Applications of probabilistic accident consequence evaluation in Cuba

International Nuclear Information System (INIS)

Rodriguez, J.M.

1996-01-01

Are presented the approaches and results of the application of Accident Consequence Evaluation methodologies in on emergency in the Juragua Nuclear Power Plant site and a population evaluation of a planned NPP site in the east of the country Findings on population sector weighing and assessment of effectiveness of primary countermeasures in the event of sever accidents (SST1 and PWR4 source terms) in Juragua NPP site are discussed Results on comparative risk-based evaluation of the population predicted evolution (in 3 temporal horizons: base year, 2005 year and 2050 year) for the planned site are described. Evaluation also included sector risk weighing, risk importance of small towns in the nearby of the effects on risk of population freezing and relocation of these villages

KAPP-3 and 4 containment pressure following postulated severe accident along with SAMG implementation

International Nuclear Information System (INIS)

Sharma, Sanjeev Kr.; Bhartia, D.K.; Mohan, Nalini; Malhotra, P.K.; Ghadge, S.G.; Chandra, Umesh

2011-01-01

Containment is an ultimate safety barrier which is designed to enclose whole reactor systems and to prevent the spread of active air-borne fission products. Studies are done to access its performance following severe accident i.e. Loss of Coolant Accident (LOCA) along with failure of Emergency Core Cooling System (ECCS), moderator and calandria vault water cooling system. The accident progression begins with the double ended break in reactor outlet/inlet header with simultaneous failure of ECCS followed by failure of moderator and calandria vault water cooling system. Initially decay heat and metal water reaction energy are assumed to be added to moderator water resulting in boiling of moderator and re-pressurization of containment due to steam addition. Subsequent to moderator boiling, decay heat and metal water reaction energy are assumed to be added to calandria vault water resulting in boiling and re-pressurization of containment due to steam addition. After moderator and calandria vault water have completely boiled off, rapid hydrogen generation would take place due to oxidation of pressure tubes and calandria tubes. In such accident scenario, the core is severely damaged. It will also lead to release of a large quantity of radio nuclides to containment atmosphere. To arrest the progression of accident, which can result in Severe Core damage and large amount of hydrogen production, which could leads to containment failure due to hydrogen deflagration or detonation, application of Severe Accident Management Guidelines (SAMG) has been studied. SAMG involve addition of water to calandria and calandria vault. It would result the boiling of the added water and consequent pressurization of containment. This paper presents the analysis for pressure-temperature of KAPP-3 and 4 containment following the postulated accident along with the application of Severe Accident Management Guidelines (SAMG). SAMG initiated action helps in arresting the progression of core

Investigation into the causes of accidents on scraper systems in the gold and platinum mining sectors

CSIR Research Space (South Africa)

Moseme, R

2003-11-01

Full Text Available and cleaning operations of the scraper winch systems that require identification. This research report identifies the risk and hazards associated with scraper winch systems that may lead to potential accidents in the gold and platinum sector. The research also...

Normal accidents

International Nuclear Information System (INIS)

Perrow, C.

1989-01-01

The author has chosen numerous concrete examples to illustrate the hazardousness inherent in high-risk technologies. Starting with the TMI reactor accident in 1979, he shows that it is not only the nuclear energy sector that bears the risk of 'normal accidents', but also quite a number of other technologies and industrial sectors, or research fields. The author refers to the petrochemical industry, shipping, air traffic, large dams, mining activities, and genetic engineering, showing that due to the complexity of the systems and their manifold, rapidly interacting processes, accidents happen that cannot be thoroughly calculated, and hence are unavoidable. (orig./HP) [de

THE INTERDEPENDENCE BETWEEN THE FINANCIAL SECTOR AND BUSINESS SECTOR IN ASEAN 4 COUNTRIES

Directory of Open Access Journals (Sweden)

Aulia Keiko Hubbansyah

2018-01-01

Full Text Available In this study, we analyze the dynamic interactions between the financial sectors and the business sectors in the ASEAN-4 countries (Indonesia, Malaysia, Thailand and Singapore. To do that, we apply the newly generalized version of the Vector Autoregressive Framework (VAR spillover index approach proposed by Diebold and Yilmaz (2012 as our method of analysis. Based on quarterly data of each variable over the period from the first quarter of 1984 to the fourth quarter of 2015 for the ASEAN-4 countries, this study finds that: 1 Spillovers between the variables move in a diverse manner over the period of analysis for each country, 2 The variable that acts as the dominant crisis transmitter in each country is different for each country, 3 The interdependence between the variables became stronger, both within and across the countries, during the crisis period. In particular, the business sectors played a leading role during the onset of the crisis, while the financial sectors took their places as the dominant source of spillovers as the crisis deepened. 4 Credit growth in Thailand was found to be the dominant transmitter of shocks to the ASEAN-3 countries. Overall, these results suggest that the strength and movement of the spillovers between the financial and business sectors changed from time to time along with the changes that happened in the economies.

Accident risks in the energy sector

International Nuclear Information System (INIS)

Burgherr, P.

2005-01-01

This article discusses the accident rate of natural gas installations, which are quoted by the author to be lowest of all fossil fuels. The statistics on accidents and their consequences are looked at for the whole natural gas supply chain. The results of a study commissioned by the Swiss Gas and Water Professionals Association (SVGW) are presented and discussed. Statistics for the European Union and Eastern Europe are looked at and analysed. The study's methodological basis is described and the criteria used for the definition of an accident considered to be 'serious' are listed. The results of comparisons made of various energy chains are presented and discussed. Graphics are presented of frequency of occurrence and seriousness of damage for various forms of energy as well as for maximum possible consequences of accidents. Specific analyses for the natural gas chain are presented

Safe commuting factors from existing guidelines in Malaysia: a review for the construction sector

Science.gov (United States)

Sukor, E. S. A.; Suratkon, A.; Mohammad, H.; Yaman, S. K.

2018-04-01

The construction industry is a very active and dynamic industry, which proceeding as one of the significant industry that contributing to the country’s economy. Unfortunately, the construction industry has also earned the reputation of being the riskiest industry because of the higher rates of accidents and fatalities. Nevertheless, overwhelming focus by many on the accident in the workplace has shaded the alarming issue of the construction-related commuting accident. As reported by the Malaysia’s Social Security Organisation (SOCSO) in 2016, the number of commuting accidents and the compensations paid is increasing each year, and it is including the construction sector. Aware of the importance of safe commuting, several Malaysian agencies have developed their guidelines specifically for the improvement of such issue. Regrettably, the number of guidelines published does not exemplify the improvement of such issue when the number of commuting accidents is on the rise, especially for the construction sector. Therefore, this preliminary research was conducted to identify the safe commuting factors from the existing guidelines through manual document analysis. The finding shows that there are four (4) major categories namely; (1) driver/human factor, (2) vehicle factor, (3) environment factor, and (4) others. Hence, the research posits for subsequent exploration to ensure strategic implementation of those factors that will benefit the Malaysia’s construction sector.

Safety Culture and Issue in the Malaysian Manufacturing Sector

Directory of Open Access Journals (Sweden)

Ali Danish

2017-01-01

Full Text Available . This paper highlights the Safety culture and issue in the Malaysian Manufacturing Sector and emphasis the high occupational accidents due to lack of safety culture and non-compliance of the requirements of Occupational Safety and Health Act 1994. The aim of this study is to review the occupational accidents occurrence in the Malaysia workplace since 2012-2016. Malaysia aimed to reduce the occupational accidents, the results show by DOSH increase that Occupational Noise Induced Hearing Loss 83.7%, occupational musculoskeletal diseases, 4.4% and occupational lung diseases 2.3%. But the as per the record from DOSH that in last 5-Years, the increment in the fatal accidents by Average 26%, Permanent Disability by Average 71% and Non-Permanent Disability by 64 % are investigated only in Manufacturing Industries. The government must show their high interest on such a vulnerable employees to accomplish the above aim. This step will be helpful for planning to reduce the accidents in workplaces and it will also detect the prevention for the future accidents.

[Work accidents and automatic circuit reclosers in the electricity sector: beyond the immediate causes].

Science.gov (United States)

Silva, Alessandro Jose Nunes da; Almeida, Ildeberto Muniz de; Vilela, Rodolfo Andrade de Gouveia; Mendes, Renata Wey Berti; Hurtado, Sandra Lorena Beltran

2018-05-10

The Brazilian electricity sector has recorded high work-related mortality rates that have been associated with outsourcing, used to cut costs. In order to decrease the power outage time for consumers, the industry adopted the automatic circuit recloser as the technical solution. The device has hazardous implications for maintenance workers. The aim of this study was to analyze the origins and consequences of work accidents in power systems with automatic circuit recloser, using the Accident Analysis and Prevention (AAP) model. The AAP model was used to investigate two work accidents, aimed to explore the events' organizational origins. Case 1 - when changing a deenergized secondary line, a worker received a shock from the energized primary cable (13.8kV). The system reclosed three times, causing severe injury to the worker (amputation of a lower limb). Case 2 - a fatal work accident occurred during installation of a new crosshead on a partially insulated energized line. The tip of a metal cross arm section strap touched the energized secondary line and electrocuted the maintenance operator. The circuit breaker component of the automatic circuit recloser failed. The analyses revealed how business management logic can participate in the root causes of work accidents through failures in maintenance management, outsourced workforce management, and especially safety management in systems with reclosers. Decisions to adopt automation to guarantee power distribution should not overlook the risks to workers in overhead power lines or fail to acknowledge the importance of ensuring safe conditions.

Self-reported occupational accidents among Brazil's adult population based on data from the 2013 National Health Survey.

Science.gov (United States)

Malta, Deborah Carvalho; Stopa, Sheila Rizzato; Silva, Marta Maria Alves da; Szwarcwald, Célia Landmann; Franco, Marco da Silveira; Santos, Flavia Vinhaes; Machado, Elaine Leandro; Gómez, Carlos Minayo

2017-01-01

to provide an overview of occupational accidents among Brazil's adult population. descriptive study using data from the 2013 National Health Survey. A total of 4.9 million workers mentioned having suffered some kind of work-related accident, which is equivalent to 3.4% (CI95% 4.6-5.6) of Brazil's adult population. Prevalence rates were higher among men, young adults aged between 18 and 39 years, and black people and in the North Region of the country. Prevalence was highest in the State of Para and lowest in the State of Rio de Janeiro State. Around one third of all accidents were commuting accidents, 50.4% (CI95% 45.3-55.5) of people who had suffered an occupational accident were prevented from carrying out some kind of routine activity due to the accident, 8.8% (CI95% 6.4-11.2) were hospitalized and 19% (CI95% 15.3-22.7) had sequelae resulting from occupational accidents. the data provided by the National Health Survey comprises an unprecedented and invaluable source of information on these issues in Brazil. The results of the survey confirm that occupational accidents are underreported, since official figures do not cover individuals working in the informal sector.

Indonesian Sea Accident Analysis (Case Study From 2003 – 2013)

Science.gov (United States)

Arya Dewanto, Y.; Faturachman, D.

2018-03-01

There are so many accidents in sea transportation in Indonesia. Most of the accidents happen because of low concern aspects of the safety and security of the crew. In sailing, a man as transport users to interact with the ship and the surrounding environment (including other ships, cruise lines, ports, and the situation of local conditions). These interactions are sometimes very complex and related to various aspects of. Aware of the multiplicity of aspects related to the third of these factors, seeking the safety of cruise through a reduction in the number of accidents and the risk of death and serious injuries due to accidents and goods transported is certainly not enough attempted through mono-sector approach, but rather takes a multi-sector approach to the efforts. In this paper, we described the Indonesian Sea Transportation accident analysis for eleven years divided into four items: total of ship accident type, ship accident factor, total of casualties, region of ship accidents. All data founded from Marine Court (Mahkamah Pelayaran). From that 4 items we can find Indonesia Sea Accident Analysis from 2003-2013.

Corporate Cost of Occupational Accidents

DEFF Research Database (Denmark)

Rikhardsson, Pall M.; Impgaard, M.

2004-01-01

method could be used in all of the companies without revisions. The evaluation of accident cost showed that 2/3 of the costs of occupational accidents are visible in the Danish corporate accounting systems reviewed while 1/3 is hidden from management view. The highest cost of occupational accidents......The systematic accident cost analysis (SACA) project was carried out during 2001 by The Aarhus School of Business and PricewaterhouseCoopers Denmark with financial support from The Danish National Working Environment Authority. Its focused on developing and testing a method for evaluating...... occupational costs of companies for use by occupational health and safety professionals. The method was tested in nine Danish companies within three different industry sectors and the costs of 27 selected occupational accidents in these companies were calculated. One of the main conclusions is that the SACA...

46 CFR 326.4 - Reports of accidents and occurrences.

Science.gov (United States)

2010-10-01

... 46 Shipping 8 2010-10-01 2010-10-01 false Reports of accidents and occurrences. 326.4 Section 326... MARINE PROTECTION AND INDEMNITY INSURANCE UNDER AGREEMENTS WITH AGENTS § 326.4 Reports of accidents and occurrences. The Agent shall report every accident or occurrence of a P&I nature promptly to both the Director...

Occupational safety of different industrial sectors in Khartoum State, Sudan. Part 1: Safety performance evaluation.

Science.gov (United States)

Zaki, Gehan R; El-Marakby, Fadia A; H Deign El-Nor, Yasser; Nofal, Faten H; Zakaria, Adel M

2012-12-01

Safety performance evaluation enables decision makers improve safety acts. In Sudan, accident records, statistics, and safety performance were not evaluated before maintenance of accident records became mandatory in 2005. This study aimed at evaluating and comparing safety performance by accident records among different cities and industrial sectors in Khartoum state, Sudan, during the period from 2005 to 2007. This was a retrospective study, the sample in which represented all industrial enterprises in Khartoum state employing 50 workers or more. All industrial accident records of the Ministry of Manpower and Health and those of different enterprises during the period from 2005 to 2007 were reviewed. The safety performance indicators used within this study were the frequency-severity index (FSI) and fatal and disabling accident frequency rates (DAFR). In Khartoum city, the FSI [0.10 (0.17)] was lower than that in Bahari [0.11 (0.21)] and Omdurman [0.84 (0.34)]. It was the maximum in the chemical sector [0.33 (0.64)] and minimum in the metallurgic sector [0.09 (0.19)]. The highest DAFR was observed in Omdurman [5.6 (3.5)] and in the chemical sector [2.5 (4.0)]. The fatal accident frequency rate in the mechanical and electrical engineering industry was the highest [0.0 (0.69)]. Male workers who were older, divorced, and had lower levels of education had the lowest safety performance indicators. The safety performance of the industrial enterprises in Khartoum city was the best. The safety performance in the chemical sector was the worst with regard to FSI and DAFR. The age, sex, and educational level of injured workers greatly affect safety performance.

Profiling technological failure and disaster in the energy sector: A comparative analysis of historical energy accidents

International Nuclear Information System (INIS)

Sovacool, Benjamin K.; Kryman, Matthew; Laine, Emily

2015-01-01

This study assesses the risk of energy accidents using an original historical dataset over the period 1874-2014, and it evaluates that risk across 11 energy systems: biofuels, biomass, coal, geothermal, hydroelectricity, hydrogen, natural gas, nuclear power, oil, solar energy, and wind energy. Our study shows how these energy systems collectively involved almost 1,100 accidents resulting in more than 210,000 human fatalities and almost $350 billion in property damages. Across the entire sample, the mean amount of property damage was $319 million and 196 fatalities per accident, though when reflected as a median the numbers substantially improve to $3 million in damages per accident and 0 fatalities. We found that wind energy is the most frequent to incur an accident within our sample, accounting for almost one third of accidents. Accidents at hydroelectric dams were the most fatal, accounting for 85 percent of fatalities. Nuclear power accidents are by far the most expensive, accounting for 70 percent of damages. We then utilize this data to test six hypotheses, drawn from the energy studies literature, related to energy systems, energy policy and regulation, and technological learning. - Highlights: • 1085 energy accidents have resulted in 211,529 human fatalities and $344.4 billion in property damages. • Wind energy is the most frequent to incur an accident. • Hydroelectric dam accidents tend to be the most fatal. • Nuclear energy accidents tend to be the most expensive. • Coal, natural gas, and oil are the least likely to incur an accident, when normalized to energy output.

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)

Investigation of Qom Rural Area Water Network Accident in 2010 and Minimization Approaches of Accident Frequencies

Directory of Open Access Journals (Sweden)

Hossein Jafari Mansoorian

2016-02-01

Full Text Available Background & Aims of the Study : Accidents in water networks can lead to increase the uncounted water, costs of repair, maintenance, restoration and enter water contaminants to water network. The aim of this study is to survey the accidents of Qom rural water network and choose the right approaches to reduce the number of accidents. Materials & Methods: In this cross-sectional study, four sector of Qom province (Markazi, Dastjerd, Kahak and Qahan, were assessed over a period of 8 months (July – January 2010. This study was conducted through questionnaire of Ministry of Energy. Results: The total number of accidents was 763. The highest number of accidents in the four sectors was related to Markazi sector with 228 accidents. According to the time of the accident, the highest and lowest number of accident was related to September (19.7% and November (6.8%, respectively. According to the location of the accident on network, the highest and lowest number of accident was related to distribution network (64% and connections (17.5% and transmission pipe (18.34%, respectively. According to the type of the accident, the highest and lowest number of accident was related to breaking (47.8% and gasket failure (1.2%, respectively. Considering with the pipes’ material, the highest and lowest number of accident was related to polyethylene pipes (93% and steel and cast iron pipes (0.5%, 0.5%, respectively. Conclusions: Due to the high break rate of Polyethylene pipes, it is recommended to be placed in priority of leak detection and rehabilitation.   .

Aspects Concerning The Rules And The Investigation Of Traffic Accidents As Work Accidents

Science.gov (United States)

Tarnu, Lucian Ioan

2015-07-01

When Romania joined the European Union, it was imposed that the Romanian legislation in the field of the security and health at work be in line with the European one. The concept of health as it is defined by the International Body of Health, refers to a good physical, mental and social condition. The improvement of the activity of preventing the traffic accidents as work accidents must have as basis the correct and accurate evaluation of risks of getting injured. The goal of the activity of prevention and protection is to ensure the best working conditions, the prevention of accidents and occupational diseases and the adjustment to the scientific and technological progress. In the road transport sector, as in any other sector, it is very important to pay attention to working conditions to ensure a workforce motivated and well qualified. Some features make it a more difficult sector risk management than other sectors. However, if one takes into account how it works in practice this sector and the characteristics of drivers and how they work routinely, risks, dangers and threats can be managed efficiently and with great success.

[Current situation of accidents in the world].

Science.gov (United States)

Aguilar-Zinser, José Valente

2010-01-01

According to the World Health Organization (WHO), the number of traffic accidents is of concern. About 1.2 million people die every year on the roadways and about 20 to 50 million suffer from non-lethal trauma. Countries with low or medium incomes have higher rates of lethality by traffic accidents (21.5 and 19.5 per 100,000 habitants, respectively) than countries with higher incomes (10.3 per 100,000). It is estimated that the cost of traffic accidents in countries that are members of the Organization for Economic Cooperation and Development (OECD), escalate to rates that are between 2-5% of the gross domestic product (GDP). According to data from the health sector in Mexico, these rates are equivalent to 1.3 of GDR The WHO foresees that traffic accident traumas will rise to be the third cause of mortality in 2030. Because of the high complexity of the transport sector, it is necessary that the Transport and Communication Ministry works in a multidisciplinary and intersectorial fashion to ensure that the land transportation systems operate effectively in accordance with national economic development and the quality of life of the Mexican people.

49 CFR 840.3 - Notification of railroad accidents.

Science.gov (United States)

2010-10-01

... 49 Transportation 7 2010-10-01 2010-10-01 false Notification of railroad accidents. 840.3 Section... SAFETY BOARD RULES PERTAINING TO NOTIFICATION OF RAILROAD ACCIDENTS § 840.3 Notification of railroad accidents. The operator of a railroad shall notify the Board by telephoning the National Response Center at...

Questions about the reactor accident with Chernobyl-4

International Nuclear Information System (INIS)

Heijboer, R.J.

1986-01-01

The author presents an inventory of existing information about the Chernobyl-4 accident. Several possible scenarios are described and a comparison is drawn with the Three Mile Island-2 accident. The author concludes that the event is connected to an inherent instability of the RBMK-1000 reactor type. (G.J.P.)

Effects of B4C control rod degradation under severe accident

Energy Technology Data Exchange (ETDEWEB)

Seo, Si-Won; Park, Sang-Gil; Han, Sang-Ku [Atomic Creative Technology Co., Daejeon (Korea, Republic of)

2016-10-15

Boron carbide (B4C) is widely used as absorber material in western boiling water reactor (BWR), some PWR, EPR and Russian RBMK and VVERs. B4C oxidation is one of the important phenomena of in-vessel. In the present paper, the main results and knowledge gained regarding the B4C control rod degradation from above mentioned experiments are reviewed and arranged to inform its significance on the severe accident consequences. In this paper, the role of B4C control rod oxidation and the subsequent degradation on the severe accident consequences is reviewed with available literature and report of previous experimental program regarding the B4C oxidation. From this review, it seems that the contribution of this B4C oxidation on the accident progression to the further severe accident situation is not negligible. For the future work, the extensive experimental data interpretation will be performed to assess quantitatively the effect of B4C oxidation and degradation on the various postulated severe accident conditions.

Accident Risks In The Energy Sector: Comparative Evaluations

International Nuclear Information System (INIS)

Hirschberg, S.; Burgherr, P.

