accident to a Candu NPP

    International Nuclear Information System (INIS)

    Margeanu, C.A.; Margeanu, S.; Olteanu, Gh.

    2009-01-01

    The paper presents calculations of nuclear accident consequences to public and environment, for a Candu NPP using advanced fuel in two hypothetical accident scenarios: (1) large LOCA followed by partial core melting with early containment failure; (2) late core disassembly and containment bypass through ECCS. During both accidents a release occurs, radioactive contaminants being dispersed into atmosphere. As reference, estimations for Candu standard UO 2 fuel were used. The radioactive core inventory was obtained by using ORIGEN-S computer code included in ORNL,SCALE 5 programs package. Radiological consequences assessment to public and environment was performed by means of PC COSYMA computer code