2005-01-01

Severe accidents are considered one of the most controversial issues in current comparative studies of the environmental and health impact of energy systems. The present work focuses on severe accident scenarios relating to fossil energy chains (coal, oil and gas), nuclear power and hydro-power. The scope of the study is not limited to the power production (conversion) step of these energy chains, but, wherever applicable, also includes full energy chains. With the exception of the nuclear chain, the focus of the present work is on the evaluation of the historical experience of accidents. The basis for this evaluation is the comprehensive database ENSAD (Energy-Related Severe Accident Database), which has been established at PSI. For hypothetical nuclear accidents, a probabilistic technique has also been employed. The broader picture, derived from examination of full energy chains, leads, on a world-wide basis, to the conclusion that immediate fatality rates are much higher for the fossil chains than expected if only power plants are considered. Generally, immediate fatality rates are significantly higher for non-OECD countries than for OECD countries, and, in the case of hydro and nuclear, the difference is rather dramatic. In addition to aggregated values, frequency-consequence curves are also provided, since they not only reflect implicitly a ranking based on aggregated values, but also include such information as the observed, or predicted, chain-specific maximum extent of damages. Finally, damage and external costs of severe accidents for the different energy chains have been estimated, based on the unit cost values for the various consequence types. (author)

Development of instrumentation systems for severe accidents. 4. New accident tolerant in-containment pressure transducer for containment pressure monitoring system

International Nuclear Information System (INIS)

Oba, Masato; Teruya, Kuniyuki; Yoshitsugu, Makoto; Ikeuchi, Takeshi

2015-01-01

The accident at Tokyo Electric Power Company's Fukushima Dai-ichi Nuclear Power Plant (TF-1 accident) caused severe situations and resulted in a difficulty in measuring important parameters for monitoring plant conditions. Therefore, we have studied the TF-1 accident to select the important parameters that should be monitored at the severe accident and are developing the Severe Accident Instrumentations and Monitoring Systems that could measure the parameters in severe accident conditions. Mitsubishi Heavy Industries, LTD (MHI) developed a new accident tolerant containment pressure monitoring system and demonstrated that the monitoring system could endure extremely harsh environmental conditions that envelop severe accident environmental conditions inside a containment such as maximum operating temperature of up to 300degC and total integrated dose (TID) of 1 MGy gamma. The new containment pressure monitoring system comprises of a strain gage type pressure transducer and a mineral insulated (MI) cable with ceramic connectors, which are located in the containment, and a strain measuring amplifier located outside the containment. Less thermal and radiation degradation is achieved because of minimizing use of organic materials for in-containment equipment such as the transducer and connectors. Several tests were performed to demonstrate the performance and capability of the in-containment equipment under severe accident environmental conditions and the major steps in this testing were run in the following test sequences: (1) the baseline functional tests (e.g., repeatability, non-linearity, hysteresis, and so on) under normal conditions, (2) accident radiation testing, (3) seismic testing, and (4) steam/temperature test exposed to simulated severe accident environmental conditions. The test results demonstrate that the new pressure transducer can endure the simulated severe accident conditions. (author)

Analysis of eventual accidents in a water experimental loop, using the Relap 4 computer code

International Nuclear Information System (INIS)

Fernandes Filho, T.L.

1981-01-01

Transients caused by accidents as (1) loss of coolant, (2) failure in the principal pump and (3) power excursions were analysed. In the accident simulation, the Relap 4/Mod 3 computer code was used. The results obtained with the steady state model showed to be consistent with the project-and operation data of the experimental loop. For all the accidents analysed that considered the performance of safety systems, the highest temperature of the heating rods in the testing section did not exceed the permissible temperature. (E.G.) [pt

Comparative Assessment of Severe Accidents in the Chinese Energy Sector

Energy Technology Data Exchange (ETDEWEB)

Hirschberg, S; Burgherr, P; Spiekerman, G; Cazzoli, E; Vitazek, J; Cheng, L

2003-03-01

This report deals with the comparative assessment of accidents risks characteristic for the various electricity supply options. A reasonably complete picture of the wide spectrum of health, environmental and economic effects associated with various energy systems can only be obtained by considering damages due to normal operation as well as due to accidents. The focus of the present work is on severe accidents, as these are considered controversial. By severe accidents we understand potential or actual accidents that represent a significant risk to people, property and the environment and may lead to large consequences. (author)

Finite size giant magnons in the SU(2) x SU(2) sector of AdS4 x CP3

International Nuclear Information System (INIS)

Lukowski, Tomasz; Sax, Olof Ohlsson

2008-01-01

We use the algebraic curve and Luescher's μ-term to calculate the leading order finite size corrections to the dispersion relation of giant magnons in the SU(2) x SU(2) sector of AdS 4 x CP 3 . We consider a single magnon as well as one magnon in each SU(2). In addition the algebraic curve computation is generalized to give the leading order correction for an arbitrary multi-magnon state in the SU(2) x SU(2) sector.

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

International Nuclear Information System (INIS)

2015-08-01

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

Barriers to learning from incidents and accidents

NARCIS (Netherlands)

Dechy, N.; Dien, Y.; Drupsteen, L.; Felicio, A.; Cunha, C.; Roed-Larsen, S.; Marsden, E.; Tulonen, T.; Stoop, J.; Strucic, M.; Vetere Arellano, A.L.; Vorm, J.K.J. van der; Benner, L.

2015-01-01

This document provides an overview of knowledge concerning barriers to learning from incidents and accidents. It focuses on learning from accident investigations, public inquiries and operational experience feedback, in industrial sectors that are exposed to major accident hazards. The document

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

International Nuclear Information System (INIS)

2015-08-01

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

Quantification of severe accident source terms of a Westinghouse 3-loop plant

International Nuclear Information System (INIS)

Lee Min; Ko, Y.-C.

2008-01-01

Integrated severe accident analysis codes are used to quantify the source terms of the representative sequences identified in PSA study. The characteristics of these source terms depend on the detail design of the plant and the accident scenario. A historical perspective of radioactive source term is provided. The grouping of radionuclides in different source terms or source term quantification tools based on TID-14844, NUREG-1465, and WASH-1400 is compared. The radionuclides release phenomena and models adopted in the integrated severe accident analysis codes of STCP and MAAP4 are described. In the present study, the severe accident source terms for risk quantification of Maanshan Nuclear Power Plant of Taiwan Power Company are quantified using MAAP 4.0.4 code. A methodology is developed to quantify the source terms of each source term category (STC) identified in the Level II PSA analysis of the plant. The characteristics of source terms obtained are compared with other source terms. The plant analyzed employs a Westinghouse designed 3-loop pressurized water reactor (PWR) with large dry containment

Comparative assessment of severe accident risks in the energy sector

International Nuclear Information System (INIS)

Hirschberg, S.; Spiekerman, G.; Dones, R.

1997-01-01

This paper addresses one of the major limitations of the current comparative studies of environmental and health impacts of energy systems, i.e. the treatment of severe accidents. The work covers technical aspects of severe accidents and thus primarily reflects an engineering perspective on the energy-related risk issues. The assessments concern full energy chains associated with fossil sources (coal, oil and gas), nuclear power and hydro power. A comprehensive severe accidents database has been established. Thanks to the variety of information sources used, it exhibits in comparison with other corresponding databases a far more extensive coverage of the energy-related accidents. For hypothetical nuclear accidents the probabilistic approach has been employed and extended to cover the economic consequences of power reactor accidents. Results of comparisons between the various energy chains are shown and discussed along with a number of current issues in comparative assessment of severe accidents. As opposed to the previous studies, the aim of the present work has been, to cover whenever possible, a relatively broad spectrum of damage categories of interest. (author) 5 figs., 1 tab., 18 refs

Medical aspects of the nuclear accident in the Chernobylsk-4 reactor

International Nuclear Information System (INIS)

Arndt, D.; Schmidt, W.

1989-01-01

The Kiev conference on the Chernobylsk reactor accident was concerned with the following items: (1) Medical consequences and organization of medical assistance as well as aftercare of radiation-exposed persons. (2) Analysis of the postirradiation situation and judgement of the consequences of the accident as to the USSR population. (3) Peculiarities of external and internal radiation exposure of the population in the area controlled. (4) Organization and efficiency of the epidemiological register of the USSR. (5) Organization and judgement of educational work and public relations concerning the sanitary conditions in populations exposed to an increased contamination

Analysis of Fukushima Daiichi Nuclear Power Station severe accident using MAAP4.05

International Nuclear Information System (INIS)

Yoo, Jae S.; Suh, Kune Y.; Kim, Dong M.

2011-01-01

Rather extensive reactor core meltdown and partial melt-through that took place at the Fukushima Daiichi nuclear power plants (NPPs) on March 11, 2011 had been caused by a massive earthquake followed by tsunami rarely seen in history. The happening had turned into an unprecedented serious accident since the Chernobyl Unit 4 in 1986 that extended over multiple reactors simultaneously. A previous documentary survey, NUREG-1150 report provides significant insights into how a severe accident might develop at a boiling water reactor (BWR) and the range of consequences. NUREG-1150 did identify the importance of loss of power accidents for a BWR. This paper describes recent analyses of the Fukushima Daiichi NPPs severe accident. Calculations were performed with the MAAP4.05 code by modifying the parameter file for the Peach Bottom Unit 2, a BWR 4 type in the Mark-I containment. Generally this is the same type of reactor as Fukushima Daiichi Units 2 and 3. This resulted in good understanding of the response of this type of early BWRs to prolonged loss of diesel generators and batteries. There is clearly vulnerability with this early type of BWRs which would be less onerous than later existing plant and new build designs. This analysis, however, was based on rather limited amount of information obtained at the time of preparing this report and adopted various estimates and assumptions for conditions necessary to run the analysis. Hence there persists considerable uncertainty in the results. MAAP4.05 was run pursuant to the observed data and chronology of Fukushima Daiichi Units 1 through 3 reported by the Tokyo Electric Power Company (TEPCO) as well as the Japanese Government. Severe accident scenarios have not only gone far beyond the design basis, but also exceeded the extent of multiple breakdowns assumed in the preparation for such accident management measures as the malfunction or loss of all the emergency core cooling system (ECCS) combined with the extended loss of

Occupational accidents in the Netherlands: incidence, mental harm, and their relationship with psychosocial factors at work.

Science.gov (United States)

van der Klauw, Marloes; Hengel, Karen Oude; Roozeboom, Maartje Bakhuys; Koppes, Lando L; Venema, Anita

2016-01-01

This study investigated the incidence of mental harm due to occupational accidents and the relation between psychosocial factors at work and the occurrence of occupational accidents in the Netherlands for the construction industry and health and welfare sector. Analyses revealed that occupational accidents in the construction industry more often involved physical harm, whereas accidents in the health and welfare sector relatively more often resulted in mental harm, in comparison to other sectors. Results showed that psychosocial factors were associated with occupational accidents in both sectors. For the construction industry, high time pressure and exposure to violence and harassment by colleagues or supervisors were associated with occupational accidents. For the health and welfare sector, low autonomy and exposure to violence and harassment by colleagues or supervisors or by people outside the organization were associated with occupational accidents. The present paper stresses the importance of also taking psychological consequences and psychosocial factors at work into account in assessing the occurrence of occupational accidents.

The Swedish methodology of intervening in agricultural sector in case of nuclear accident

International Nuclear Information System (INIS)

Preuthun, Jan

1997-01-01

In Sweden the provincial administrative Councils are in charge with the public administration of the region as well as with the assistance and relief emergency operations in case of nuclear accident. Also, decontamination operations following accidental release of radioactive matter are in care of these Councils. Central services placed under the direct authority of the government have specific tasks in case of nuclear accident. These are: SKI, National Service for Nuclear Energy Inspection; SMHI, Institute of Meteorology and Hydrology; SSI, National Institute for Radiation Protection; SLV, National Agency for Alimentation; SJV, Office of Agriculture and SRV, Centre of Assistance Services. The Central services have also the task to keep the Government informed with any development in the field of nuclear emergency. SRV pursuits training and drilling emergency programmes for intervention personnel. In case of crisis the role of coordination is assumed by National Institute of Radiation Protection while under direction of SJV a 'Crisis Cell' and an Information Center are immediately formed to cope with the rapid evolution of events and consequences. The objectives and the preparatory measures which are implemented by SJV. among which a manual of emergency intervention are listed and described. The last sections of the paper presents the provisions in case of radioactive release and the measures aiming at limitation of damage in the sectors of animal and vegetal food production

Explaining and predicting workplace accidents using data-mining techniques

International Nuclear Information System (INIS)

Rivas, T.; Paz, M.; Martin, J.E.; Matias, J.M.; Garcia, J.F.; Taboada, J.

2011-01-01

Current research into workplace risk is mainly conducted using conventional descriptive statistics, which, however, fail to properly identify cause-effect relationships and are unable to construct models that could predict accidents. The authors of the present study modelled incidents and accidents in two companies in the mining and construction sectors in order to identify the most important causes of accidents and develop predictive models. Data-mining techniques (decision rules, Bayesian networks, support vector machines and classification trees) were used to model accident and incident data compiled from the mining and construction sectors and obtained in interviews conducted soon after an incident/accident occurred. The results were compared with those for a classical statistical techniques (logistic regression), revealing the superiority of decision rules, classification trees and Bayesian networks in predicting and identifying the factors underlying accidents/incidents.

Explaining and predicting workplace accidents using data-mining techniques

Energy Technology Data Exchange (ETDEWEB)

Rivas, T., E-mail: trivas@uvigo.e [Dpto. Ingenieria de los Recursos Naturales y Medio Ambiente, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain); Paz, M., E-mail: mpaz.minas@gmail.co [Dpto. Ingenieria de los Recursos Naturales y Medio Ambiente, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain); Martin, J.E., E-mail: jmartin@cippinternacional.co [CIPP International, S.L. Parque Tecnologico de Asturias, Parcela 43, Oficina 11, 33428 Llanera (Spain); Matias, J.M., E-mail: jmmatias@uvigo.e [Dpto. Estadistica e Investigacion Operativa, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain); Garcia, J.F., E-mail: jgarcia@cippinternacional.co [CIPP International, S.L. Parque Tecnologico de Asturias, Parcela 43, Oficina 11, 33428 Llanera (Spain); Taboada, J., E-mail: jtaboada@uvigo.e [Dpto. Ingenieria de los Recursos Naturales y Medio Ambiente, E.T.S.I. Minas, University of Vigo, Campus Lagoas, 36310 Vigo (Spain)

2011-07-15

Current research into workplace risk is mainly conducted using conventional descriptive statistics, which, however, fail to properly identify cause-effect relationships and are unable to construct models that could predict accidents. The authors of the present study modelled incidents and accidents in two companies in the mining and construction sectors in order to identify the most important causes of accidents and develop predictive models. Data-mining techniques (decision rules, Bayesian networks, support vector machines and classification trees) were used to model accident and incident data compiled from the mining and construction sectors and obtained in interviews conducted soon after an incident/accident occurred. The results were compared with those for a classical statistical techniques (logistic regression), revealing the superiority of decision rules, classification trees and Bayesian networks in predicting and identifying the factors underlying accidents/incidents.

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

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.

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.

[Under registration of occupational accidents in São Paulo, Brazil, 1997].

Science.gov (United States)

Binder, Maria Cecília Pereira; Cordeiro, Ricardo

2003-08-01

To estimate the number of occupational accidents that occurred in a certain municipality during a specific period of time as well as the extent of sub-registration. The study sample was comprised of 4.782 households within the municipality of Botucatu, São Paulo occupied by a total 17,219 inhabitants on the 1st of July, 1997. In each household, an adult inhabitant was interviewed in order to identify the occurrence of occupational accidents in the three months preceding the interview. When such occurrences were identified, the injured workers were interviewed. The Cochran formula was utilized to calculate the confidence interval. Seventy-six individuals confirmed that they had suffered occupational accidents during these three months. In 1997, there were approximately 1,810 occupational accidents in Botucatu, according to our estimates, and the incidence of work related injuries in the population was approximately 4.1% (CI 95% 3.0%-5.3%). Thirty-nine (51.3%, CI 95% 41.1%61.6%) of the above 76 workers were not covered by the Social Security System. Consequently, their injuries were not reported for there was no legally binding obligation to fill out and emit the official registration form - Comunicação de Acidente do Trabalho (CAT) [the work injury report]. Included among the latter are civil servants and informal sector workers, such as self-employed, casual workers and others. Although the remaining 37 workers (48.7%) were covered by the Social Security System and emission of the work injury report was obligatory, 20 of the cases (54.1% CI 95% 39.4%-68.7%) had not been registered. A greater proportion of cases of sub-registration were found among those workers employed in micro, small and medium sized businesses than among those working in large firms. Only 22.4% (CI 13.8%-30.9%) of the occupational accidents reported in this study were registered by the Social Security System. Research findings confirm that analyses based on the number of officially registered

Simulation of a beyond design-basis-accident with RELAP5/MOD3.1

Energy Technology Data Exchange (ETDEWEB)

Banati, J. [Lappeenranta Univ. of Technology, Lappeenranta (Finland)

1995-09-01

This paper summarizes the results of analyses, parametric and sensitivity studies, performed using the RELAP5/MOD3.1 computer code for the 4th IAEA Standard Problem Exercise (SPE-4). The test, conducted on the PMK-2 facility in Budapest, involved simulation of a Small Break Loss Of Coolant Accident (SBLOCA) with a 7.4% break in the cold leg of a VVER-440 type pressurized water reactor. According to the scenario, the unavailability of the high pressure injection system led to a beyond design basis accident. For prevention of core damage, secondary side bleed-and-feed accident management measures were applied. A brief description of the PMK-2 integral type test facility is presented, together with the profile and some key phenomenological aspects of this particular experiment. Emphasis is placed on the ability of the code to predict the main trends observed in the test and thus, an assessment is given for the code capabilities to represent the system transient.

Task Force Report, Safety of Personnel in LHC underground areas following the accident of 19th September 2008

CERN Document Server

Delille, B; Inigo-Golfin, J; Lindell, G; Roy, G; Tavian, L; Thomas, E; Trant, R; Völlinger, C

2009-01-01

In January 2009, the Task Force on Safety of Personnel in the LHC underground areas following the accident in sector 3-4 of 19th September 2008 (Safety Task Force) received from the CERN Director General the mandate to investigate the impact of the accident of 19th September 2008 on the safety of personnel working in the LHC underground areas. This mandate includes the elaboration of preventive and/or corrective measures, if deemed necessary. This report gives the conclusions and recommendations of the Safety Task Force which have been reviewed by an external advisory committee of safety experts.

Application of Latin hypercube sampling to RADTRAN 4 truck accident risk sensitivity analysis

International Nuclear Information System (INIS)

Mills, G.S.; Neuhauser, K.S.; Kanipe, F.L.

1994-01-01

The sensitivity of calculated dose estimates to various RADTRAN 4 inputs is an available output for incident-free analysis because the defining equations are linear and sensitivity to each variable can be calculated in closed mathematical form. However, the necessary linearity is not characteristic of the equations used in calculation of accident dose risk, making a similar tabulation of sensitivity for RADTRAN 4 accident analysis impossible. Therefore, a study of sensitivity of accident risk results to variation of input parameters was performed using representative routes, isotopic inventories, and packagings. It was determined that, of the approximately two dozen RADTRAN 4 input parameters pertinent to accident analysis, only a subset of five or six has significant influence on typical analyses or is subject to random uncertainties. These five or six variables were selected as candidates for Latin Hypercube Sampling applications. To make the effect of input uncertainties on calculated accident risk more explicit, distributions and limits were determined for two variables which had approximately proportional effects on calculated doses: Pasquill Category probability (PSPROB) and link population density (LPOPD). These distributions and limits were used as input parameters to Sandia's Latin Hypercube Sampling code to generate 50 sets of RADTRAN 4 input parameters used together with point estimates of other necessary inputs to calculate 50 observations of estimated accident dose risk.Tabulations of the RADTRAN 4 accident risk input variables and their influence on output plus illustrative examples of the LHS calculations, for truck transport situations that are typical of past experience, will be presented

Some problems connected with the Chernobyl NPP Unit 4 Accident

International Nuclear Information System (INIS)

Bar'yakhtar, V.G.

1994-01-01

The description of the eruption of radionuclides caused by the Chernobyl NPP Unit 4 Accident, including the effective time of the accident, quality and quantity of radio waste, is presented. A particular attention is given to the spotty structure of Chernobyl's contamination. The assumption that the spots distribution may be a consequence of the turbulent processes in the atmosphere is made

Fatal occupational injuries in the construction sector in Kocaeli, Turkey, 1990--2001.

Science.gov (United States)

Colak, Basar; Etiler, Nilay; Bicer, Umit

2004-10-01

In Turkey, the construction sector is responsible for the largest number of work-related fatalities among all industries. This study's objective is to determine the characteristics of the fatalities in the construction sector in Kocaeli Province. The study was carried out retrospectively by investigating the records of occupational deaths between 1990 and 2001 in the Kocaeli District of Turkey. Fatal occupational injuries in the construction sector were investigated in detail by evaluating the records. The analysis was based on data from 153 deaths. The incidence of occupational injuries was found overall to be 4.5% in Kocaeli, while the annual mortality rate was 60.4 in Kocaeli and 79.0 in Turkey per 100,000 workers over the entire time period. On the other hand, the fatality rate of occupational injuries was found to be 12.0 per 1,000 in Turkey and 6.4 per 1,000 in Kocaeli. The evaluation of the type of injuries in construction sector has revealed that in 69 of cases (45.1%) fell down from high altitude, in 22 cases (14.4%) vehicle accident, and in 22 (14.4%) electrocution were the cause of death. The leading causes of death have been found to be blunt-force trauma (37.9%) and head trauma (25.5%). Fourty one percent of those who had occupational accidents have had less than one year work experience. Only in 7.8% of deaths, the cause was determined through an autopsy.

The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response

International Nuclear Information System (INIS)

2015-08-01

This volume describes the key events and response actions from the onset of the accident at the Fukushima Daiichi nuclear power plant (NPP), operated by the Tokyo Electric Power Company (TEPCO), on 11 March 2011. It also describes the national emergency preparedness and response (EPR) system in place in Japan and the international EPR framework prior to the accident. It is divided into five sections. Section 3.1 describes the initial actions taken by Japan in response to the accident, involving: identification of the accident, notification of off-site authorities and activation of the response; mitigatory actions taken on-site; and initial off-site response. Section 3.2 describes the protective measures taken for personnel in response to the natural disaster, protection of emergency workers, medical management of emergency workers and the voluntary involvement of members of the public in the emergency response. Section 3.3 describes the protective actions and other response actions taken by Japan to protect the public. It addresses urgent and early protective actions; the use of a dose projection model, the System for Prediction of Environmental Emergency Dose Information (SPEEDI), as a basis for decisions on protective actions during the accident; environmental monitoring; provision of information to the public and international community; and issues related to international trade and waste management. Section 3.4 describes the transition from the emergency phase to the recovery phase. It also addresses the national analysis of the accident and the emergency response. Section 3.5 describes the response by the IAEA, other international organizations within the Inter- Agency Committee on Radiological and Nuclear Emergencies (IACRNE), the actions of IAEA Member States with regard to protective actions recommended to their nationals in Japan and the provision of international assistance. A summary, observations and lessons conclude each section. There are three

Independent accident investigation: a modern safety tool

International Nuclear Information System (INIS)

Stoop, John A.

2004-01-01

Historically, safety has been subjected to a fragmented approach. In the past, every department has had its own responsibility towards safety, focusing either on working conditions, internal safety, external safety, rescue and emergency, public order or security. They each issued policy documents, which in their time were leading statements for elaboration and regulation. They also addressed safety issues with tools of various nature, often specifically developed within their domain. Due to a series of major accidents and disasters, the focus of attention is shifting from complying with quantitative risk standards towards intervention in primary operational processes, coping with systemic deficiencies and a more integrated assessment of safety in its societal context. In The Netherlands recognition of the importance of independent investigations has led to an expansion of this philosophy from the transport sector to other sectors. The philosophy now covers transport, industry, defense, natural disaster, environment and health and other major occurrences such as explosions, fires, and collapse of buildings or structures. In 2003 a multi-sector covering law will establish an independent safety board in The Netherlands. At a European level, mandatory investigation agencies are recognized as indispensable safety instruments for aviation, railways and the maritime sector, for which EU Directives are in place or being progressed [Transport accident and incident investigation in the European Union, European Transport Safety Council, ISBN 90-76024-10-3, Brussel, 2001]. Due to a series of major events, attention has been drawn to the consequences of disasters, highlighting the involvement of rescue and emergency services. They also have become subjected to investigative efforts, which in return, puts demands on investigation methodology. This paper comments on an evolutionary development in safety thinking and of safety boards, highlighting some consequences for strategic

Managing severe reactor accidents. A review and evaluation of our knowledge on reactor accidents and accident management

International Nuclear Information System (INIS)

Gustavsson, Veine

2002-11-01

The report gives a review of the results from the last years research on severe reactor accidents, and an opinion on the possibilities to refine the present strategies for accident management in Swedish and Finnish BWRs. The following aspect of reactor accidents are the major themes of the study: 1. Early pressure relief from hydrogen production; 2. Recriticality in re-flooded, degraded core; 3. Melt-through; 4. Steam explosion after melt-through; 5. Coolability of the melt after after melt-through; 6. Hydrogen fire in the reactor containment; 7. Leaking containment; 8. Hydrogen fire in the reactor building; 9. Long-time developments after a severe accident; 10. Accidents during shutdown for overhaul; 11. Information need for remedial actions. Possibilities for improving the strategies in each of these areas are discussed. The review shows that our knowledge is sufficient in the areas 1, 2, 4, 6, 8. For the other areas, more research is needed

Simulation of severe accident using March-3 computer code

International Nuclear Information System (INIS)

Fernandes, A.; Nakata, H.

1991-01-01

The severe accident sensitivity analysis utilizing the March-3 approximate modelization options has been performed. The reference results against which the present results have been compared were obtained from the best published results for the most representative accident sequences: TMLU, S sub(2)DC sub(r) and S sub(2)DCF sub(r) for the Zion-1 reactor. The results of the present sensitivity analysis revealed the presence of very crude modelizations, in the March-3 program, to represent the critical phenomenologies involved in the severe accident sequences considered, even though large uncertainties must still be taken into account due primarily to the scarcity of the integral benchmark data. (author)

New system technologies implemented at Kozloduy 3 and 4 (WWER 440-230) for containment leakage and H2 control in severe accident situations - Design, qualification, installation, commissioning

International Nuclear Information System (INIS)

Feuerbach, R.; Eckardt, B.; Kastner, B.

2005-01-01

In order to reduce the residual risk associated with hypothetical severe nuclear accidents, systems and components for filtered containment venting and H 2 reduction were developed. During severe accident scenarios large quantities of hydrogen and radioactive material may be released into the containment atmosphere within a short period of time. In the event of internal over pressurization due to hypothetical severe accident sequences a pressure barrier system has to be created to confine the activity in the containment. Unavoidable releases of activity to the environment have to be minimized to a great extent as possible. Research into the hypothetical event of core melt accidents has continued and new accident mitigation technologies have been developed. Decisions have been taken to implement these new mitigation measures in operating nuclear power plants to mitigate severe accidents consequences. In order to prevent loss of containment integrity as a result of over pressurization, nuclear power plants in the Federal Republic of Germany as well as in most other European countries have been or will be back-fitted with systems for filtered venting of the containment atmosphere and systems for H 2 -control. Similar technologies for containment venting system and H 2 control have been now implemented in the first WWER 440-230 units of Kozloduy 3 and 4. Following OECD recommendations sever accident situations were analyzed and a design of countermeasures have been performed. Main goal of the developed countermeasures was to overcome the WWER 440-230 containment design specifics like, leakage rate behavior, limited available containment volume combined with the feature of high availability of electrical supply at multiple plant sites. Further more the design of counter measures considers the common use for Kozloduy unit 3 and 4. The analysis of postulated severs accident situation - without countermeasures - showed significant increase of H 2 /O 2 concentration in the

Consequences in Guatemala of the Chernobyl accident

International Nuclear Information System (INIS)

Perez Sabino, J.F.; Ayala Jimenez, R.E.

1997-01-01

Because of the long distance between Guatemala and Chernobyl, the country did not undergo direct consequences of radioactive contamination in the short term. However, the accident repercussions were evident in the medium and long-term, mainly in two sectors, the economic-political and the environmental sectors

Validation of the metal fuel version of the SAS4A accident analysis code

International Nuclear Information System (INIS)

Tentner, A.M.

1991-01-01

This paper describes recent work directed towards the validation of the metal fuel version of the SAS4A accident analysis code. The SAS4A code system has been developed at Argonne National Laboratory for the simulation of hypothetical severe accidents in Liquid Metal-Cooled Reactors (LMR), designed to operate in a fast neutron spectrum. SAS4A was initially developed for the analysis of oxide-fueled liquid metal-cooled reactors and has played an important role in the simulation and assessment of the energetics potential for postulated severe accidents in these reactors. Due to the current interest in the metal-fueled liquid metal-cooled reactors, a metal fuel version of the SAS4A accident analysis code is being developed in the Integral Fast Reactor program at Argonne. During such postulated accident scenarios as the unprotected (i.e. without scram) loss-of-flow and transient overpower events, a large number of interrelated physical phenomena occur during a relatively short time. These phenomena include transient heat transfer and hydrodynamic events, coolant boiling, and fuel and cladding melting and relocation. Due to strong neutronic feedbacks these events can significantly influence the reactor power history in the accident progression. The paper presents the results of a recent SAS4A simulation of the M7 TREAT experiment. 6 refs., 5 figs

Severity of electrical accidents in the construction industry in Spain.

Science.gov (United States)

Suárez-Cebador, Manuel; Rubio-Romero, Juan Carlos; López-Arquillos, Antonio

2014-02-01

This paper analyzes the severity of workplace accidents involving electricity in the Spanish construction sector comprising 2,776 accidents from 2003 to 2008. The investigation considered the impact of 13 variables, classified into 5 categories: Personal, Business, Temporal, Material, and Spatial. The findings showed that electrical accidents are almost five times more likely to have serious consequences than the average accident in the sector and it also showed how the variables of age, occupation, company size, length of service, preventive measures, time of day, days of absence, physical activity, material agent, type of injury, body part injured, accident location, and type of location are related to the severity of the electrical accidents under consideration. The present situation makes it clear that greater effort needs to be made in training, monitoring, and signage to guarantee a safe working environment in relation to electrical hazards. This research enables safety technicians, companies, and government officials to identify priorities and to design training strategies to minimize the serious consequences of electrical accidents for construction workers. Copyright © 2013 Elsevier Ltd and National Safety Council. All rights reserved.

Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results

International Nuclear Information System (INIS)

Dingman, S.; Camp, S.; LaChance, J.; Mary Drouin

1995-01-01

This paper discusses the core damage frequency (CDF) insights gained by analyzing the results of the Individual Plant Examinations (IPES) for two groups of plants: boiling water reactor (BWR) 3/4 plants with Reactor Core Isolation Cooling systems, and Westinghouse 4-loop plants. Wide variability was observed for the plant CDFs and for the CDFs of the contributing accident classes. On average, transients-with loss of injection, station blackout sequences, and transients with loss of decay heat removal are important contributors for the BWR 3/4 plants, while transients, station blackout sequences, and loss-of-coolant accidents are important for the Westinghouse 4-loop plants. The key factors that contribute to the variability in the results are discussed. The results are often driven by plant-specific design and operational characteristics, but differences in modeling approaches are also important for some accident classes

Unions, Health and Safety Committees, and Workplace Accidents in the Korean Manufacturing Sector

Directory of Open Access Journals (Sweden)

Woo-Yung Kim

2016-06-01

Conclusion: Health and safety committees were found to reduce the incidence of accidents whereas unionized establishments have higher incidence of accidents than nonunionized establishments. We also found that health and safety committees can more effectively reduce accidents in nonunionized establishments. By contrast, nonexclusive joint committees can more effectively reduce accidents in unionized establishments.

Highway accident involving radiopharmaceuticals near Brookhaven, Mississippi on December 3, 1983

International Nuclear Information System (INIS)

Mohr, P.B.; Mount, M.E.; Schwartz, M.W.

1985-04-01

A rear-end collision occurred between a passenger automobile and a luggage trailer carrying 84 packages, 76 of which contained radiopharmaceuticals, on US Highway 84 near Brookhaven, Mississippi on the afternoon of December 3, 1983. The purpose of this report is to document the mechanical circumstances of the accident, confirm the nature and quantity of radioactive materials involved, and assess the nature of the physical environment to which the packages were exposed and the response of the packages. The report consists of three major sections. The first deals wth the nature and circumstances of the accident and findings of fact. The second gives an accounting and description of the materials involved and the consequences of their exposure. The third gives an assessment and analysis of the mechanisms of damage and the conclusions which may be drawn from the investigation. 4 refs., 24 figs., 4 tabs

Database on aircraft accidents

International Nuclear Information System (INIS)

Nishio, Masahide; Koriyama, Tamio

2012-09-01

probability of aircraft crash are considered to be 4 for large fixed-wing aircraft, 35 for small fixed-wing aircraft, 2 for large bladed aircraft and 30 for small bladed aircraft. (2) The data of SDF aircraft accidents is based on newspapers and aircraft magazines. The total of 45 accidents occurred, 24 of them are large fixed-wing aircrafts, 4 are small fixed-wing aircrafts and 17 are bladed aircrafts. 23 to 45 accidents fell into land. (3) The data of US aircraft accidents is based on newspapers and aircraft magazines. The total of 16 accidents occurred, 13 of which are fixed-wing aircrafts, 3 are bladed aircrafts. 6 of 16 accidents fell into land. (4) The instrument flight information on commercial aircrafts is based on 'Air transport statics' of Ministry of Land, Infrastructure, Transport and Tourism. The total number of takeoffs and landings is 29,971,662 and the total flight distance is 9,232,867,684 km. (author)

The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response. 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

Construction industry accidents in Spain.

Science.gov (United States)

Camino López, Miguel A; Ritzel, Dale O; Fontaneda, Ignacio; González Alcantara, Oscar J

2008-01-01

This paper analyzed industrial accidents that take place on construction sites and their severity. Eighteen variables were studied. We analyzed the influence of each of these with respect to the severity and fatality of the accident. This descriptive analysis was grounded in 1,630,452 accidents, representing the total number of accidents suffered by workers in the construction sector in Spain over the period 1990-2000. It was shown that age, type of contract, time of accident, length of service in the company, company size, day of the week, and the remainder of the variables under analysis influenced the seriousness of the accident. IMPACT ON INJURY PREVENTION: The results obtained show that different training was needed, depending on the severity of accidents, for different age, length of service in the company, organization of work, and time when workers work. The research provides an insight to the likely causes of construction injuries in Spain. As a result of the analysis, industries and governmental agencies in Spain can start to provide appropriate strategies and training to the construction workers.

Fuel relocation modeling in the SAS4A accident analysis code system

International Nuclear Information System (INIS)

Tentner, A.M.; Miles, K.J.

1985-01-01

SAS4A is a new code system which has been designed for analyzing the initial phase of Hypothetical Core Disruptive Accidents (HCDAs) up to gross melting or failure of the subassembly walls. During such postulated accident scenarios as the Loss-of-Flow (LOF) and Transient-Overpower (TOP) events, the relocation of the fuel plays a key role in determining the sequence of events and the amount of energy produced before neutronic shutdown. This paper discusses the general strategy used in modeling the various phenomena which lead to fuel relocation and presents the key fuel relocation models used in SAS4A. The implications of these models for the whole-core accident analysis as well as recent results of fuel motion experiment analyses are also presented

Fuel relocation modeling in the SAS4A accident analysis code system

International Nuclear Information System (INIS)

Tentner, A.M.; Miles, K.J.; Kalimullah; Hill, D.J.

1986-01-01

The SAS4A code system has been designed for the analysis of the initial phase of Hypothetical Core Disruptive Accidents (HCDAs) up to gross melting or failure of the subassembly walls. During such postulated accident scenarios as the Loss-of-Flow (LOF) and Transient-Overpower (TOP) events, the relocation of the fuel plays a key role in determining the sequence of events and the amount of energy produced before neutronic shutdown. This paper discusses the general strategy used in modelong the various phenomena which lead to fuel relocation and presents the key fuel relocation models used in SAS4A. The implications of these models for the whole-core accident analysis as well as recent results of fuel relocation are emphasized. 12 refs

An initial assessment of the Chernobyl-4 reactor accident release source

International Nuclear Information System (INIS)

Macdonald, H.F.; ApSimon, H.M.; Wilson, J.J.N.

1986-07-01

The long-range atmospheric dispersion model MESOS has been used to provide a preliminary evaluation of the effects over Western Europe of radioactivity released during the accident which occurred at the Chernobyl-4 reactor in the USSR in April 1986. The results of this analysis have been compared with observations during the first week or so following the accident of airborne contamination levels at a range of locations across Europe in order to obtain an estimate of accident release source. The work presented here was performed during the 6-8 weeks following the accident and the results obtained will be subject to refinement as more detailed data become available. However, at this early stage they indicate a release source for the Chernobyl accident, expressed as a fraction of the estimated reactor core inventory, of approx. 15-20% of the iodine and caesium isotopes, approx. 1% of the ruthenium and lesser amounts of the other fission products and actinides, together with an implied major fraction of the krypton and xenon noble gases. (author)

Chapter 6: Accidents

Energy Technology Data Exchange (ETDEWEB)

NONE

2018-04-01

Th chapter 6 presents the accidents of: 1) Stimos (Italy - May, 1975); 2) San Salvador (El Salvador - February 5, 1989); 3) Soreq (Israel - June 21, 1990); 4) Nesvizh (Belarus - October 26, 1991); 5) Illinois (USA - February, 1965); 6)Maryland (EUA - December 11, 1991); 7)Hanoi (Vietnam -November 17, 1992); 8)Fleurus (Belgium - March 11, 2006) and final remarks on accidents.

Accident sequence precursor analysis level 2/3 model development

International Nuclear Information System (INIS)

Lui, C.H.; Galyean, W.J.; Brownson, D.A.

1997-01-01

The US Nuclear Regulatory Commission's Accident Sequence Precursor (ASP) program currently uses simple Level 1 models to assess the conditional core damage probability for operational events occurring in commercial nuclear power plants (NPP). Since not all accident sequences leading to core damage will result in the same radiological consequences, it is necessary to develop simple Level 2/3 models that can be used to analyze the response of the NPP containment structure in the context of a core damage accident, estimate the magnitude of the resulting radioactive releases to the environment, and calculate the consequences associated with these releases. The simple Level 2/3 model development work was initiated in 1995, and several prototype models have been completed. Once developed, these simple Level 2/3 models are linked to the simple Level 1 models to provide risk perspectives for operational events. This paper describes the methods implemented for the development of these simple Level 2/3 ASP models, and the linkage process to the existing Level 1 models

Sociological aspects of 3.11 Fukushima Daiichi Accident aftermath and the Genshiryoku-mura (nuclear village, or pro-nuclear concession sector)

Energy Technology Data Exchange (ETDEWEB)

Sawada, T., E-mail: tetsuo@nr.titech.ac.jp [Tokyo Inst. of Technology, Research Laboratory for Nuclear Reactors, Meguro-ku, Tokyo (Japan)

2014-07-01

In the 3.11 Fukushima Daiichi Accident aftermath, information contamination induced societal confusion that led to unnecessarily grave fear among the public. The origins and development of the information contamination, and the labeling of Goyo-gakusha and Genshiryoku-mura were phenomenologically analyzed. The historical background to, and reasons for emergence of Goyo-gakusha's were examined by using an axiological approach. The analyses and examination have clarified a typical case of the origins to formation of Genshiryoku-mura. (author)

Analysis of the behaviour of the Kozloduy NPP Unit 3 under severe accident conditions

International Nuclear Information System (INIS)

Velev, V.; Saraeva, V.

2004-01-01

The objective of the analysis is to study the behaviour of the Kozloduy NPP Unit 3 under severe accident conditions. The analysis is performed using computer code MELCOR 1.8.4. This report includes a brief description of Unit 3 active core as well as description and comparison of the key events

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)

The Cost of Company Occupational Accidents: An Activity Based Analysis using the SACA Method

DEFF Research Database (Denmark)

Rikhardsson, Pall M.; Impgaard, Martin

industry sectors. The main conclusions are that only 2/3 of the costs of occupational accidents are visible in corporate accounting systems while 1/3 is hidden from management view. The highest cost of occupational accidents for a company with 3.600 employees was estimated to approximately $682...... - for evaluating the visible and hidden costs of corporate occupational accidents. It also focused on whether the registration, processing and reporting of these costs could be integrated in the corporate accounting information system. The project was based on case studies in 9 Danish companies within 3 different.......000. The integration of occupational cost calculations into accounting systems such as SAP R/3 is considered unlikely for the relatively small Danish companies although technically possible. The costs of doing this and the subsequent costs of registration and control are considered prohibitive. A way forward could...

Learning lessons from accidents with a human and organisational factors perspective: deficiencies and failures of operating experience feedback systems

International Nuclear Information System (INIS)

Dechy, N.; Rousseau, J.M.; Jeffroy, F.

2012-01-01

This paper aims at reminding the failures of operating experience feedback (OEF) systems through the lessons of accidents and provides a framework for improving the efficiency of OEF processes. The risk is for example to miss lessons from other companies and industrial sectors, or to miss the implementation of adequate corrective actions with the risk to repeat accidents. Most of major accidents have been caused by a learning failure or other organisational factors as a contributing cause among several root causes. Some of the recurring organisational factors are: -) poor recognition of critical components, of critical activities or deficiency in anticipation and detection of errors, -) excessive production pressure, -) deficiency of communication or lack of quality of dialogue, -) Excessive formalism, -) organisational complexity, -) learning deficiencies (OEF, closing feedback loops, lack of listening of whistle-blowers). Some major accidents occurred in the nuclear industry. Although the Three Mile Island accident has multiple causes, in particular, an inappropriate design of the man-machine interface, it is a striking example of the loss of external lessons from incidents. As for Fukushima it is too early to have established evidence on learning failures. The systematic study and organisational analysis of OEF failures in industrial accidents whatever their sector has enabled us to provide a framework for OEF improvements. Five key OEF issues to improve in priority: 1) human and organisational factors analysis of the root causes of the events, 2) listening to the field staff, dissenting voices and whistle-blowers, 3) monitoring of the external events that provide generic lessons, 4) building an alive memory through a culture of accidents with people who become experiences pillars, and 5) the setting of external audit or organisational analysis of the OEF system by independent experts. The paper is followed by the slides of the presentation

Numerical Analysis of the Final Cooldown of a 3.3 km Sector of the Large Hadron Collider

CERN Document Server

Liu, L; Tavian, L

2006-01-01

The final cool-down of a 107-m standard cell of LHC, which consists of the helium filling operation at 4.5 K and the further cool-down from 4.5 K to 1.9 K, has been previously simulated and analyzed numerically. To model and analyze the final cool-down process of a whole 3.3-km sector of the LHC, additional boundary conditions must be introduced. In this paper, the slope of the sector, the efficiency of the sub-cooling heat exchanger, the pressure drops and heat loads in different headers of the cryogenic distribution line as well as the fact that both the filling flow of the cold mass and the vaporized flow in the 1.8 K heat exchanger are concurrently supplied have been taken into account. The simulation results, such as the temperature evolution in the LHC magnet cold mass and the pressure profiles in cryogenic line headers during the filling and cool-down from 4.5 K to 1.9 K of a LHC sector are presented. Taking into account the required distribution of the total flow to each cell, all the cells can be fil...

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)

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...

Computerized accident management support system: development for severe accident management

International Nuclear Information System (INIS)

Garcia, V.; Saiz, J.; Gomez, C.

1998-01-01

The activities involved in the international Halden Reactor Project (HRP), sponsored by the OECD, include the development of a Computerized Accident Management Support System (CAMS). The system was initially designed for its operation under normal conditions, operational transients and non severe accidents. Its purpose is to detect the plant status, analyzing the future evolution of the sequence (initially using the APROS simulation code) and the possible recovery and mitigation actions in case of an accident occurs. In order to widen the scope of CAMS to severe accident management issues, the integration of the MAAP code in the system has been proposed, as the contribution of the Spanish Electrical Sector to the project (with the coordination of DTN). To include this new capacity in CAMS is necessary to modify the system structure, including two new modules (Diagnosis and Adjustment). These modules are being developed currently for Pressurized Water Reactors and Boiling Water REactors, by the engineering of UNION FENOSA and IBERDROLA companies (respectively). This motion presents the characteristics of the new structure of the CAMS, as well as the general characteristics of the modules, developed by these companies in the framework of the Halden Reactor Project. (Author)

Analysis of labour risks in the Spanish industrial aerospace sector

Directory of Open Access Journals (Sweden)

JUAN LAGUARDIA

Full Text Available ABSTRACT Labour risk prevention is an activity integrated within Safety and Hygiene at Work in Spain. In 2003, the Electronic Declaration for Accidents at Work, Delt@ (DELTA was introduced. The industrial aerospace sector is subject to various risks. Our objective is to analyse the Spanish Industrial Aerospace Sector (SIAS using the ACSOM methodology to assess its labour risks and to prioritise preventive actions. The SIAS and the Services Subsector (SS were created and the relevant accident rate data were obtained. The ACSOM method was applied through double contrast (deviation and translocation of the SIAS or SS risk polygon with the considered pattern, accidents from all sectors (ACSOM G or the SIAS. A list of risks was obtained, ordered by action phases. In the SIAS vs. ACSOM G analysis, radiation risks were the worst, followed by overstrains. Accidents caused by living beings were also significant in the SS vs. SIAE, which will be able to be used to improve Risk Prevention. Radiation is the most significant risk in the SIAS and the SS. Preventive actions will be primary and secondary. ACSOM has shown itself to be a valid tool for the analysis of labour risks.

Analysis of labour risks in the Spanish industrial aerospace sector.

Science.gov (United States)

Laguardia, Juan; Rubio, Emilio; Garcia, Ana; Garcia-Foncillas, Rafael

2016-01-01

Labour risk prevention is an activity integrated within Safety and Hygiene at Work in Spain. In 2003, the Electronic Declaration for Accidents at Work, Delt@ (DELTA) was introduced. The industrial aerospace sector is subject to various risks. Our objective is to analyse the Spanish Industrial Aerospace Sector (SIAS) using the ACSOM methodology to assess its labour risks and to prioritise preventive actions. The SIAS and the Services Subsector (SS) were created and the relevant accident rate data were obtained. The ACSOM method was applied through double contrast (deviation and translocation) of the SIAS or SS risk polygon with the considered pattern, accidents from all sectors (ACSOM G) or the SIAS. A list of risks was obtained, ordered by action phases. In the SIAS vs. ACSOM G analysis, radiation risks were the worst, followed by overstrains. Accidents caused by living beings were also significant in the SS vs. SIAE, which will be able to be used to improve Risk Prevention. Radiation is the most significant risk in the SIAS and the SS. Preventive actions will be primary and secondary. ACSOM has shown itself to be a valid tool for the analysis of labour risks.

CarSim: Automatic 3D Scene Generation of a Car Accident Description

OpenAIRE

Egges, A.; Nijholt, A.; Nugues, P.

2001-01-01

The problem of generating a 3D simulation of a car accident from a written description can be divided into two subtasks: the linguistic analysis and the virtual scene generation. As a means of communication between these two system parts, we designed a template formalism to represent a written accident report. The CarSim system processes formal descriptions of accidents and creates corresponding 3D simulations. A planning component models the trajectories and temporal values of every vehicle ...

Database on aircraft accidents

International Nuclear Information System (INIS)

Nishio, Masahide; Koriyama, Tamio

2013-11-01

for evaluating probability of aircraft crash are considered to be 4 for large fixed-wing aircraft, 35 for small fixed-wing aircraft, 1 for large bladed aircraft and 25 for small bladed aircraft. (2) The data of SDF aircraft accidents is based on newspapers and aircraft magazines. The total number of accidents is 42 comprised of 21 for large fixed-wing aircraft, 4 for small fixed-wing aircraft and 17 for bladed aircraft. The 23 accidents of the total fell into land. (3) The data of US aircraft accidents is based on newspapers and aircraft magazines. The total number of accidents is 16 comprised of 13 for fixed-wing aircraft and 3 for bladed aircraft. The 6 accidents of the total fell into land. (4) The instrument flight information on commercial aircrafts is based on 'Air transport statics' of Ministry of Land, Infrastructure, Transport and Tourism. The total number of takeoffs and landings is 30,685,564 and the total flight distance is 9,499,283,168 km. (author)

3.4 Environmental impacts: energy industry

International Nuclear Information System (INIS)

2004-01-01

The subchapter 3.4 'Environmental impact of the energy industry' of the 7th state of the environment report analyzes the current situation in Austria and briefly describes the following aspects: environmental policy targets, uniform taxation of energy, use of renewable energy sources, efficient use of energy, energy input, electricity supply and input, energy input into space heating and air conditioning systems, and renewable energy. In 2002, the input of final energy was risen by about 5 % in comparison to 1998. During this period, the largest increments in final energy inputs were recorded in the mobility sector with + 9.4 %, and in the private households sector with + 8.3 % . The goods production sector showed a slight decrease of about 1.3 % between 1998 and 2002. The 'goods production', 'mobility' and 'private households' sectors combined require about 87 % of the total final energy input. The final energy input for space heating and hot water in 2001 was 5.7 % above the input in 1998. Energy supply from renewable energy sources rose by about 13.8 % in 2002 compared to 1998. Domestic electricity consumption (excluding consumption for pumped-storage systems) in 2002 was about 10.5 % above consumption in 1998. Physical imports and physical exports in 2002 increased about 32 % and 8.6 % correspondingly compared to 1999. (nevyjel)

High prevalence of cesarean section births in private sector health facilities- analysis of district level household survey-4 (DLHS-4) of India.

Science.gov (United States)

Singh, Priyanka; Hashmi, Gulfam; Swain, Prafulla Kumar

2018-05-10

Worldwide rising cesarean section (CS) births is an issue of concern. In India, with increase in institutional deliveries there has also been an increase in cesarean section births. Aim of the study is to quantify the prevalence of cesarean section births in public and private health facility, and also to determine the factors associated with cesarean section births. We analyzed data from district level household survey data 4 (DLHS-4) combined individual level dataset for 19 states/UTs of India comprising 24,398 deliveries resulting in 22,111 live births for year 2011. The percentages and Chi-square has been computed for the select variables viz. Socio demographic, maternal, antenatal care and delivery related based on type of births (CS Vs normal births). The multiple logistic regression model has been used to identify the potential risk factors associated with CS births. Of 22,111 live birth analyzed 49.2% were delivered at public sector, 31.9% at private sector and 18.9% were home deliveries. Prevalence of CS births were 13.7% (95% CI; 13.0- 14.3%) and 37.9% (95% CI; 36.7- 39.0%) in the public and private sectors, respectively. Higher odds of CS births were observed with- delivery at private health facility (OR 3.79; 95% C.I 3.06-4.72), urban residence (OR 1.15; 95% C.I 1.00- 1.35), first delivery after 35 years of maternal age (OR 5.5; 95% C.I 1.85- 16.4), hypertension in pregnancy (OR 1.32; 95% C.I 1.06- 1.65) and breach presentation (OR 2.37; 95% C.I. 1.63- 3.43). Our findings shows that CS births are nearly three times more in private as compared to public sector health facilities.The higher rates of CS births, especially in private sector, not only increase the cost of care but may pose unnecessary risks to women (when there is no indications for CS). The government of India need to take measures to strengthen existing public health facilities as well as ensure that cesarean sections are performed based upon medical indications in both public and private

Fukushima-Daiichi after the severe accident (estimation)

International Nuclear Information System (INIS)

Otcenasek, Petr

2011-01-01

All facts about the Fukushima-Daiichi NPP and about the accident known at the time of publication are summarized and expected remedial actions and consequences of the accidents are deduced. The paper is structured as follows: (1) Accident initiation is known; (2) Logically inferred results; (3) Framework identification; (4) Survey; and (5) Economic and strategic impacts of the accident. Worldwide solidarity is mentioned in conclusion. (P.A.)

Near extremal intersecting giants and new decoupled sectors in N = 4 SYM

International Nuclear Information System (INIS)

Fareghbal, R.; Gowdigere, C.N.; Mosaffa, A.E.; Sheikh-Jabbari, M. M.

2008-01-01

We study near-horizon limits of near-extremal charged black hole solutions to five-dimensional U(1) 3 gauged supergravity carrying two charges, extending the recent work of Balasubramanian et al. We show that there are two near-horizon decoupling limits for the near-extremal black holes, one corresponding to the near-BPS case and the other for the far from BPS case. Both of these limits are only defined on the 10d IIB uplift of the 5d black holes, resulting in a decoupled geometry with a six-dimensional part (conformal to) a rotating BTZ x S 3 . We study various aspects of these decoupling limits both from the gravity side and the dual field theory side. For the latter we argue that there should be two different, but equivalent, dual gauge theory descriptions, one in terms of the 2d CFT's dual to the rotating BTZ and the other as certain large R-charge sectors of d = 4, N = 4 U(N) SYM theory. We discuss new BMN-type sectors of the N = 4 SYM in the N → ∞ limit in which the engineering dimensions scale as N 3/2 (for the near-BPS case) and as N 2 (for the far from BPS case). (author)

Accident investigation practices in Europe--main responses from a recent study of accidents in industry and transport.

Science.gov (United States)

Roed-Larsen, Sverre; Valvisto, T; Harms-Ringdahl, L; Kirchsteiger, C

2004-07-26

Europe has during recent years been shocked by disasters from natural events and technical breakdowns. The consequences have been comprehensive, measured by lost lives, injuries, and material and environmental damage. ESReDA wanted in 2000--by setting up a special expert group on accident investigation--to clarify the state of art of accident investigation practices and to map the use of thoroughly accident investigation in order to learn lessons from past disasters and prevent new ones. The scope was to cover three sectors in the society: transport, production processes and storage of hazardous materials, and energy production. The main method used was a questionnaire, which was sent in 2001 to about 150 organisations. About 50 replies were analysed. The replies showed great variations but also similarities, among others in definition of accident and incident, the objectives of the investigation team, criteria used to start an investigation, the status of the investigation organisation, the flow of information, the composition of the investigation team, and the use of internal or international procedures or rules. Several methods (in total 14 different methods were mentioned) were used for carrying out accident /incident investigations. Most of the respondents were willing to co-operate in one or another way with ESReDA. Although there are important biases in the material, the results from questionnaire are important inputs to the future work of ESReDA Expert group in this field. 3 safety approaches have been identified.

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.

The Fukushima accident

International Nuclear Information System (INIS)

Maqua, M.; Stueck, R.

2012-01-01

On 11 March 2011, the Tohoku earthquake and the subsequent tsunami hit the Japanese east coast, causing more than 15,000 fatalities. To this date, 3,000 people are still missing. The Fukushima Dai-ichi NPP was the nuclear installation that was most affected by the tsunami. The earthquake cut off the NPP from the national grid. About 45 minutes later, the tsunami flooded units 1-4 and led to core meltdown events with large releases for units 1, 2 and 3. Unit 4 had been in refuelling outage at that time and lost the cooling of the spent fuel pool for several days. Considerable hydrogen explosions occurred in units 1, 3 and 4. Shortly after the accident, TEPCO started to mitigate the consequences of the accident by providing external cooling to the reactors and by removing the radioactive debris from the site. Great emphasis was laid on effective radiation protection measures for the clean-up workers. Thus, up to now there has been no fatality due to the radiation caused by the Fukushima accident. The main steps of the accident sequences are described, taking into account the latest findings of investigations performed by TEPCO or on behalf of the regulatory body. The presentation focuses on the description of the status of the Fukushima Dai-ichi nuclear power plant and the future steps for cleaning-up the site. In the presentation, the major phases of the roadmap that TEPCO has developed for the clean-up are highlighted. The risks associated with the current plant status and the clean-up phases are described. Abstract the content of the manuscript in a few lines.

Stressful life events and occupational accidents.

Science.gov (United States)

Cordeiro, Ricardo; Dias, Adriano

2005-10-01

The purpose of this study was to examine the association between stressful life events and occupational accidents. This was a population-based case-control study, carried out in the city of Botucatu, in southeast Brazil. The cases consisted of 108 workers who had recently experienced occupational accidents. Each case was matched with three controls. The cases and controls answered a questionnaire about recent exposure to stressful life events. Reporting of "environmental problems", "being a victim of assault", "not having enough food at home" and "nonoccupational fatigue" were found to be risk factors for work-related accidents with estimated incidence rate ratios of 1.4 [95% confidence interval (95% CI) 1.1-1.7], 1.3 (95% CI 1.1-1.7), 1.3 (95% CI 1.1-1.6), and 1.4 (95% CI 1.2-1.7) respectively. The findings of the study suggested that nonwork variables contribute to occupational accidents, thus broadening the understanding of these phenomena, which can support new approaches to the prevention of occupational accidents.

Long-Term Station Blackout Accident Analyses of a PWR with RELAP5/MOD3.3

Directory of Open Access Journals (Sweden)

Andrej Prošek

2013-01-01

Full Text Available Stress tests performed in Europe after accident at Fukushima Daiichi also required evaluation of the consequences of loss of safety functions due to station blackout (SBO. Long-term SBO in a pressurized water reactor (PWR leads to severe accident sequences, assuming that existing plant means (systems, equipment, and procedures are used for accident mitigation. Therefore the main objective was to study the accident management strategies for SBO scenarios (with different reactor coolant pumps (RCPs leaks assumed to delay the time before core uncovers and significantly heats up. The most important strategies assumed were primary side depressurization and additional makeup water to reactor coolant system (RCS. For simulations of long term SBO scenarios, including early stages of severe accident sequences, the best estimate RELAP5/MOD3.3 and the verified input model of Krško two-loop PWR were used. The results suggest that for the expected magnitude of RCPs seal leak, the core uncovery during the first seven days could be prevented by using the turbine-driven auxiliary feedwater pump and manually depressurizing the RCS through the secondary side. For larger RCPs seal leaks, in general this is not the case. Nevertheless, the core uncovery can be significantly delayed by increasing RCS depressurization.

Scientific literacy No.05 after the 3.11 accident

International Nuclear Information System (INIS)

Makino, Junichiro

2013-01-01

It has been seen that the thyroid cancer incidence in the Chernobyl accident is larger one order of magnitude over the cancer incidence guessed from the investigation of radiation-exposed people after the 3.11 accident. Taking into account the limitation in the epidemiologic studies of radiation-exposed people, the results of these studies cannot be regarded as an absolute being. It is necessary to revaluate scientifically Chernobyl actual conditions and to think the radioactive influence with low dose-rate. (M.H.)

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.)

Emotional stress and traffic accidents: the impact of separation and divorce.

Science.gov (United States)

Lagarde, Emmanuel; Chastang, Jean-François; Gueguen, Alice; Coeuret-Pellicer, Mireille; Chiron, Mireille; Lafont, Sylviane

2004-11-01

Personal responses to stressful life events are suspected of increasing the risk of serious traffic accidents. We analyzed data from a French cohort study (the GAZEL cohort), including a retrospective driving behavior questionnaire, from 13,915 participants (10,542 men age 52-62 years and 3373 women age 47-62 years in 2001). Follow-up data covered 1993-2000. Hazard ratios for serious accidents (n = 713) were computed by Cox's proportional hazard regression with time-dependent covariates. Separate analyses were also performed to consider only at-fault accidents. Marital separation or divorce was associated with an increased risk of a serious accident (all serious accidents: hazard ratio 2.9, 95% confidence interval = 1.7-5.0; at-fault accidents: 4.4, 2.3-8.3). The impact of separation and divorce did not differ according to alcohol consumption levels. Other life events associated with increased risk of serious accident were a child leaving home (all accidents: 1.2, 0.97-1.6; at-fault accidents: 1.5, 1.1-2.1), an important purchase (all accidents: 1.4, 1.1-1.7; at-fault accidents: 1.6, 1.2-2.1), and hospitalization of the partner (all accidents: 1.4, 1.1-2.0). This study suggests that recent separation and divorce are associated with an increase in serious traffic accidents.

Safety Culture and Issue in the Malaysian Manufacturing Sector

OpenAIRE

Ali Danish; Yusof Yusri; Adam Anbia

2017-01-01

. This paper highlights the Safety culture and issue in the Malaysian Manufacturing Sector and emphasis the high occupational accidents due to lack of safety culture and non-compliance of the requirements of Occupational Safety and Health Act 1994. The aim of this study is to review the occupational accidents occurrence in the Malaysia workplace since 2012-2016. Malaysia aimed to reduce the occupational accidents, the results show by DOSH increase that Occupational Noise Induced Hearing Loss ...

Report on the radiological accident in Goiania, Goias, Brazil

International Nuclear Information System (INIS)

Alves, R.N.

1988-01-01

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

Medical care of radiation accidents

International Nuclear Information System (INIS)

Nakao, Isamu

1986-02-01

This monograph, divided into six chapters, focuses on basic knowledge and medical strategies for radiation accidents. Chapters I to V deal with practice in emergency care for radiation exposure, covering 1) medical strategies for radiation accidents, 2) personnel dosimetry and monitoring, 3) nuclear facilities and their surrounding areas with the potential for creating radiation accidents, and emergency medical care for exposed persons, 4) emergency care procedures for radiation exposure and radioactive contamination, and 5) radiation hazards and their treatment. The last chapter provides some references. (Namekawa, K.)

Revisiting Ulchin 4 SGTR Accident - Analysis for EOP Improvement

Energy Technology Data Exchange (ETDEWEB)

Lee, Eun-Hye; Lee, Wook-Jo; Jerng, Dong-Wook [Chung-Ang University, Seoul (Korea, Republic of)

2016-10-15

The Steam Generator Tube Ruputure (SGTR) is an accident that U-tube inside the SG is defected so that the reactor coolant releases through broken U-tube and this is one of design basis accidents. Operating the Nuclear Power Plants (NPP), maintaing the integrity of core and preventing radiation release are most important things. Because of risks, many researchers have studied scenarios, impacts and the ways to mitigate SGTR accidents. The study to provide an experimental database of aerosol particle retention and to develop models to support accident management interventions during SGTR was performed. The scaled-down models of NPP were used for experiments, also, MELCOR and SCDAP/RELAP5 were used to simulate a design basis SGTR accident. This study had a major role to resolve uncertainties of various physical models for aerosol mechanical resuspension. The other study which analyzed SGTR accident for System-integrated Modular Advanced Reactor (SMART) was performed. In this analysis, the amount of break flow was focused and TASS/SMRS code was used. It assumed that maximum leak was generated, and found that high RCS pressure, low core inlet coolant temperature, and low break location of the SG cassette contributed to leakage. Although the leakage was large, there was no direct release to atmosphere because the pressure of secondary loop was maintained below the safety relief valve set point. In this analysis, comparison of mitigating procedure when SGTR occurs between shutdown condition and full power condition was performed. In shutdown condition, the core uncovery would not take place in 16 hours whether the cooling procedures are performed or not. Therefore, the integrated amount of break flow should be considered only. In this point of view, cooling through intact SG only, case 3, is the best way to minimize the amount of break flow. In full power condition, the core water level is changed due to high reactor power. The important thing to protect NPP is to keep

A Comprehensive Analysis of the X-15 Flight 3-65 Accident

Science.gov (United States)

Dennehy, Cornelius J.; Orr, Jeb S.; Barshi, Immanuel; Statler, Irving C.

2014-01-01

The November 15, 1967, loss of X-15 Flight 3-65-97 (hereafter referred to as Flight 3-65) was a unique incident in that it was the first and only aerospace flight accident involving loss of crew on a vehicle with an adaptive flight control system (AFCS). In addition, Flight 3-65 remains the only incidence of a single-pilot departure from controlled flight of a manned entry vehicle in a hypersonic flight regime. To mitigate risk to emerging aerospace systems, the NASA Engineering and Safety Center (NESC) proposed a comprehensive review of this accident. The goal of the assessment was to resolve lingering questions regarding the failure modes of the aircraft systems (including the AFCS) and thoroughly analyze the interactions among the human agents and autonomous systems that contributed to the loss of the pilot and aircraft. This document contains the outcome of the accident review.

Priorities for Addressing Severe Accident and L3PSA in Radiation Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Jang, M. S.; Kang, H. S.; Kim, S. R. [NESS, Daejeon (Korea, Republic of); Yang, Y. H.; Yoon, Y. I. [KHNP, Daejeon (Korea, Republic of)

2016-05-15

Domestic rules for the radiation environment impact assessment were enacted based on NUREG-0555, the guidance to the nuclear regulatory commission staff in implementing provisions of 10 CFR 51, 'environmental protection regulations for domestic licensing and related regulatory functions', related to NPPs. A revised document of NUREG-0555 was published in 2000 as NUREG-1555, Vol. 1 and 2. The related domestic rules would have made some revisions in accordance with NUREG-1555 in 2016. In this paper, we would introduce the new technical standards and review legal and technical issues on legislation. There are three legal and technical issues on revised legislation that includes severe accidents and L3PSA results in RER. First, it may need a regular and continuing education for the severe accident concept, probabilistic assessment method and conservative assumptions for severe accident, how to interpret the assessment results, the probability of a severe accident, SAMA and etc. to obtain the public understanding for severe accident. Second, it needs the development of strategy and technology not only to evaluate the risk of multi-unit accidents and failure case and the impacts of inter-unit shared systems and common events for the probabilistic assessment of severe accidents but also to solve many potential L3PSA challenges. Finally, the cost-beneficial SAMAs analysis would be added in radiation environmental impact and severe accident impact analysis.

Man, road and vehicle: risk factors associated with the severity of traffic accidents.

Science.gov (United States)

Almeida, Rosa Lívia Freitas de; Bezerra Filho, José Gomes; Braga, José Ueleres; Magalhães, Francismeire Brasileiro; Macedo, Marinila Calderaro Munguba; Silva, Kellyanne Abreu

2013-08-01

To describe the main characteristics of victims, roads and vehicles involved in traffic accidents and the risk factors involved in accidents resulting in death. METHODS A non-concurrent cohort study of traffic accidents in Fortaleza, CE, Northeastern Brazil, in the period from January 2004 to December 2008. Data from the Fortaleza Traffic Accidents Information System, the Mortality Information System, the Hospital Information System and the State Traffic Department Driving Licenses and Vehicle database. Deterministic and probabilistic relationship techniques were used to integrate the databases. First, descriptive analysis of data relating to people, roads, vehicles and weather was carried out. In the investigation of risk factors for death by traffic accident, generalized linear models were used. The fit of the model was verified by likelihood ratio and ROC analysis. RESULTS There were 118,830 accidents recorded in the period. The most common types of accidents were crashes/collisions (78.1%), running over pedestrians (11.9%), colliding with a fixed obstacle (3.9%), and with motorcycles (18.1%). Deaths occurred in 1.4% of accidents. The factors that were independently associated with death by traffic accident in the final model were bicycles (OR = 21.2, 95%CI 16.1;27.8), running over pedestrians OR = 5.9 (95%CI 3.7;9.2), collision with a fixed obstacle (OR = 5.7, 95%CI 3.1;10.5) and accidents involving motorcyclists (OR = 3.5, 95%CI 2.6;4.6). The main contributing factors were a single person being involved (OR = 6.6, 95%CI 4.1;10.73), presence of unskilled drivers (OR = 4.1, 95%CI 2.9;5.5) a single vehicle (OR = 3.9, 95%CI 2,3;6,4), male (OR = 2.5, 95%CI 1.9;3.3), traffic on roads under federal jurisdiction (OR = 2.4, 95%CI 1.8;3.7), early morning hours (OR = 2.4, 95%CI 1.8;3.0), and Sundays (OR = 1.7, 95%CI 1.3;2.2), adjusted according to the log-binomial model. CONCLUSIONS Activities promoting the prevention of traffic accidents should primarily focus on

41 CFR 101-39.401 - Reporting of accidents.

Science.gov (United States)

2010-07-01

...-INTERAGENCY FLEET MANAGEMENT SYSTEMS 39.4-Accidents and Claims § 101-39.401 Reporting of accidents. (a) The... manager of the GSA IFMS fleet management center issuing the vehicle; (2) The employee's supervisor; and (3... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Reporting of accidents...

Cannabis, alcohol and fatal road accidents.

Science.gov (United States)

Martin, Jean-Louis; Gadegbeku, Blandine; Wu, Dan; Viallon, Vivian; Laumon, Bernard

2017-01-01

This research aims to estimate the relative risks of responsibility for a fatal accident linked to driving under the influence of cannabis or alcohol, the prevalence of these influences among drivers and the corresponding attributable risk ratios. A secondary goal is to estimate the same items for three other groups of illicit drugs (amphetamines, cocaine and opiates), and to compare the results to a similar study carried out in France between 2001 and 2003. Police procedures for fatal accidents in Metropolitan France during 2011 were analyzed and 300 characteristics encoded to provide a database of 4,059 drivers. Information on alcohol and four groups of illicit drugs derived from tests for positivity and potential confirmation through blood analysis. The study compares drivers responsible for causing the accident, that is to say having directly contributed to its occurrence, to drivers involved in an accident for which they were not responsible, and who can be assimilated to drivers in general. The proportion of persons driving under the influence of alcohol is estimated at 2.1% (95% CI: 1.4-2.8) and under the influence of cannabis at 3.4% (2.9%-3.9%). Drivers under the influence of alcohol are 17.8 times (12.1-26.1) more likely to be responsible for a fatal accident, and the proportion of fatal accidents which would be prevented if no drivers ever exceeded the legal limit for alcohol is estimated at 27.7% (26.0%-29.4%). Drivers under the influence of cannabis multiply their risk of being responsible for causing a fatal accident by 1.65 (1.16-2.34), and the proportion of fatal accidents which would be prevented if no drivers ever drove under the influence of cannabis is estimated at 4.2% (3.7%-4.8%). An increased risk linked to opiate use has also been found to be significant, but with low prevalence, requiring caution in interpreting this finding. Other groups of narcotics have even lower prevalence, and the associated extra risks cannot be assessed. Almost a

Cannabis, alcohol and fatal road accidents.

Directory of Open Access Journals (Sweden)

Jean-Louis Martin

Full Text Available This research aims to estimate the relative risks of responsibility for a fatal accident linked to driving under the influence of cannabis or alcohol, the prevalence of these influences among drivers and the corresponding attributable risk ratios. A secondary goal is to estimate the same items for three other groups of illicit drugs (amphetamines, cocaine and opiates, and to compare the results to a similar study carried out in France between 2001 and 2003.Police procedures for fatal accidents in Metropolitan France during 2011 were analyzed and 300 characteristics encoded to provide a database of 4,059 drivers. Information on alcohol and four groups of illicit drugs derived from tests for positivity and potential confirmation through blood analysis. The study compares drivers responsible for causing the accident, that is to say having directly contributed to its occurrence, to drivers involved in an accident for which they were not responsible, and who can be assimilated to drivers in general.The proportion of persons driving under the influence of alcohol is estimated at 2.1% (95% CI: 1.4-2.8 and under the influence of cannabis at 3.4% (2.9%-3.9%. Drivers under the influence of alcohol are 17.8 times (12.1-26.1 more likely to be responsible for a fatal accident, and the proportion of fatal accidents which would be prevented if no drivers ever exceeded the legal limit for alcohol is estimated at 27.7% (26.0%-29.4%. Drivers under the influence of cannabis multiply their risk of being responsible for causing a fatal accident by 1.65 (1.16-2.34, and the proportion of fatal accidents which would be prevented if no drivers ever drove under the influence of cannabis is estimated at 4.2% (3.7%-4.8%. An increased risk linked to opiate use has also been found to be significant, but with low prevalence, requiring caution in interpreting this finding. Other groups of narcotics have even lower prevalence, and the associated extra risks cannot be assessed

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)

Analysis of construction accidents in Spain, 2003-2008.

Science.gov (United States)

López Arquillos, Antonio; Rubio Romero, Juan Carlos; Gibb, Alistair

2012-12-01

The research objective for this paper is to obtain a new extended and updated insight to the likely causes of construction accidents in Spain, in order to identify suitable mitigating actions. The paper analyzes all construction sector accidents in Spain between 2003 and 2008. Ten variables were chosen and the influence of each variable is evaluated with respect to the severity of the accident. The descriptive analysis is based on a total of 1,163,178 accidents. Results showed that the severity of accidents was related to variables including age, CNAE (National Classification of Economic Activities) code, size of company, length of service, location of accident, day of the week, days of absence, deviation, injury, and climatic zones. According to data analyzed, a large company is not always necessarily safer than a small company in the aspect of fatal accidents, experienced workers do not have the best accident fatality rates, and accidents occurring away from the usual workplace had more severe consequences. Results obtained in this paper can be used by companies in their occupational safety strategies, and in their safety training programs. Copyright © 2012 National Safety Council and Elsevier Ltd. All rights reserved.

Comparison of MAAP4.03 with RELAP/SCDAPSIM/MOD3.2

Energy Technology Data Exchange (ETDEWEB)

Kohriyama, T.; Ohtani, M. [Technical Support Project, Institute of Nuclear Technology, Institute of Nuclear Safety System, Incorporated, Mihama, Fukui (Japan); Ezzidi, A.; Morota, H. [Computer Software Development Co., Ltd., Tokyo (Japan)

2000-11-01

The MAAP4.03 code has been widely used for analyses of severe accident phenomena. It is, however, a system level code applying simpler models and could show phenomenological uncertainties. In order to support MAAP4.03 by a more detailed mechanistic code such as RELAP/SCDAPSIM/MOD3.2, code-to-code comparisons are performed. For a typical 4 loop PWR, analyses of two severe accident sequences were executed. Both codes predicted similar tendencies until the beginning of core melt. MAAP4.03 showed earlier slumping of molten core to a lower head of a reactor pressure vessel than RELAP/SCDAPSIM/MOD3.2. MAAP4.03 considers only axial flows of molten core and crusts suddenly breach by Creep Rupture. RELAP/SCDAPSIM/MOD3.2 treats axial and radial spreads by repeated cycles of melting, flowing and freezing. Bottom crusts can be supported by intact fuel rods. By these more realistic RELAP/SCDAPSIM/MOD3.2 models, MAAP4.03 could be supported maintaining conservatism. (author)

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.

[Accidents among postmen using motorbikes for mail deliveries in Tuscany in the period 2007-2009].

Science.gov (United States)

Chellini, Elisabetta; Cortini, Barbara; Mameli, Marina; Abbarchi, M; Dei, Simona; Rossi, Oriana; Zallocco, A

2014-01-01

Health risks for postmen using motorbikes for mail delivery may be influenced by stability, weight and ease of handling of the vehicle, traffic and slippery or irregular road surface. To describe accidents that occurred among postmen in Tuscany and evaluate how many of these would have been prevented using the UNI EN 13595/2004 safety jacket. Record linkage of data obtained from the employer--the main mail delivery company in Italy--and from the Italian Workers Compensation Authority on accidents that occurred in postmen in Tuscany who used motorbikes for deliveries during the period 2007-2009. Accident rates (with CI 95%) by age, sex, year and province were calculated; the differences were evaluated using chi2 test. 1,342 accidents requiring at least 3 days' sick absence were recorded in postmen in Tuscany in the period 2007-2009, with an increasing trend in young men. The average accident rate was 17.6 per 100 workers, with 42,419 sick absence days. The female rate was higher compared to men (19.4%, CI 95% 18.03-20.79 in women vs 15.5%, CI 95%: 14.15-16.89 in men). 68% of accidents occurred driving a motorbike. The index of severity was 6.79, which was higher than that calculated by INAIL for the whole Tuscan transport and communication work sector (5.31). 309 accidents (11,021 sick absence days) could have been mitigated or avoided using UNI EN 13595/2004 safety jackets (47% spinal, 30% shoulder, 23% elbow, arm and forearm). The frequency of accidents in postmen using motorbikes is extremely high. Several serious accidents could have been prevented using the UNI EN 13595/2004 safety jackets, suggesting the need to make their use obligatory by these workers.

On-line measurements of RuO{sub 4} during a PWR severe accident

Energy Technology Data Exchange (ETDEWEB)

Reymond-Laruinaz, S.; Doizi, D. [CEA, DEN, Departement de Physico-chimie, CEA/Saclay, 91191 Gif sur Yvette Cedex, (France); Manceron, L. [Societe Civile Synchrotron SOLEIL, L' Orme des Merisiers, St-Aubin BP48, 91192 Gif-sur-Yvette Cedex, (France); MONARIS, UMR 8233, Universite Pierre et Marie Curie, 4 Place Jussieu, case 49, F-75252 Paris Cedex 05, (France); Boudon, V. [Laboratoire Interdisciplinaire Carnot de Bourgogne, UMR 6303 CNRS-Universite de Bourgogne, 9 avenue Alain Savary, BP 47870, F-21078 Dijon Cedex, (France); Ducros, G. [CEA, DEN, Departement d' Etudes des Combustibles, CEA/Cadarache, 13108 Saint-Paul-lez-Durance cedex, (France)

2015-07-01

After the Fukushima accident, it became essential to have a way to monitor in real time the evolution of a nuclear reactor during a severe accident, in order to react efficiently and minimize the industrial, ecological and health consequences of the accident. Among gaseous fission products, the tetroxide of ruthenium RuO{sub 4} is of prime importance since it has a significant radiological impact. Ruthenium is a low volatile fission product but in case of the rupture of the vessel lower head by the molten corium, the air entering into the vessel oxidizes Ru into gaseous RuO{sub 4}, which is not trapped by the Filtered Containment Venting Systems. To monitor the presence of RuO{sub 4} allows making a diagnosis of the core degradation and quantifying the release into the atmosphere. To determine the presence of RuO{sub 4}, FTIR spectrometry was selected. To study the feasibility of the monitoring, high-resolution IR measurements were realized at the French synchrotron facility SOLEIL on the infrared beam line AILES. Thereafter, theoretical calculations were done to simulate the FTIR spectrum to describe the specific IR fingerprint of the molecule for each isotope and based on its partial pressure in the air. (authors)

Radiological accident 'The Citadel' medical aspects

International Nuclear Information System (INIS)

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

2008-01-01

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

Analysis of Occupational Accidents in Underground and Surface Mining in Spain Using Data-Mining Techniques.

Science.gov (United States)

Sanmiquel, Lluís; Bascompta, Marc; Rossell, Josep M; Anticoi, Hernán Francisco; Guash, Eduard

2018-03-07

An analysis of occupational accidents in the mining sector was conducted using the data from the Spanish Ministry of Employment and Social Safety between 2005 and 2015, and data-mining techniques were applied. Data was processed with the software Weka. Two scenarios were chosen from the accidents database: surface and underground mining. The most important variables involved in occupational accidents and their association rules were determined. These rules are composed of several predictor variables that cause accidents, defining its characteristics and context. This study exposes the 20 most important association rules in the sector-either surface or underground mining-based on the statistical confidence levels of each rule as obtained by Weka. The outcomes display the most typical immediate causes, along with the percentage of accidents with a basis in each association rule. The most important immediate cause is body movement with physical effort or overexertion, and the type of accident is physical effort or overexertion. On the other hand, the second most important immediate cause and type of accident are different between the two scenarios. Data-mining techniques were chosen as a useful tool to find out the root cause of the accidents.

Severe accident recriticality analyses (SARA)

DEFF Research Database (Denmark)

Frid, W.; Højerup, C.F.; Lindholm, I.

2001-01-01

with all three codes. The core initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality-both super-prompt power bursts and quasi steady-state power......Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies......, which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal g(-1), was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate of 2000 kg s(-1). In most cases, however, the predicted energy deposition was smaller, below...

Studying Disabling Occupational Accidents in the Construction Industry During Two Years

Directory of Open Access Journals (Sweden)

Ahmad Soltanzadeh

2014-06-01

Full Text Available Background & Objectives : Idnetifying causes of occupational accidents is a key issue to prevent these accidents. The present study aimed to identify and analyze debilitating accidents in the construction industry during a two-year period ( 2010 - 2011 years . Methods: This was an analytical cross-sectional study. The study data included information about all debilitating accidents occurred within two years. Data collection was performed according to the accident report forms in construction sites. Data analysis was performed using SPSS software version 16. The level of significance was considered as P=0.05. Results: The mean age and job experience of injured people were 27.95±6.95 and 2.34±2.00 years, respectively. Most injuries to people were reported in hand (35.4%, legs (28.3% and back (20.4%. Most of accident types were respectively related to slipping and falling (26.1%, throwing objects (21.7%, falls (18.6%, abrasion (16.8% and clash (16.4%. Moreover, the main causes of accidents were related to lack of housekeeping (97.3%, lack of proper training (85.8%, lack of PPE (73.0%, unsafe acts (63.3%, unsafe conditions (32.3% and equipment (22.6%. Conclusion: Analyzing causes of disabling accidents in the construction industry showed that important factors in these accidents included lack of housekeeping, failure to provide proper training, lack of suitable PPE, unsafe acts, unsafe conditions and equipment for the construction jobs

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

State of reaction on news media for JCO criticality accident on abroad

International Nuclear Information System (INIS)

Itoh, Takeshi

1999-01-01

The criticality accident, which occurred in JCO Tokai on September 30th 1999, was the first accident accompanied with serious radiation exposure to persons at Japanese nuclear facilities. As an evacuation order for local residents was issued, it caused uneasiness to the public. It also gave great impact to the foreign countries. In this report we have investigated the reactions in such countries, as U.S., France, Germany and U.K. by means of news media like TV, newspapers and magazines. Finding are as follows: They were all surprised to know the cause of the accident, which was by improper procedure of JCO workers. Because they couldn't imagine that such an accident might happen in such a high-tech country as Japan. The Japanese regulator was criticized for their insufficient criticality facility surveillance. There arose some questions for Japanese nuclear reliabilities. Because of the delayed announcement of the accident by Japanese public sector, anti-nuclear groups, like Greenpeace, NCI, etc., have a chance to carry on their campaign. The information from Japanese public sector was not enough to satisfy the foreign news media. We concluded that it is also necessary to develop effective information dissemination to overseas in case of a nuclear accident. (author)

Accidents in the school environment: perspectives of staff concerned with data collection and reporting procedures.

Science.gov (United States)

Williams, W R; Latif, A H; Cater, L

2003-05-01

School-accident reports document incidents that have resulted in children requiring assistance from staff in the education and healthcare sectors. This study was undertaken to investigate the collection and use of data by agencies concerned with the school-accident problem. Our aim was to determine if the annual collection and use of such a large body of data might be improved through better management procedures. Interviews were conducted with primary and secondary school staff in one education authority. Interviewees completed a questionnaire on accident activity and accident reporting in their school. In the healthcare sector, staff from the Schools' Office and the ambulance unit servicing the schools provided information on their collection and use of data. Our survey found that accident activity is usually a private matter for individual schools, shared to varying degrees with the education authority. Playgrounds, children's behaviour and footwear carried much of the blame for the injuries sustained. Staff generally accepted the current accident rates. The compilation of accident data by the Schools' Office, accident and emergency department, and ambulance service were compromised by deficiencies in computerization and computer software. The management and utilization of school-accident data could be improved by better collaboration within and between the education and healthcare agencies.

Chernobyl accident: causes and consequences (expert conclusion). Part 3. Chernobyl accident effect on Belarus

International Nuclear Information System (INIS)

Nesterenko, V.B.

1992-01-01

Expert conclusion is presented on the Chernobyl accident effect on Belarus. Problems of ground and food contamination, medical and biological radiation effects on the population are considered. Attention is paid to the radiation monitoring and radiometric gages. Scale of the damage for forestry and agriculture is described and recommendations on the agriculture is described and recommendations on the agricultural production and forest utilization at contaminated areas are given. 24 refs.; 4 figs.; 24 tabs

Airway accidents in critical care unit: A 3-year retrospective study in a Public Teaching Hospital of Eastern India

Science.gov (United States)

Dasgupta, Sugata; Singh, Shipti Shradha; Chaudhuri, Arunima; Bhattacharya, Dipasri; Choudhury, Sourav Das

2016-01-01

Background: Although tracheal tubes are essential devices to control and protect airway in a critical care unit (CCU), they are not free from complications. Aims: To document the incidence and nature of airway accidents in the CCU of a government teaching hospital in Eastern India. Methods: Retrospective analysis of all airway accidents in a 5-bedded (medical and surgical) CCU. The number, types, timing, and severity of airway accidents were analyzed. Results: The total accident rate was 19 in 233 intubated and/or tracheostomized patients over 1657 tube days (TDs) during 3 years. Fourteen occurred in 232 endotracheally intubated patients over 1075 endotracheal tube (ETT) days, and five occurred in 44 tracheostomized patients over 580 tracheostomy TDs. Fifteen accidents were due to blocked tubes. Rest four were unplanned extubations (UEs), all being accidental extubations. All blockages occurred during night shifts and all UEs during day shifts. Five accidents were mild, the rest moderate. No major accident led to cardiorespiratory arrest or death. All blockages occurred after 7th day of intubation. The outcome of accidents were more favorable in tracheostomy group compared to ETT group (P = 0.001). Conclusions: The prevalence of airway accidents was 8.2 accidents per 100 patients. Blockages were the most common accidents followed by UEs. Ten out of the 15 blockages and all 4 UEs were in endotracheally intubated patients. Tracheostomized patients had 5 blockages and no UEs. PMID:27076709

Ambulance traffic accidents in Taiwan.

Science.gov (United States)

Chiu, Po-Wei; Lin, Chih-Hao; Wu, Chen-Long; Fang, Pin-Hui; Lu, Chien-Hsin; Hsu, Hsiang-Chin; Chi, Chih-Hsien

2018-04-01

Ambulance traffic accidents (ATAs) are the leading cause of occupation-related fatalities among emergency medical service (EMS) personnel. We aim to use the Taiwan national surveillance system to analyze the characteristics of ATAs and to assist EMS directors in developing policies governing ambulance operations. A retrospective, cross-sectional and largely descriptive study was conducted using Taiwan national traffic accidents surveillance data from January 1, 2011 to October 31, 2016. Among the 1,627,217 traffic accidents during the study period, 715 ATAs caused 8 deaths within 24 h and 1844 injured patients. On average, there was one ATA for every 8598 ambulance runs. Compared to overall traffic accidents, ATAs were 1.7 times more likely to result in death and 1.9 times more likely to have injured patients. Among the 715 ATAs, 8 (1.1%) ATAs were fatal and 707 (98.9%) were nonfatal. All 8 fatalities were associated with motorcycles. The urban areas were significantly higher than the rural areas in the annual number of ATAs (14.2 ± 7.3 [7.0-26.7] versus 3.1 ± 1.9 [0.5-8.4], p = 0.013), the number of ATA-associated fatalities per year (0.2 ± 0.2 [0.0-0.7] versus 0.1 ± 0.1 [0.0-0.2], p = 0.022), and the annual number of injured patients (who needed urgent hospital visits) in ATAs (19.4 ± 7.3 [10.5-30.9] versus 5.2 ± 3.8 [0.9-15.3], p traffic accident reporting system should be built to provide EMS policy guidance for ATA reduction and outcome improvements. Copyright © 2018. Published by Elsevier B.V.

Safety in the Transport Sector

DEFF Research Database (Denmark)

Jørgensen, Kirsten

2012-01-01

In EU the transport sector has an incident rate of accidents at work at 40 pr 1000 employees. The Danish insurance company CODAN has insured a big part of this sector concerning transport of gods on shore. The purpose of the project is to document the safety problems in the sector and to develop...... a strategy for a preventive intervention in transport enterprises. The results will in the end be included in a new strategy for the insurance company and the transport sectores organization towards a better safety performance. The safety problems for the employees are the activities carried out by loading......, unloading or work with transport equipment carried out at many different work places. The main safety problems are falls, heavy lifting, poor ergonomic working conditions, hits or collisions with gods, equipments or falling objects, the traffic risk situations, work with animals and finally the risk...

Outcome of pregnancy in one Norwegian county 3 years prior to and 3 years subsequent to the Chernobyl accident

International Nuclear Information System (INIS)

Ulstein, M.; Skeie Jensen, T.; Irgens, L.M.; Lie, R.T.; Sivertsen, E.

1990-01-01

Pregnancy outcome was studied in a county in Norway 3 years prior to and 3 years subsequent to the Chernobyl nuclear plant accident on 26th April 1986. More detailed analyses have been performed for the 12 months prior to and subsequent to the accident. A significant increase in the spontaneous abortion rate the first year after the accident was followed by a slight decrease during the second and third years, but figures were still higher than the period prior to the accident. The rate of legal abortions was unchanged. During the entire observation period the number of births increased continuously, with the exception of a decrease in the last 2 months of 1986 and the first month of 1987. A higher incidence of spontaneous abortions was found for pregnancies conceived during the first 3 months after the accident. This increase in the spontaneous abortion rate is noteworthy, and more especially its long-term persistence, which cannot be the results of external radiation. The internal radiation from food polluted by radioactive fallout is a possible explanation. Changes in nutrition in order to avoid polluted food may also be of importance. (authors)

Outcome of pregnancy in one Norwegian county 3 years prior to and 3 years subsequent to the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Ulstein, M.; Skeie Jensen, T.; Irgens, L.M.; Lie, R.T.; Sivertsen, E. (Univ. of Bergen (Norway). Dept. of Obstetrics and Gynecology, and Medical Birth Registry)

1990-01-01

Pregnancy outcome was studied in a county in Norway 3 years prior to and 3 years subsequent to the Chernobyl nuclear plant accident on 26th April 1986. More detailed analyses have been performed for the 12 months prior to and subsequent to the accident. A significant increase in the spontaneous abortion rate the first year after the accident was followed by a slight decrease during the second and third years, but figures were still higher than the period prior to the accident. The rate of legal abortions was unchanged. During the entire observation period the number of births increased continuously, with the exception of a decrease in the last 2 months of 1986 and the first month of 1987. A higher incidence of spontaneous abortions was found for pregnancies conceived during the first 3 months after the accident. This increase in the spontaneous abortion rate is noteworthy, and more especially its long-term persistence, which cannot be the results of external radiation. The internal radiation from food polluted by radioactive fallout is a possible explanation. Changes in nutrition in order to avoid polluted food may also be of importance. (authors).

Application of the severe accident code ATHLET-CD. Modelling and evaluation of accident management measures (Project WASA-BOSS)

Energy Technology Data Exchange (ETDEWEB)

Wilhelm, Polina; Jobst, Matthias; Kliem, Soeren; Kozmenkov, Yaroslav; Schaefer, Frank [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Div. Reactor Safety

2016-07-01

The improvement of the safety of nuclear power plants is a continuously on-going process. The analysis of transients and accidents is an important research topic, which significantly contributes to safety enhancements of existing power plants. In case of an accident with multiple failures of safety systems core uncovery and heat-up can occur. In order to prevent the accident to turn into a severe one or to mitigate the consequences of severe accidents, different accident management measures can be applied. Numerical analyses are used to investigate the accident progression and the complex physical phenomena during the core degradation phase, as well as to evaluate the effectiveness of possible countermeasures in the preventive and mitigative domain [1, 2]. The presented analyses have been performed with the computer code ATHLET-CD developed by GRS [3, 4].

Accident selection methodology for TA-55 FSAR

International Nuclear Information System (INIS)

Letellier, B.C.; Pan, P.Y.; Sasser, M.K.

1995-01-01

In the past, the selection of representative accidents for refined analysis from the numerous scenarios identified in hazards analyses (HAs) has involved significant judgment and has been difficult to defend. As part of upgrading the Final Safety Analysis Report (FSAR) for the TA-55 plutonium facility at the Los Alamos National Laboratory, an accident selection process was developed that is mostly mechanical and reproducible in nature and fulfills the requirements of the Department of Energy (DOE) Standard 3009 and DOE Order 5480.23. Among the objectives specified by this guidance are the requirements that accident screening (1) consider accidents during normal and abnormal operating conditions, (2) consider both design basis and beyond design basis accidents, (3) characterize accidents by category (operational, natural phenomena, etc.) and by type (spill, explosion, fire, etc.), and (4) identify accidents that bound all foreseeable accident types. The accident selection process described here in the context of the TA-55 FSAR is applicable to all types of DOE facilities

HIV surveillance in needlestick accidents with health workers

Directory of Open Access Journals (Sweden)

Janete Lane Amadei

2010-12-01

Full Text Available Objective: To characterize the occurrence of needlestick accidents with health professionals submitted to rapid HIV tests. Methods: A descriptive, epidemiological study, carried out by notification of the occurrence of needlestick accidents in the Epidemiology Sector of the State Health Secretariat, in 2008. The following variables were assessed: gender, age, exposed biological material, type of exposure, source patient, and injured patient, progression of the case, accident situation, and use of personal protective equipment (PPE, 180 days serology and occupational area. Results: There have been reports of 143 accidents, prevailing in nursing, female, 20 to 30 years, involving the blood and biological material by percutaneous puncture. We found no standardization in the use of PPE. The HIV test revealed no positive cases. Conclusion: This study helped to characterize the occurrence of accidents reported in health care professionals and evaluate the protocol of care given. It also revealed non-contamination by HIV.

A reactivity accidents simulation of the Fort Saint Vrain HTGR

International Nuclear Information System (INIS)

Fainer, Gerson

1980-01-01

A reactivity accidents analysis of the Fort Saint Vrain HTGR was made. The following accidents were analysed 1) A rod pair withdrawal accident during normal operation, 2) A rod pair ejection accident, 3) A rod pair withdrawal accident during startup operations at source levels and 4) Multiple rod pair withdrawal accident. All the simulations were performed by using the BLOOST-6 nuclear code The steady state reactor operation results obtained with the code were consistent with the design reactor data. The numerical analysis showed that all accidents - except the first one - cause particle failure. (author)

Analysis of a station blackout transient at the Kori units 3/4

International Nuclear Information System (INIS)

Bang, Young Seok; Kim, Hho Jung

1992-01-01

A transient analysis of station blackout accident is performed to evaluate the plant specific capability to cope with the accident at the Kori Units 3/4. The RELAP5/MOD3/5m5 code and full three loop modelling scheme are used in the calculation. The leak flow from reactor coolant system due to a failure of reactor coolant pump seal following the accident is assumed to be 25 gpm and the turbine driven aux feedwater unavailable. As a result, it is found that no core uncovery occurs in the plant until 7100 sec following a station blackout, the steam generator has a decay heat removal capability until 3100 sec, and the natural circulation over the reactor coolant loop until the complete loop seal voiding are observed. And the Nuclear Plant Analyzer is used and found to be effective in improving the phenomenological understanding on the accident

Linking of FRAP-T, FRAPCON and RELAP-4 codes for transient analysis and accidents of light water reactors fuel rods

International Nuclear Information System (INIS)

Marra Neto, A.; Silva, A.T. e; Sabundjian, G.; Freitas, R.L.; Neves Conti, T. das.

1991-09-01

The computer codes FRAP-T, FRAPCON and RELAP-4 have been linked for the fuel rod behavior analysis under transients and hypothetical accidents in light water reactors. The results calculated by thermal hydraulic code RELAP-4 give input in file format into the transient fuel analysis code FRAP-T. If the effect of fuel burnup is taken into account, the fuel performance code FRAPCON should provide the initial steady state data for thhe transient analysis. With the thermal hydraulic boundary conditions provided by RELAP-4 (MOD3), FRAP-T6 is used to analyse pressurized water reactor fuel rod behavior during the blowdown phase under large break loss of coolant accident conditions. Two cases have been analysed: without and with initialization from FRAPCON-2 steady state data. (author)

49 CFR 837.3 - Published reports, material contained in the public accident investigation dockets, and accident...

Science.gov (United States)

2010-10-01

... 49 Transportation 7 2010-10-01 2010-10-01 false Published reports, material contained in the... OF RECORDS IN LEGAL PROCEEDINGS § 837.3 Published reports, material contained in the public accident... submitted, in writing, to the Public Inquiries Branch. Demands for specific published reports and studies...

Causes of Coal Mine Accidents in the World and Turkey.

Science.gov (United States)

Küçük, Filiz Çağla Uyanusta; Ilgaz, Aslıhan

2015-04-01

Occupational accidents and occupational diseases are common in the mining sector in Turkey and throughout the world. The most common causes of accidents in coal mining are firedamp and dust explosions, landslips, mine fires, and technical failures related to transport and mechanization. An analysis of occupational accidents in the consideration of social and economic factors will let understand the real causes behind these accidents, which are said to happen inevitably due to technical deficiencies or failures. Irregular working conditions, based on profit maximization and cost minimization, are related to strategic operational preferences and public policies. Proving that accidents in mines, where occupational health and safety measures are not implemented and inspections are not done properly or at all, are caused by the fact that production is imposed to be carried out in the fastest, cheapest, and most profitable way will allow us to take steps to prevent further mine accidents.

Management for the prevention of accidents from disused sealed radioactive sources

International Nuclear Information System (INIS)

2001-04-01

The objective of this report is to provide advice to sealed radiation source (SRS) users, radioactive waste operators, and other concerned public sectors on the measures to be taken to reduce the risk of accidents associated with disused or spent SRS. The report also explains policies as well as technical and administrative procedures to minimize the risk of accidents and to mitigate the consequences should an accident occur. The report emphasizes areas of high risk in handling disused or spent SRS in any form and condition to help to save health, life and financial resources

Kyshtym riddle: possible kind of the accident

International Nuclear Information System (INIS)

Ballereau, P.

1988-01-01

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

Studies of potential severe accidents in Finnish nuclear power plants. Quarterly report 3. quarter 1987

International Nuclear Information System (INIS)

Aro, Ilari.

1989-07-01

This thesis is based on six publications dealing with severe accident studies in Finnish nuclear power plants. Main emphasis has been put on general technical bases and methodologies applied in severe accident evaluation in Finland. As an example of the use of the analysis and evaluation methods, the analysis of one representative accident sequence, t otal loss of AC power , has been presented for both Finnish power plant types. This accident sequence is required to be analyzed in the Finnish safety guide YVL 2.2 which deals with transient and accident analyses as a basis of technical solutions at nuclear powr plants. Two different analysis methods, MAAP 3.0 and MARCH 3/STCP have been used for receiving as complete a picture as possible of the flow of events and for verifying the models to some extent. Besides the use of the two different models, the method of sensitivity analysis has been used for evaluating the effects of some important technical parameters on the accident flow. Finally, conclusions of the applicability of the two methods for analyzing severe accident sequences in Finnish plants have been discussed

Simulation of the SPE-4 small-break loss-of-coolant accident

International Nuclear Information System (INIS)

Cebull, P.; Hassan, Y.A.

1993-01-01

A small-break loss of coolant accident (SBLOCA) conducted at the PMK-2 integral test facility was analyzed using RELAP5/MOD3. 1. The experiment simulated a 7.4% break in the cold leg of a VVER-440/213-type nuclear power plant as part of the International Atomic Energy Agency's Fourth Standard Problem Exercise (SPE-4). The VVER design differs from pressurized water reactors (PWRS) of western origin, primarily in its use of horizontal steam generators, hot- and cold-leg loop seals, and safety injection tanks. Because of these differences, it will exhibit somewhat different transient behavior than most PWRS. The PMK-2 test facility, located at the KFKI Atomic Energy Research Institute (AEKI), is a scale model of the Paks nuclear power plant in Hungary with scaling factors of 1:2070 in power and volume and 1:1 in elevation. Primarily used to study SBLOCAs and natural circulation behavior of VVER reactors, it has been used in three previous SPEs

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)

Accident analysis in the water loop of the nuclear engineering department of IPEN using the RELAP4 code

International Nuclear Information System (INIS)

Fernandes Filho, T.L.

1980-06-01

A thermal-hydraulic analysis to describe the transient behavior in the water loop of the Nuclear Engineering Department of the Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, Brazil, was performed. Postulated accidents such as those resulting from (1) loss of coolant, (2) main pump failure and (3) power excursions, were studied. The computer code RELAP4/Mod.3 was employed as the principal tool of analysis. (Author) [pt

Safety climate and accidents at work

DEFF Research Database (Denmark)

Ajslev, Jeppe; Dastjerdi, Efat Lali; Dyreborg, Johnny

2017-01-01

Aim: Occupational safety climate is utilized as a way to measure the risk of accidents and injuries at work. This study investigates which factors are associated with safety climate and accidents at work. Methods: In the 2012 round of the Danish Work Environment and Health Study, 15,144 workers...... from the general working population of Denmark replied to questions about safety climate and accidents at work. Mutually adjusted logistic regression analyses determined the association between variables. Results: Within the last year, 5.7% had experienced an accident resulting in sickness absence....... The number of safety climate problems was progressively associated with the odds ratio (OR) for accidents. For one safety climate problem the OR for accidents was 2.01 (95% CI 1.67–2.42), for four or more safety climate problems the OR was 4.57 (95% CI 3.64–5.74). Young workers (18–24 years) had higher odds...

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

Rates of thoracic trauma and mortality due to accidents in Brazil

International Nuclear Information System (INIS)

Cury, Francisco; Baitello, Andre Luciano; Echeverria, Rodrigo Florencio; Espada, Paulo Cesar; Godoy, Jose Maria Pereira de

2009-01-01

To report on the causes of trauma, indexes of trauma, and mortality related to thoracic trauma in one region of Brazil. This prospective study was performed at the Regional Trauma Center in Syo Josi do Rio Preto over a 1-year period, from 1 st July 2004 to 30 th June 2005. We included all patients attending the center's emergency room with thoracic trauma and an anatomic injury scale (AIS) > - 2. We collected data using a protocol completed on arrival in hospital utilizing the AIS. We studied the types of accidents as well as the mortality and the AIS scores. Prevalence rates were calculated and the paired t-test and logistic regression were employed for the statistical analysis.There were a total of 373 casualties with AIS > - 2 and there were 45 (12%) deaths. The causes of thoracic trauma among the 373 casualties were as follows: 91 (24.4%) car crashes, 75 (20.1%) falls, 46 (12.3%) motorbike accidents, 40 (10.7%) stabbings, 22 (5.9%) accidents involving pedestrians, 21 (5.6%) bicycle accidents, 17 (4.6%) shootings, and 54 (14.5%) other types of accident. The severity of the injuries was classified according to the AIS: 224 (60%) were grade 2, 101 (27%) were grade 3, 27 (7.2%) were grade 4, 18 (4.9%) were grade 5, and 3 were (0.8%) grade 6. With respect to thoracic trauma, pedestrians involved in accidents and victims of shootings had mortality rates that were significantly higher than that of those involved in other types of accidents. Road accidents are the main cause of thoracic injury, with accidents involving pedestrians and shootings being associated with a greater death rate. (author)

Fukushima. The accident sequence and important causes. Pt. 2/3; Fukushima. Unfallablauf und wesentliche Ursachen. T. 2/3

Energy Technology Data Exchange (ETDEWEB)

Pistner, Christoph [Oeko-Institut e.V., Darmstadt (Germany). Bereich Nukleartechnik und Anlagensicherheit

2013-07-01

In this part on the accident sequence in the NPP Fukushima Daiichi on March 11, 2011 the important safety systems of a nuclear power plant are described, including the design of a nuclear boiling water reactor with Mark-II type containment, the high-pressure injection system and the systems for afterheat removal. The chronology of the accident progress in the NPP units 1-3 is described. The units 4-6 were shutdown due to revision work. Due to the earthquake an electric power transformation station close to the NPP site and the power poles were destroyed, the redundant power supply of the neighboring electricity supplier Tohoku did not work. All emergency diesel generators were flooded and destroyed resulting in the so-called station blackout. Firefighting trucks and materials for radiation protection and the infrastructure at the NPP site were destroyed. The release of radioactivity induced a severe contamination of the reactor site.

Causes of Coal Mine Accidents in the World and Turkey

Science.gov (United States)

Küçük, Filiz Çağla Uyanusta; Ilgaz, Aslıhan

2015-01-01

Occupational accidents and occupational diseases are common in the mining sector in Turkey and throughout the world. The most common causes of accidents in coal mining are firedamp and dust explosions, landslips, mine fires, and technical failures related to transport and mechanization. An analysis of occupational accidents in the consideration of social and economic factors will let understand the real causes behind these accidents, which are said to happen inevitably due to technical deficiencies or failures. Irregular working conditions, based on profit maximization and cost minimization, are related to strategic operational preferences and public policies. Proving that accidents in mines, where occupational health and safety measures are not implemented and inspections are not done properly or at all, are caused by the fact that production is imposed to be carried out in the fastest, cheapest, and most profitable way will allow us to take steps to prevent further mine accidents. PMID:29404108

Fatal accidents analysis in Peruvian mining industry

International Nuclear Information System (INIS)

Candia, R. C.; Hennies, W. T.; Azevedo, R. c.; Almeida, I.G.; Soto, J. F.

2010-01-01

Although reductions in the tax of injuries and accidents have been observed in recent years, Mining is still one of the highest risks industries. The basic causes for occurrence of fatalities can be attributed to unsafe conditions and unsafe acts. In this scene is necessary to identify safety problems and to aim the effective solutions. On the other hand, the developing countries dependence on primary industries as mining is evident. In the Peruvian economy, approximately 16% of the GNP and more than 50% of the exportations are due to the mining sector, detaching its competitive position in the worldwide mining. This paper presents fatal accidents analysis in the Peruvian mining industry, having as basis the register of occurred fatal accidents since year 2000 until 2007, identifying the main types of accidents occurred. The source of primary information is the General Mining Direction (DGM) of the Peruvian Mining and Energy Ministry (MEM). The majority of victims belongs to tertiary contractor companies that render services for mine companies. The results of the analysis show also that the majority of accidents happened in the underground mines, and that it is necessary to propose effective solutions to manage risks, aiming at reducing the fatal accidents taxes. (Author)

An exercise on clean-up actions in an urban environment after a nuclear accident. Report of the NKS EKO 4 programme

International Nuclear Information System (INIS)

French, S.; Haemaelaeinen, R.; Naadland, E.; Roed, J.; Salo, A.; Sinkko, K.

1996-03-01

The EKO 4/c working group of the environmental effects and emergency preparedness programme (EKO) of the Nordic Nuclear Safety Research (NKS) organised a decision conference on August 30th and 31st, 1995 in Stockholm, Sweden. The meeting was designed to be attended by those responsible for planning and deciding on protective actions in the Nordic countries after a nuclear accident. Issues concerning clean-up strategies in an urban environment after a hypothetical and very severe reactor accident were discussed at the meeting. The objectives of the meeting were to provide a shared understanding between the decision makers and the radiation protection community on concerns and issues related to decision on protective actions after a nuclear accident. (6 refs., 2 figs., 3 tabs.)

Experience in construction of new safe confinement over ChNPP-4 damages in beyond design-basis accident: view in 30 year

International Nuclear Information System (INIS)

Nosovskij, A.V.

2016-01-01

Many organizations and institutions participated in the elimination of ChNPP-4 accident. However, the main efforts on conservation of the damaged unit and ChNPP-3 commissioning were performed in 1986-1987 by experts of the enterprises and organizations of the Ministry of Medium Machine Building of the Soviet Union, who have been sent to the staff of the specially created Construction Administration US-605. The paper presents the activity of US-605 experts, describes administrative and technical measures of radiation safety during construction of the Shelter in difficult radiation conditions. Such efforts enabled accumulation of significant and unique experience in mitigation of severe accident consequences, which shall be used to prevent any nuclear accidents and eliminate their consequences

An exercise on clean-up actions in an urban environment after a nuclear accident. Report of the NKS EKO 4 programme

Energy Technology Data Exchange (ETDEWEB)

French, S. [ed.] [Leeds Univ. (United Kingdom). School of Computer Studies; Finck, R. [ed.] [Swedish Radiation Protection Inst., Stockholm (Sweden); Haemaelaeinen, R. [ed.] [Helsinki Univ. of Technology, Espoo (Finland); Naadland, E. [ed.] [Norwegian Radiation Protection Authority, Oesteraas (Norway); Roed, J. [ed.] [Risoe National Lab., Roskilde (Denmark); Salo, A. [ed.] [Helsinki (Finland); Sinkko, K. [ed.] [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland)

1996-03-01

The EKO 4/c working group of the environmental effects and emergency preparedness programme (EKO) of the Nordic Nuclear Safety Research (NKS) organised a decision conference on August 30th and 31st, 1995 in Stockholm, Sweden. The meeting was designed to be attended by those responsible for planning and deciding on protective actions in the Nordic countries after a nuclear accident. Issues concerning clean-up strategies in an urban environment after a hypothetical and very severe reactor accident were discussed at the meeting. The objectives of the meeting were to provide a shared understanding between the decision makers and the radiation protection community on concerns and issues related to decision on protective actions after a nuclear accident. (6 refs., 2 figs., 3 tabs.).

Accident prevention programme

International Nuclear Information System (INIS)

1978-01-01

This study by the Steel Industry Safety and Health Commission was made within the context of the application by undertakings of the principles of accident and disease prevention previously adopted by the said Commission. It puts forward recommendations for the effective and gradual implementation of a programme of action on occupational health and safety in the various departments of an undertaking and in the undertaking as a whole. The methods proposed in this study are likely to be of interest to all undertakings in the metallurgical industry and other industrial sectors

PROPUESTA PARA LA EVALUACIÓN DEL IMPACTO ECONÓMICO DE LA SINIESTRALIDAD LABORAL EN EL SECTOR DE LA CONSTRUCCIÓN PROPOSAL FOR THE EVALUATION OF THE ECONOMIC IMPACT OF OCCUPATIONAL ACCIDENTS IN THE CONSTRUCTION INDUSTRY

Directory of Open Access Journals (Sweden)

Gloria Isabel Carvajal Peláez

2011-12-01

Full Text Available Los accidentes laborales suponen importantes costos humanos y económicos para la empresa, el accidentado y la sociedad. Generalmente, representan una gran repercusión económica negativa para las empresas del sector de la construcción, las cuales soportan un costo mayor del que se refleja debido a la gran cantidad de variables ocultas que se desconocen. Dado que hasta ahora la evaluación de los costos generados por los accidentes laborales ha tenido lugar mediante el desarrollo de métodos muy dispares entre sí, y según Durán [1], no se ha hecho ningún tipo de evaluación económica que estime de manera exhaustiva el costo de los daños a la salud relacionados con el trabajo, en esta comunicación, se presenta mediante un modelo matemático de aplicación al sector de la construcción español, que el costo de los accidentes laborales es el consumo de recursos materiales y humanos derivados del aseguramiento, la prevención y los siniestros.Work-related accidents involve significant human and economic costs for the companies, people, and society. Said accidents usually represent a great negative economic impact for the construction industries, which support a higher cost than reflected due to the large amount of hidden variables are unknown. Until now, the evaluation of the costs generated by labor accidents has been based on the development of very different methods and, as Duran [1] has not made any kind of economic assessment that comprehensively considers the economic cost of damage to health associated with work, this paper present a mathematical model applicable to the Spain construction industry, that the cost of labor accidents, is the consumption of material and human resources derived from insurance, prevention and accidents.

NPP Krsko Severe Accident Management Guidelines Implementation

International Nuclear Information System (INIS)

Basic, I.; Krajnc, B.; Bilic-Zabric, T.; Spiler, J.

2002-01-01

Severe Accident Management is a framework to identify and implement the Emergency Response Capabilities that can be used to prevent or mitigate severe accidents and their consequences. The USA NRC has indicated that the development of a licensee plant specific accident management program will be required in order to close out the severe accident regulatory issue (Ref. SECY-88-147). Generic Letter 88-20 ties the Accident management Program to IPE for each plant. The SECY-89-012 defines those actions taken during the course of an accident by the plant operating and technical staff to: 1) prevent core damage, 2) terminate the progress of core damage if it begins and retain the core within the reactor vessel, 3) maintain containment integrity as long as possible, and 4) minimize offsite releases. The subject of this paper is to document the severe accident management activities, which resulted in a plant specific Severe Accident Management Guidelines implementation. They have been developed based on the Krsko IPE (Individual Plant Examination) insights, Generic WOG SAMGs (Westinghouse Owners Group Severe Accident Management Guidances) and plant specific documents developed within this effort. Among the required plant specific actions the following are the most important ones: Identification and documentation of those Krsko plant specific severe accident management features (which also resulted from the IPE investigations). The development of the Krsko plant specific background documents (Severe Accident Plant Specific Strategies and SAMG Setpoint Calculation). Also, paper discusses effort done in the areas of NPP Krsko SAMG review (internal and external ), validation on Krsko Full Scope Simulator (Severe Accident sequences are simulated by MAAP4 in real time) and world 1st IAEA Review of Accident Management Programmes (RAMP). (author)

Reactivity initiated accident test series Test RIA 1-4 fuel behavior report

International Nuclear Information System (INIS)

Cook, B.A.; Martinson, Z.R.

1984-09-01

This report presents and discusses results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Nine preirradiated fuel rods in a 3 x 3 bundle configuration were subjected to a power burst while at boiling water reactor hot-startup system conditions. The test resulted in estimated axial peak, radial average fuel enthalpies of 234 cal/g UO 2 on the center rod, 255 cal/g UO 2 on the side rods, and 277 cal/g UO 2 on the corner rods. Test RIA 1-4 was conducted to investigate fuel coolability and channel blockage within a bundle of preirradiated rods near the present enthalpy limit of 280 cal/g UO 2 established by the US Nuclear Regulatory Commission. The test design and conduct are described, and the bundle and individual rod thermal and mechanical responses are evaluated. Conclusions from this final test and the entire PBF RIA Test Series are presented

Cost analysis and financial risk profile for severe reactor accidents at Waterford-3

International Nuclear Information System (INIS)

Cutbush, J.D.; Abbott, E.C.; Carpenter, W.L. Jr.

1992-01-01

To support Louisiana Power and Light Company (LP and L) in determining an appropriate level of nuclear property insurance for Waterford Steam Electric Station, Unit 3 (Waterford-3), ABZ, Incorporated, performed a series of cost analyses and developed a financial risk profile. This five-month study, conducted in 1991, identified the potential Waterford-3 severe reactor accidents and described each from a cleanup perspective, estimated the cost and schedule to cleanup from each accident, developed a probability distribution of associated financial exposure, and developed a profile of financial risk as a function of insurance coverage

Occupational accidents in the Netherlands: incidence, mental harm, and their relationship with psychosocial factors at work

NARCIS (Netherlands)

Klauw, M. van der; Oude Hengel, K.; Bakhuys Roozeboom, M.M.C.; Koppes, L.; Venema, A.

2016-01-01

This study investigated the incidence of mental harm due to occupational accidents and the relation between psychosocial factors at work and the occurrence of occupational accidents in the Netherlands for the construction industry and health and welfare sector. Analyses revealed that occupational

Safety in New Zealand's adventure tourism industry: the client accident experience of adventure tourism operators.

Science.gov (United States)

Bentley , T A; Page, S J; Laird, I S

2000-01-01

Injuries and fatalities among participants of adventure tourism activities have the potential to seriously impact on New Zealand's tourism industry. However, the absence of statistics for tourist accidents in New Zealand, and the lack of detailed academic research into adventure tourism safety, means the extent of the problem is unknown. The aims of the present study were to determine the incidence of client injuries across a range of adventure tourism activity sectors, and to identify common accident events and contributory risk factors. A postal questionnaire survey of New Zealand adventure tourism operators was used. Operators were asked to provide information related to their business; the number of recorded client injuries during the preceding 12 month period, January to December 1998; common accident and injury events associated with their activity; and perceived risk factors for accidents in their sector of the adventure tourism industry. The survey was responded to by 142 New Zealand adventure tourism operators. The operators' reported client injury experience suggests the incidence of serious client injuries is very low. Highest client injury incidence rates were found for activities that involved the risk of falling from a moving vehicle or animal (e.g., cycle tours, quad biking, horse riding, and white-water rafting). Slips, trips, and falls on the level were common accident events across most sectors of the industry. Perceived accident/incident causes were most commonly related to the client, and in particular, failure to attend to and follow instructions. The prevalence of client injuries in activity sectors not presently covered by government regulation, suggests policy makers should look again at extending codes of practice to a wider range of adventure tourism activities. Further research considering adventure tourism involvement in overseas visitor hospitalized injuries in New Zealand, is currently in progress. This will provide supporting evidence

Analysis of the metallic containment integrity of Angra 2/3 reactor under the effects of the design basis accident

International Nuclear Information System (INIS)

Costa, J.R.

1981-06-01

The application of Condru 4 computer code, developed to determine the maximum values of pressure and temperature that occur inside the metallic containment building of PWR nuclear power plants, in case of a hypothetic accident - LOCA - considered as a Design Basic Accident - DBA. The hypothesis, input and results for the simulation of a loss of coolant in the hot leg of the Angra-2/3 reactors, considered as the most critical case for that Kind of project, are presented. The analysis was made with input provided by the manufacturer. (Author) [pt

Severe accident tests and development of domestic severe accident system codes

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)

Severe accident tests and development of domestic severe accident system codes

International Nuclear Information System (INIS)

2013-01-01

According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)

Accidents - Chernobyl accident; Accidents - accident de Tchernobyl

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)

Safety and health practice among laboratory staff in Malaysian education sector

Science.gov (United States)

Husna Che Hassan, Nurul; Rasdan Ismail, Ahmad; Kamilah Makhtar, Nor; Azwadi Sulaiman, Muhammad; Syuhadah Subki, Noor; Adilah Hamzah, Noor

2017-10-01

Safety is the most important issue in industrial sector such as construction and manufacturing. Recently, the increasing number of accident cases reported involving school environment shows the important of safety issues in education sector. Safety awareness among staff in this sector is crucial in order to find out the method to prevent the accident occurred in future. This study was conducted to analyze the knowledge of laboratory staff in term of safety and health practice in laboratory. Survey questionnaires were distributing among 255 of staff laboratory from ten District Education Offices in Kelantan. Descriptive analysis shows that the understanding of safety and health practice are low while doing some job activities in laboratory. Furthermore, some of the staff also did not implemented safety practice that may contribute to unplanned event occur in laboratory. Suggestion that the staff at laboratory need to undergo on Occupational Safety and Health training to maintain and create safe environment in workplaces.

Characteristics of worker accidents on NYSDOT construction projects.

Science.gov (United States)

Mohan, Satish; Zech, Wesley C

2005-01-01

This paper aims at providing cost-effective safety measures to protect construction workers in highway work zones, based on real data. Two types of accidents that occur in work zones were: (a) construction work area accidents, and (b) traffic accidents involving construction worker(s). A detailed analysis of work zone accidents involving 36 fatalities and 3,055 severe injuries to construction workers on New York State Department of Transportation (NYSDOT) construction projects from 1990 to 2001 established that five accident types: (a) Struck/Pinned by Large Equipment, (b) Trip or Fall (elevated), (c) Contact w/Electrical or Gas Utility, (d) Struck-by Moving/Falling Load, and (e) Crane/Lift Device Failure accounted for nearly 96% of the fatal accidents, nearly 63% of the hospital-level injury accidents, and nearly 91% of the total costs. These construction work area accidents had a total cost of $133.8 million. Traffic accidents that involve contractors' employees were also examined. Statistical analyses of the traffic accidents established that five traffic accident types: (a) Work Space Intrusion, (b) Worker Struck-by Vehicle Inside Work Space, (c) Flagger Struck-by Vehicle, (d) Worker Struck-by Vehicle Entering/Exiting Work Space, and (e) Construction Equipment Struck-by Vehicle Inside Work Space accounted for nearly 86% of the fatal, nearly 70% of the hospital-level injury and minor injury traffic accidents, and $45.4 million (79.4%) of the total traffic accident costs. The results of this paper provide real statistics on construction worker related accidents reported on construction work zones. Potential preventions based on real statistics have also been suggested. The ranking of accident types, both within the work area as well as in traffic, will guide the heavy highway contractor and owner agencies in identifying the most cost effective safety preventions.

Summary and evaluation: fuel dynamics loss-of-flow experiments (tests L2, L3, and L4)

International Nuclear Information System (INIS)

Barts, E.W.; Deitrich, L.W.; Eberhart, J.G.; Fischer, A.K.; Meek, C.C.

1975-09-01

Three similar experiments conducted to support the analyses of hypothetical LMFBR unprotected-loss-of-flow accidents are summarized and evaluated. The tests, designated L2, L3, and L4, provided experimental data against which accident-analysis codes could be compared, so as to guide further analysis and modeling of the initiating phases of the hypothetical accident. The tests were conducted using seven-pin bundles of mixed-oxide fuel pins in Mark-II flowing-sodium loops in the TREAT reactor. Test L2 used fresh fuel. Tests L3 and L4 used irradiated fuel pins having, respectively, ''intermediate-power'' (no central void) and ''high-power'' (fully developed central void) microstructure. 12 references

Integration between environmental management and strategic planning in the oil and gas sector

International Nuclear Information System (INIS)

Magrini, Alessandra; Lins, Luiz dos Santos

2007-01-01

For activities that have a high possibility of causing environmental accidents, like in the oil and gas sector, it is reasonable to expect the environmental management to be an important variable within the company's strategic planning. However, this is not always true. In some cases, a change in the companies' attitude, abandoning a reactive position and assuming a proactive one, only happens upon the occurrence of serious environmental accidents with strong repercussion in the media. For the company that was the object of study, these accidents gave rise to deep changes in its environmental management, culminating in investments of approximately US$ 2.6 billion in environment, health and security, from 2000 to 2004. This was the highest amount to date invested on these areas by an oil company. This case study seeks to discuss the integration between environmental management and strategic planning in the oil and gas sector over a period of 10 years (from 1995 to 2004) in order to make a contextual analysis of the period before and after the environmental accidents possible

Obstructive sleep apnoea syndrome as a cause of road traffic accidents.

Science.gov (United States)

Aguiar, M; Valença, J; Felizardo, M; Caeiro, F; Moreira, S; Staats, R; Bugalho de Almeida, A A

2009-01-01

Several studies have demonstrated that obstructive sleep apnoea syndrome (OSAS) patients have a higher rate of road traffic accidents. Our study aimed to analyse any differences in OSAS patients between those who reported having had road traffic accidents and/or near misses and those who did not. We studied 163 patients with OSAS (apnoea- hypopnoea index (AHI)>10/h) diagnosed using nocturnal polysomnography (NPSG), all drivers, 18.4% of whom drove for a living. Patients were asked at their first clinical interview to self-report road traffic accidents and/or near misses over the past 3 years which had been caused by abnormal daytime drowsiness. This allowed patients to be divided into two groups, those who had had road traffic accidents and/or near misses and those who had not. Both were compared as to age, body mass index (BMI), Epworth Sleepiness Scale (ESS), daytime PaO2 and PaCO2, Functional Outcomes of Sleep Questionnaire (FOSQ) test and NPSG data. This latter was total sleep time (TTS), sleep efficiency, sleep stages, arousal index (ARI), AHI, minimal and average SaO2, % of time with SaO2 TDAH) (T test). Group I (no road traffic accidents) No=89 patients; group II (road traffic accidents) No=74 patients. Age (years) was 57.6+/-11.8 vs. 54.7+/-10.9 (ns); male gender, 75% vs. 78.4%; ESS, 12.3+/-5.4 vs. 17.6+/-4.3 (pTDAH (minutes), 98.5+/-63.7 vs. 133.3+/-83.2 (p=0,005). In our experience patients who had road traffic accidents and/or near misses had a more severe OSAS, with higher AHI, excessive daytime sleepiness and lower quality of life.

Reactivity initiated accident analyses for the safety assessment of upgraded JRR-3

International Nuclear Information System (INIS)

Harami, Taikan; Uemura, Mutsumi; Ohnishi, Nobuaki

1984-08-01

JRR-3, currently a heavy water moderated and cooled 10 MW reactor, is to be upgraded to a light water moderated and cooled, heavy water reflected 20 MW reactor. This report describes the analytical results of reactivity initiated accidents for the safety assessment of upgraded JRR-3. The following five cases have been selected for the assessment; (1) uncontrolled control rod withdrawal from zero power, (2) uncontrolled control rod withdrawal from full power, (3) removal of irradiation samples, (4) increase of primary coolant flow, (5) failure of heavy water tank. Parameter studies have been made for each of the above cases to cover possible uncertainties. All analyses have been made by a computer code EUREKA-2. The results show that the safety criteria for upgraded JRR-3 are all met and the adequacy of the design is confirmed. (author)

Lessons from Chernobyl post-accident management

International Nuclear Information System (INIS)

Schneider, T.

2012-01-01

The Chernobyl accident has shown that the long-term management of its consequences is not straightforward. The management of the consequences has revealed the complexity of the situation to deal with. The long-term contamination of the environment has affected all the dimensions of the daily life of the inhabitants living in affected territories: health, environment, social life, education, work, distribution of foodstuffs and commodities... The experience from the Chernobyl accident shows 4 key issues that may be beneficial for the populations living in territories affected by the Fukushima accident: 1) the direct involvement of the inhabitants in their own protection, 2) the radiation monitoring system and health surveillance at the local level, 3) to develop a practical radiation protection culture among the population, and 4) the setting up of economic measures to favour the local development. (A.C.)

Medical experience: Chernobyl and other accidents

International Nuclear Information System (INIS)

Densow, D.; Kindler, H.; Fliedner, T.M.

2000-01-01

A radiation accident can be defined as an involuntary relevant exposure of man to ionising radiation or radioactive material. Provided one of the ensuing criteria is met with at least one person involved in an excursion of ionising radiation and or radioactive material, the respective incident can be considered a radiation accident in accordance with ICRP, NCRP (US), and WHO: ≥0.25 Sv total body irradiation with lesions of the rapidly dividing tissues; ≥6 Sv cutaneous and local irradiation; ≥0.4 Sv local irradiation of other organ systems through external sources; incorporation equal to or in excess of more than half of the maximum permissible organ burden; and medical accidents meeting one of the above criteria. Several actions have been taken to categorise radiation accidents in order to learn from previous accidents in terms of both managerial and medical experience. For this presentation three approaches will be discussed concerning their relevance to the individual treatment and risk management. This will be obtained by applying three classification schemes to all known radiation accidents: 1. classification with respect to the accident mechanism, 2. classification concerning the radiation injury, and 3. classification concerning the extent of the accident. In a fourth chapter the efficacy of bone marrow transplantation will briefly be commented on based on the accumulated experience of about 400 radiation accidents world-wide. (author)

RJHS 3(4b).cdr

African Journals Online (AJOL)

ABEOLUGBENGAS

2013-08-08

Aug 8, 2013 ... respondents had an accident at the workplace while 4% had injury, 60% had ... Department of Community Health, Federal Medical Centre, Owo, Ondo State, Nigeria. Res. ... fluids is a common problem among health care.

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)

Automobile Accidents Attended by Mobile Emergency Care Service

Directory of Open Access Journals (Sweden)

Ana Virgínia Gomes Barros

2017-05-01

Full Text Available Background: Automobile accidents are increasing every day and are becoming a serious public health problem due to the high morbidity and mortality rate. The goal of the current study was to characterise the traffic accidents attended by the Mobile Emergency Care Service (MECS in Ibiara, PB. Methods: This exploratory, descriptive, documentary study adopted a quantitative approach and analysis of data. The population consisted of all victims of traffic accidents attended by MECS in the city of Ibiara, PB, from June 2015 to June 2016. The following variables were studied: age, gender, time and day of the week the accident occurred, nature of the incident, substance ingested by the victim, wearing personal protective equipment (PPE or not, the anatomical lesions on the victim and the body regions hit during the accident. Results: The sample consisted of 49 accident victims, and the majority (81.6% were male, predominately 30 to 59 years. Events occurring at night (63.3% and during the week (65.3% predominated. The most frequent type of accident was motorcycle fall (71.4%, with almost half having consumed alcohol (46.9% and most not wearing PPE (77.6%. The regions of the body most affected were the lower limbs (67.3% and upper limbs (53.1%. Conclusion: The main factor/cause of these accidents was due to imprudence and violation of traffic laws, highlighting the need to invest in traffic education policies, to direct campaigns for the prevention of traffic accidents, as well as expand the surveillance of traffic laws by authorities.

3-Dimensional Methodology for the Control Rod Ejection Accident Analysis Using UNICORNTM

International Nuclear Information System (INIS)

Jang, Chan-su; Um, Kil-sup; Ahn, Dawk-hwan; Kim, Yo-han; Sung, Chang-kyung; Song, Jae-seung

2006-01-01

The control rod ejection accident has been analyzed with STRIKIN-II code using the point kinetics model coupled with conservative factors to address the three dimensional aspects. This may result in a severe transient with very high fuel enthalpy deposition. KNFC, under the support of KEPRI and KAERI, is developing 3-dimensional methodology for the rod ejection accident analysis using UNICORNTM (Unified Code of RETRAN, TORC and MASTER). For this purpose, 3-dimensional MASTER-TORC codes, which have been combined with the dynamic-link library by KAERI, are used in the transient analysis of the core and RETRAN code is used to estimate the enthalpy deposition in the hot rod

Nuclear Reactor RA Safety Report, Vol. 13, Causes of possible accidents

International Nuclear Information System (INIS)

1986-11-01

This volume includes the analysis of possible accidents on the RA research reaktor. Any unwanted action causing decrease of integrity of any of the reactor safety barriers is considered to be a reactor accident. Safety barriers are: fuel element cladding, reactor vessel, biogical shield, and reactor building. Reactor accidents can be classified in four categories: (1) accidents caused by reactivity changes; (2) accidents caused by mis function of the cooling system; (3) accidents caused by errors in fuel management and auxiliary systems; (4) accidents caused by natural or other external disasters. The analysis of possible causes of reactor accidents includes the analysis of possible impacts on the reactor itself and the environment [sr

Mitigation of severe accidents in AREVA's Gen 3+ nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fischer, M., E-mail: manfred.fischer@areva.com; Henning, A.; Surmann, R.

2014-04-01

The current AREVA Gen 3+ PWR designs (EPR™ and ATMEA1) are based on the proven defense-in-depth safety concepts inherited from their predecessors, the French “N4” and the German “Konvoi” reactors. Complemented by specific enhancements, including higher redundancy and diversity as well as the use of passive systems, this leads to very low values of the core damage frequency (CDF). Notwithstanding this very low probability, dedicated design measures have been implemented to improve the response of the plant in case of a postulated severe accident (SA) with core melting. This way not only the frequency of large-early-releases (LERF) but also the related radiological consequences are drastically reduced. Situations that potentially lead to high loads that can challenge the short-term integrity of the containment, like RPV melt-through under high pressure, energetic hydrogen/steam explosions, as well as long-term containment failure caused by internal over-pressure are avoided by a combination of preventive measures and dedicated systems. At the example of the EPR{sup TM}, the paper gives an overview of the severe accident mitigation strategy and the related measures and systems of AREVAs current Gen 3+ reactors, with special focus on the function of the core melt stabilization system.

Aspects epidémiologiques des accidents domestiques de l'enfant à ...

African Journals Online (AJOL)

2. Clinics in Mother and Child Health. Tableau 1: Types d'accidents domestiques retrouvés. Type d'accident. Nombre. Pourcentage. Chute. 26. 46,4. Intoxication au pétrole. 9. 16,1. Brûlure. 5. 8,9. Coupure. 5. 8,9. Corps étranger. 4. 7,1. Collusion avec un objet contondant. 4. 7,1. Morsure. 2. 3,7. Suffocation. 1. 1,8. Total. 56.

Construction accidents: identification of the main associations between causes, mechanisms and stages of the construction process.

Science.gov (United States)

Carrillo-Castrillo, Jesús A; Trillo-Cabello, Antonio F; Rubio-Romero, Juan C

2017-06-01

To identify the most frequent causes of accidents in the construction sector in order to help safety practitioners in the task of prioritizing preventive actions depending on the stage of construction. Official accident investigation reports are analysed. A causation pattern is identified with the proportion of causes in each of the different possible groups of causes. Significant associations of the types of causes with accident mechanisms and construction stages have been identified. Significant differences have been found in accident causation depending on the mechanism of the accident and the construction stage ongoing. These results should be used to prioritize preventive actions to combat the most likely causes for each accident mechanism and construction stage.

Response to the Chernobyl accident in Japan

International Nuclear Information System (INIS)

Anon.

1986-01-01

The worst nuclear accident in history happened at No.4 unit of the Chernobyl Atomic Power Station in USSR. Since the Chernobyl accident, a number of measures have been introduced in many countries, including the reconsideration of programs for construction and operation of nuclear power plants. In Japan, the press and television first reported the accident on April 29. The next day, all the relevant governmental agencies began to collect and analyze information in order to prepare possible countermeasures. The Nuclear Safety Commission issued a statement covering three points: 1) the radioactive substances released by the accident will have virtually no influence on the health of people in Japan, 2) a Special Committee on the Chernobyl Atomic Power Station Accident will be established, and 3) the Soviet government must provide all detailed information about the accident as soon as it is available. On April 30, the Committee on Radioactivity decided to increase radioactivity observations by the Science and Technology Agency, the Defence Agency, and the Meteorological Agency. On the same day, the Ministry of International Trade and Industry set up a survey committee for the Chernobyl accident with the responsibility of collecting and analyzing information about the accident. A review is also made in this article as to how the Japanese media reported the accident and how people reacted on reading the newspapers and watching TV on the accident. (Nogami, K.)

Bounding Accident Analysis for LLNL BSL-3 Facility

Energy Technology Data Exchange (ETDEWEB)

Johnson, Mark [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2010-09-14

The conclusion of this evaluation is that the consequence estimates in the EA can be reproduced using a public-accessible Gaussian plume-dispersion model and conservative modeling assumptions consistent with the accident scenario postulated in the EA. Also, the potential consequences to the public for the postulated accident would be far below the minimum infectious dose of one organism.

The accidents due to ionizing radiations - the situation on a half century

International Nuclear Information System (INIS)

2007-02-01

This report takes stock updated in 2006, serious accidents occurred in the four sectors in civil, industrial, medical and military. Its goal is to provide an explanatory and critical review of the most representative accident that caused serious harm to victims. The report analyses for each accident, and whenever reliable data exist, the reasons for its occurrence, consequences for victims and possibly to the environment, remedial actions that have been made and medical treatments when they were innovative. Using a combination of accidents with common features, the report offers key lessons to be learned from these tragic events. This report is intended for practitioners of radiation protection in general and does not target particular experts in any technical or medical specialty. (N.C.)

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

A preliminary study for the implementation of general accident management strategies

Energy Technology Data Exchange (ETDEWEB)

Yang, Soo Hyung; Kim, Soo Hyung; Jeong, Young Hoon; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1998-12-31

To enhance the safety of nuclear power plants, implementation of accident management has been suggested as one of most important programs. Specially, accident management strategies are suggested as one of key elements considered in development of the accident management program. In this study, generally applicable accident management strategies to domestic nuclear power plants are identified through reviewing several accident management programs for the other countries and considering domestic conditions. Identified strategies are as follows; 1) Injection into the Reactor Coolant System, 2) Depressurize the Reactor Coolant System, 3) Depressurize the Steam Generator, 4) Injection into the Steam Generator, 5) Injection into the Containment, 6) Spray into the Containment, 7) Control Hydrogen in the Containment. In addition, the systems and instrumentation necessary for the implementation of each strategy are also investigated. 11 refs., 3 figs., 3 tabs. (Author)

A preliminary study for the implementation of general accident management strategies

Energy Technology Data Exchange (ETDEWEB)

Yang, Soo Hyung; Kim, Soo Hyung; Jeong, Young Hoon; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1997-12-31

To enhance the safety of nuclear power plants, implementation of accident management has been suggested as one of most important programs. Specially, accident management strategies are suggested as one of key elements considered in development of the accident management program. In this study, generally applicable accident management strategies to domestic nuclear power plants are identified through reviewing several accident management programs for the other countries and considering domestic conditions. Identified strategies are as follows; 1) Injection into the Reactor Coolant System, 2) Depressurize the Reactor Coolant System, 3) Depressurize the Steam Generator, 4) Injection into the Steam Generator, 5) Injection into the Containment, 6) Spray into the Containment, 7) Control Hydrogen in the Containment. In addition, the systems and instrumentation necessary for the implementation of each strategy are also investigated. 11 refs., 3 figs., 3 tabs. (Author)

Empirical Bayesian Geographical Mapping of Occupational Accidents among Iranian Workers.

Science.gov (United States)

Vahabi, Nasim; Kazemnejad, Anoshirvan; Datta, Somnath

2017-05-01

Work-related accidents are believed to be a serious preventable cause of mortality and disability worldwide. This study aimed to provide Bayesian geographical maps of occupational injury rates among workers insured by the Iranian Social Security Organization. The participants included all insured workers in the Iranian Social Security Organization database in 2012. One of the applications of the Bayesian approach called the Poisson-Gamma model was applied to estimate the relative risk of occupational accidents. Data analysis and mapping were performed using R 3.0.3, Open-Bugs 3.2.3 rev 1012 and ArcMap9.3. The majority of all 21,484 investigated occupational injury victims were male (98.3%) including 16,443 (76.5%) single workers aged 20 - 29 years. The accidents were more frequent in basic metal, electric, and non-electric machining jobs. About 0.4% (96) of work-related accidents led to death, 2.2% (457) led to disability (partial and total), 4.6% (980) led to fixed compensation, and 92.8% (19,951) of the injured victims recovered completely. The geographical maps of estimated relative risk of occupational accidents were also provided. The results showed that the highest estimations pertained to provinces which were mostly located along mountain chains, some of which are categorized as deprived provinces in Iran. The study revealed the need for further investigation of the role of economic and climatic factors in high risk areas. The application of geographical mapping together with statistical approaches can provide more accurate tools for policy makers to make better decisions in order to prevent and reduce the risks and adverse outcomes of work-related accidents.

Wrapping corrections beyond the sl(2) sector in N = 4 SYM

Energy Technology Data Exchange (ETDEWEB)

Beccaria, M.; Ratti, C. [Dipartimento di Fisica, Universita del Salento, Lecce (Italy); Macorini, G. [Niels Bohr International Academy and Discovery Center, Niels Bohr Institute, Copenhagen (Denmark)

2012-07-15

The sl(2) sector of N = 4 SYM theory has been much studied and the anomalous dimensions of those operators are well known. Nevertheless, many interesting operators are not included in this sector. We consider a class of twist operators beyond the sl(2) subsector introduced by Freyhult, Rej and Zieme. They are spin n, length-3 operators. At one-loop they can be identified with three gluon operators. At strong coupling, they are associated with spinning strings with two spins in AdS space and charge in S{sup 5}. We exploit the Y-system to compute the leading weak-coupling four loop wrapping correction to their anomalous dimension. The result is written in closed form as a function of the spin n. We combine the wrapping correction with the known four loop asymptotic Bethe Ansatz contribution and analyze special limits in the spin n. In particular, at large n, we prove that a generalized Gribov-Lipatov reciprocity holds. At negative unphysical spin, we present a simple BFKL-like equation predicting the rightmost leading poles. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Validation of severe accident management guidance for the wolsong plants

International Nuclear Information System (INIS)

Park, S. Y.; Jin, Y. H.; Kim, S. D.; Song, Y. M.

2006-01-01

Full text: Full text: The severe accident management(SAM) guidance has been developed for the Wolsong nuclear power plants in Korea. The Wolsong plants are 700MWe CANDU-type reactors with heavy water as the primary coolant, natural uranium-fueled pressurized, horizontal tubes, surrounded by heavy water moderator inside a horizontal calandria vessel. The guidance includes six individual accident management strategies: (1) injection into primary heat transport system (2) injection into calandria vessel (3) injection into calandria vault (4) reduction of fission product release (5) control of reactor building condition (6) reduction of reactor building hydrogen. The paper provides the approaches to validate the SAM guidance. The validation includes the evaluation of:(l) effectiveness of accident management strategies, (2) performance of mitigation systems or components, (3) calculation aids, (4) strategy control diagram, and (5) interface with emergency operation procedure and with radiation emergency plan. Several severe accident sequences with high probability is selected from the plant specific level 2 probabilistic safety analysis results for the validation of SAM guidance. Afterward, thermal hydraulic and severe accident phenomenological analyses is performed using ISAAC(Integrated Severe Accident Analysis Code for CANDU Plant) computer program. Furthermore, the experiences obtained from a table-top-drill is also discussed

Severe Accident Research Program plan update

International Nuclear Information System (INIS)

1992-12-01

In August 1989, the staff published NUREG-1365, ''Revised Severe Accident Research Program Plan.'' Since 1989, significant progress has been made in severe accident research to warrant an update to NUREG-1365. The staff has prepared this SARP Plan Update to: (1) Identify those issues that have been closed or are near completion, (2) Describe the progress in our understanding of important severe accident phenomena, (3) Define the long-term research that is directed at improving our understanding of severe accident phenomena and developing improved methods for assessing core melt progression, direct containment heating, and fuel-coolant interactions, and (4) Reflect the growing emphasis in two additional areas--advanced light water reactors, and support for the assessment of criteria for containment performance during severe accidents. The report describes recent major accomplishments in understanding the underlying phenomena that can occur during a severe accident. These include Mark I liner failure, severe accident scaling methodology, source term issues, core-concrete interactions, hydrogen transport and combustion, TMI-2 Vessel Investigation Project, and direct containment heating. The report also describes the major planned activities under the SARP over the next several years. These activities will focus on two phenomenological issues (core melt progression, and fuel-coolant interactions and debris coolability) that have significant uncertainties that impact our understanding and ability to predict severe accident phenomena and their effect on containment performance SARP will also focus on severe accident code development, assessment and validation. As the staff completes the research on severe accident issues that relate to current generation reactors, continued research will focus on efforts to independently evaluate the capability of new advanced light water reactor designs to withstand severe accidents

ROAD TRANSPORT ACCIDENTS IN NIGERIA AND THE ROLE

Directory of Open Access Journals (Sweden)

Olasunkanmi Oriola AKINYEMI

2016-06-01

Full Text Available Analysis of road traffic accidents revealed that most accidents are as a result of drivers’ errors. Over the years, active safety systems (ASS were devised in vehicle to reduce the high level of road accidents, caused by human errors, leading to death and injuries.This study however evaluated the impacts of ASS inclusions into vehicles in Nigeria road transportation network. The objectives was to measure how ASS contributed to making driving safer and enhanced transport safety. Road accident data were collected, for a period of eleven years, from Lagos State Ministry of Economic Planning and Budget, Central Office of Statistics. Quantitative analysis of the retrospective accident was conducted by computing the proportion of yearly number of vehicles involved in road accident to the total number of vehicles for each year. Results of the analysis showed that the proportion of vehicles involved in road accidents decreased from 16 in 1996 to 0.89 in 2006, the injured persons reduced from 15.58 in 1998 to 0.3 in 2006 and the death rate diminished from 4.45 in 1998 to 0.1 in 2006. These represented 94.4%, 95% and 95% improvement respectively on road traffic safety. It can therefore be concluded that the inclusions of ASS into design of modern vehicles had improved road safety in Nigeria automotive industry.

Development of integrated accident management assessment technology

International Nuclear Information System (INIS)

Jung, Won Dea; Ha, Jae Joo; Jin, Young Ho

2002-04-01

This project aims to develop critical technologies for accident management through securing evaluation frameworks and supporting tools, in order to enhance capabilities coping with severe accidents. For the research goal, firstly under the viewpoint of accident prevention, on-line risk monitoring system and the analysis framework for human error have been developed. Secondly, the training/supporting systems including the training simulator and the off-site risk evaluation system have been developed to enhance capabilities coping with severe accidents. Four kinds of research results have been obtained from this project. Firstly, the framework and taxonomy for human error analysis has been developed for accident management. As the second, the supporting system for accident managements has been developed. Using data that are obtained through the evaluation of off-site risk for Younggwang site, the risk database as well as the methodology for optimizing emergency responses has been constructed. As the third, a training support system, SAMAT, has been developed, which can be used as a training simulator for severe accident management. Finally, on-line risk monitoring system, DynaRM, has been developed for Ulchin 3 and 4 unit

Examining the Feasibilities of Industry 4.0 for the Hospitality Sector with the Lens of Management Practice

OpenAIRE

Shamim, S.; Cang, Shuang; Yu, H.N.A.; Liu, Y.

2017-01-01

Industry 4.0 and its impact in the manufacturing sector are well documented. However, the service sector is understudied, and it is also facing the challenges of mass customization, digital enhancement, smart work environment, and efficient supply chain. The aim of this study is to fill this research gap by exploring the issues of Industry 4.0 in the service sector, with cases in the hospitality industry. All the challenges of Industry 4.0 require continuous innovation and learning, which is ...

Wheelchair-related accidents: relationship with wheelchair-using behavior in active community wheelchair users.

Science.gov (United States)

Chen, Wan-Yin; Jang, Yuh; Wang, Jung-Der; Huang, Wen-Ni; Chang, Chan-Chia; Mao, Hui-Fen; Wang, Yen-Ho

2011-06-01

To report the prevalence, mechanisms, self-perceived causes, consequences, and wheelchair-using behaviors associated with wheelchair-related accidents. A case-control study. Community. A sample of experienced, community-dwelling, active manual and powered wheelchair users (N=95) recruited from a hospital assistive technology service center. Not applicable. Wheelchair-using behaviors, wheelchair-related accidents over a 3-year period, and the mechanisms and consequences of the accidents. Among the 95 participants, 52 (54.7%) reported at least 1 accident and 16 (16.8%) reported 2 or more accidents during the 3 years prior to the interview. A total of 74 accidents, were categorized into tips and falls (87.8%), accidental contact (6.8%), and dangerous operations (5.4%). A logistic regression found individuals who failed to maintain their wheelchairs regularly (odds ratio [OR]=11.28; 95% confidence interval [CI], 2.62-48.61) and used a wheelchair not prescribed by professionals (OR=4.31; 95% CI, 1.10-16.82) had significantly greater risks of accidents. In addition to the risk factor, lack of regular wheelchair maintenance, the Poisson regression corroborated the other risk factor, seat belts not used (incident rate ratio=2.14; 95% CI, 1.08-4.14), for wheelchair-related accidents. Wheelchair-related accidents are closely related to their wheelchair-using behaviors. Services including professional evaluation, repair, maintenance, and an educational program on proper wheelchair use may decrease the risks of wheelchair accidents. Copyright © 2011 American Congress of Rehabilitation Medicine. Published by Elsevier Inc. All rights reserved.

Analysis and research status of severe core damage accidents

International Nuclear Information System (INIS)

1984-03-01

The Severe Core Damage Research and Analysis Task Force was established in Nuclear Safety Research Center, Tokai Research Establishment, JAERI, in May, 1982 to make a quantitative analysis on the issues related with the severe core damage accident and also to survey the present status of the research and provide the required research subjects on the severe core damage accident. This report summarizes the results of the works performed by the Task Force during last one and half years. The main subjects investigated are as follows; (1) Discussion on the purposes and necessities of severe core damage accident research, (2) proposal of phenomenological research subjects required in Japan, (3) analysis of severe core damage accidents and identification of risk dominant accident sequences, (4) investigation of significant physical phenomena in severe core damage accidents, and (5) survey of the research status. (author)

Accident and emergency management

International Nuclear Information System (INIS)

Andersen, V.; Moellenbach, K.; Heinonen, R.; Jakobsson, S.; Kukko, T.; Berg, Oe.; Larsen, J.S.; Westgaard, T.; Magnusson, B.; Andersson, H.; Holmstroem, C.; Brehmer, B.; Allard, R.

1988-06-01

There is an increasing potential for severe accidents as the industrial development tends towards large, centralised production units. In several industries this has led to the formation of large organisations which are prepared for accidents fighting and for emergency management. The functioning of these organisations critically depends upon efficient decision making and exchange of information. This project is aimed at securing and possibly improving the functionality and efficiency of the accident and emergency management by verifying, demonstrating, and validating the possible use of advanced information technology in the organisations mentioned above. With the nuclear industry in focus the project consists of five main activities: 1) The study and detailed analysis of accident and emergency scenarios based on records from incidents and rills in nuclear installations. 2) Development of a conceptual understanding of accident and emergency management with emphasis on distributed decision making, information flow, and control structure sthat are involved. 3) Development of a general experimental methodology for evaluating the effects of different kinds of decision aids and forms of organisation for emergency management systems with distributed decision making. 4) Development and test of a prototype system for a limited part of an accident and emergency organisation to demonstrate the potential use of computer and communication systems, data-base and knowledge base technology, and applications of expert systems and methods used in artificial intelligence. 5) Production of guidelines for the introduction of advanced information technology in the organisations based on evaluation and validation of the prototype system. (author)

Childhood accidents: the relationship of family size to incidence, supervision, and rapidity of seeking medical care.

Science.gov (United States)

Schwartz, Shepard; Eidelman, Arthur I; Zeidan, Amin; Applebaum, David; Raveh, David

2005-09-01

Large family size may be a risk factor for childhood accidents. A possible association with quality of child supervision and rapidity of seeking medical care has not been fully evaluated. To determine whether children with multiple siblings are at increased risk for accidents, to assess whether quality of child supervision varies with family size, and to evaluate the relationship of family size with the rapidity of seeking medical care after an accident. We prospectively studied 333 childhood accidents treated at TEREM (emergency care station) or the Shaare Zedek Medical Center. Details on family composition and the accident were obtained through parental interview. Family size of the study population was compared with that of the Jerusalem population. Families with one to three children (Group 1) and four or more children (Group 2) were compared with regard to type of supervision and different "Gap times" - the time interval from when the accident occurred until medical assistance was sought ("Gap 1"), the time from that medical contact until arrival at Shaare Zedek ("Gap 2"), and the time from the accident until arrival at Shaare Zedek for those children for whom interim medical assistance either was ("Gap 3A") or was not ("Gap 3B") sought. Children from families with 1, 2, 3, 4 and > or =5 children comprised 7.2%, 18.3%, 14.4%, 18.6% and 41.4% of our sample compared to 20.4%, 21.8%, 18.4%, 14.7% and 24.7% in the general population respectively. Children from Group 2 were less often attended to by an adult (44.5% vs. 62.0%) and more often were in the presence only of other children at the time of the accident (27.0% vs. 10.5%). Gaps 1, 2 and 3A in Group 2 (6.3 hours, 16.5 hours, 27.8 hours respectively) were longer than for Group 1 (2.7, 10.7, 13.3 hours respectively). The risk for accidents is increased among children from families with four or more children. The adequacy of child supervision in large families is impaired. There is a relative delay from the time

32 CFR 644.532 - Reporting accidents.

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Reporting accidents. 644.532 Section 644.532... and Improvements § 644.532 Reporting accidents. Immediately upon receipt of information of an accident... that an accident has occurred, the former using command should be requested to send qualified explosive...

Second sector cool down

CERN Multimedia

2007-01-01

At the beginning of July, cool-down is starting in the second LHC sector, sector 4-5. The cool down of sector 4-5 may occasionally generate mist at Point 4, like that produced last January (photo) during the cool-down of sector 7-8.Things are getting colder in the LHC. Sector 7-8 has been kept at 1.9 K for three weeks with excellent stability (see Bulletin No. 16-17 of 16 April 2007). The electrical tests in this sector have got opt to a successful start. At the beginning of July the cryogenic teams started to cool a second sector, sector 4-5. At Point 4 in Echenevex, where one of the LHC’s cryogenic plants is located, preparations for the first phase of the cool-down are underway. During this phase, the sector will first be cooled to 80 K (-193°C), the temperature of liquid nitrogen. As for the first sector, 1200 tonnes of liquid nitrogen will be used for the cool-down. In fact, the nitrogen circulates only at the surface in the ...

Perspectives on phenomenology and simulation of severe accident in light water reactors

International Nuclear Information System (INIS)

Sugimoto, Jun

2014-01-01

Severe accident phenomena in light water reactors (LWRs) are generally characterized by their physically and chemically complex processes involved with high temperature core melt, multi-component and multi-phase flows, transport of radioactive materials and sometimes highly non-equilibrium state. Severe accident phenomenology is usually categorized into four phases; (1) fuel degradation, (2) in-vessel phenomena, (3) ex-vessel phenomena and (4) fission product release and transport. Among these, ex-vessel phenomena consist of five subcategories; 1) direct containment heating, 2) fuel coolant interaction (steam explosion), 3) molten core concrete interaction, 4) hydrogen behaviour and control and 5) containment failure/leakage. In the field of simulation of severe accident, severe accident analytical codes have been developed in the United States, EU and Japan, such as MAAP, MELCOR, ASTEC, THALES and SAMPSON. Many different kinds of analytical codes for the specific severe accident phenomena have also been developed worldwide. After the accident at Fukushima Daiichi Nuclear Power Station, review of severe accident research issues has been conducted and several issues are reconsidered, such as effects of BWR core degradation behaviors, sea water injection, pool scrubbing under rapid depressurization, containment failure/leakage and re-criticality. Some new experimental and analytical efforts have been started after the Fukushima accident. The present paper describes the perspectives on phenomenology and simulation of severe accident in LWRs, with the emphasis of insights obtained in the review of Fukushima accident. (author)

Investigating plutonium contamination in marine sediments off Fukushima coast following the Fukushima Dai-ichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Bu Wenting; Guo Qiuju; Zheng, Jian; Aono, Tatsuo; Tagami, Keiko; Uchida, Shigeo; Zhang, Jing; Yamada, Masatoshi

2013-01-01

The Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident has caused large amounts of anthropogenic radionuclides to be released into the atmosphere as well as directly discharged into the sea. To obtain the vertical distribution of Pu isotopes in marine sediments and to better assess the possible contamination from the FDNPP accident in the marine environment, activities of "2"3"9"+"2"4"0Pu and "2"4"1Pu, as well as the atom ratios of "2"4"0Pu/"2"3"9Pu and "2"4"1Pu/"2"3"9Pu, were investigated in a sediment core collected from the western North Pacific in July 2011. The observed vertical profile of "2"3"9"+"2"4"0Pu activities and "2"4"0Pu/"2"3"9Pu atom ratios showed no extra injection of Pu from the accident, indicating no immediate Pu contamination from the FDNPP accident in the marine sediments in the region investigated. (author)

[Characterization of severe acute occupational poisoning accidents in China between 1989 and 2003].

Science.gov (United States)

Zhang, Min; Li, Tao; Wang, Huan-Qiang; Wang, Hong-Fei; Chen, Shu-Yang; Du, Xie-Yi; Zhang, Shuang; Qin, Jian

2006-12-01

To analyze severe acute occupational poisoning accidents reported in China between 1989 and 2003, and to study the characteristics of severe acute occupational poisoning accidents and provide scientific evidences for prevention and control strategies. The data from the national occupational poisoning case reporting system were analyzed with descriptive methods. (1) There were 506 acute severe occupational poisoning accidents for 15 years with 4 657 workers poisoned. The total poisoning rate was 54.8%, and the total mortality was 16.5%. The average poisoning age was (31.9 +/- 9.8) years old and the average death age was (33.7 +/- 10.3) years old. The poisoning accidents occurred more in men than in women. (2) There were more than 112 chemicals which caused these poisoning accidents. Most of the accidents caused by hydrogen sulfide, carbon monoxide, benzene and homologs, metal and metalloid and carbon dioxide, and the types of chemicals varied in different types of industries. (3) The accidents mainly occurred in chemical industry, manufacture, water disposal industry, mining and construction industry, and the risk was higher in some jobs than others, such as cleanout, machine maintenance and repair, production, mine and digging. The accidents occurred more frequently from April to August each year. (1) The control over the severe acute occupational poisoning is urgent. (2) The trend of the characteristics of severe acute occupational poisoning accidents is centralized in the high risk industries, poisons and jobs. (3) The characteristics of the accidents varied in different types of industries. (4) It is the key point to strengthen the supervision on poisoning.

[Cord accident after external cephalic version: Reality or mostly myth?

Science.gov (United States)

Boujenah, J; Fleury, C; Pharisien, I; Benbara, A; Tigaizin, A; Bricou, A; Carbillon, L

2017-01-01

To study the occurrence of cords accident (nuchal cords, prolapse, and braces) after external cephalic version according to its failure or success. Retrospective study between 1998-2015 comparing in the cord accident diagnosed at delivery (by midwife or doctors according to mode of delivery): Patients with attempt ECV: Group 1 cephalic presentation after successful ECV with trial of labor, and Group 2 failed ECV followed by elective cesarean or trial of labor. Patients with no attempt ECV Group 3 spontaneous cephalic presentation matching for delivery date, maternal age, parity, body mass index, and delivery history with group 1, Group 4 Breech presentation without attempt ECV with trial of labor. A total of 776 women with breech presentation were included (198 in group 1, 446 in group 2, 396 in group 3 and 118 in group 4). The prevalence of cord accident did not differ according to ECV attempt (17.08 % versus 18.9 %), to cephalic presentation (group 1: 24.7 % versus group 3: 25 %) and to breech presentation (group 2: 16.9 % versus group 4: 17.2 %). The trial of labor after failed ECV did not increase the risk of cord accident when compared with elective cesarean (17.4 % versus 16 %). A prolapse cord was only observed after trial of labor, i.e. in groups 1, 2 and 4 without difference (respectively 1, 0.8 and 1.7 %). In each group, the rate of cesarean was not different according to the presence of nuchal cord. Success or failed External cephalic version is not associated with an increased risk of cord accident. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

A study on hydrogen deflagration for selected severe accident sequences in Ringhals 3

Energy Technology Data Exchange (ETDEWEB)

Gustavsson, V.; Moeller, E. [SwedPower AB (Sweden)

2002-01-01

In this report, we have investigated the most important severe accident sequences in Ringhals 3, a Westinghouse 3-loop PWR, concerning hydrogen generation and containment pressure at hydrogen deflagration. In order to analyze the accident sequences and to calculate the hydrogen production, the computer code MAAP (Modular Accident Analysis Program) was used. Six accident sequences were studied, where four were LOCA cases and two transients. MAAP gives the evolution of the accident and particularly the pressure in the containment and the production of hydrogen as a function of time. The pressure peaks at deflagration were calculated by the method AICC-Adiabatic Isochoric Complete Combustion. The results from these calculations are conservative for two reasons. Adiabatic combustion means that the heat losses to structures in the containment are neglected. The combustion is also assumed to occur once and all available hydrogen is burned. The maximum pressure in five analysed cases was compared with the failure pressure of the containment. In the LOCA case, 373 kg hydrogen was burned and the resulting peak pressure in the containment was 0,53 MPa. In the transient, where 720 kg hydrogen was burned, the peak pressure was 0,69 MPa. This is the same as the failure pressure of the containment. Finally, in the conservative case, 980 kg hydrogen was burned and the resulting peak pressure 0,96 MPa. However, it should be noted that these conclusions are conservative from two points of view. Firstly a more realistic (than AICC) calculation of the peak pressure would give a lower value than 0,69 MPa. Secondly, there is conservatism in the evaluation of the failure pressure. (au)

26 CFR 1.501(c)(9)-3 - Voluntary employees' beneficiary associations; life, sick, accident, or other benefits.

Science.gov (United States)

2010-04-01

... recreational activities such as athletic leagues are considered other benefits. The provision of child-care...; life, sick, accident, or other benefits. 1.501(c)(9)-3 Section 1.501(c)(9)-3 Internal Revenue INTERNAL..., or other benefits. (a) In general. The life, sick, accident, or other benefits provided by a...

Robustness of Electrical Systems of Nuclear Power Plants in Light of the Fukushima Daiichi Accident (ROBELSYS). Workshop Proceedings, Paris, France, 1-4 April 2014. Appendix 2 (Cont'd) and Appendix 3 - Robustness of Electrical Systems of NPP's in Light of the Fukushima Daiichi Accident. ROBELSYS Workshop Proceedings. Appendices 2 and 3

International Nuclear Information System (INIS)

2015-01-01

The March 2011 accident at Fukushima Daiichi triggered discussions about the significance of electrical power hazards and their treatment in safety analyses. In order to address these issues and provide relevant conclusions and recommendations to CSNI and CNRA, the Robustness in Electrical Systems (ROBELSYS) Technical Working Group was established in 2012 under the leadership of the Institut de Radioprotection et de Surete Nucleaire (IRSN) of France. The purpose of the ROBELSYS Technical Working Group was to organize an international workshop to identify and discuss the lessons learned from the Fukushima Daiichi accident. The workshop was focused on the provisions taken by various countries concerning national requirements and modifications to the plant designs in order to enhance the robustness of electrical systems, especially the protection against extreme external hazards. The ROBELSYS workshop was held at the OECD Conference Centre in Paris in April 1-4, 2014. A total of 105 participants attended the workshop representing industry and government organisations from 25 countries, as well as international organisations. A total of 34 technical presentations were given in seven sessions as follows: - 1: National Programmes on Evolution of Onsite and Offsite Electric Power Systems; - 2: Role of Electric Power in Severe Accident Management; - 3: Requirements for Robustness of Onsite Electric Power Systems; - 4: Simulation of Transients within NPP Plant Distribution Systems; - 5: Requirements for Equipment Used for Emergency Response; - 6: Margin Assessments for Modern Power Electronics; - 7: Digital Components in Power Systems. Items addressed in the workshop included: - Review of the lessons learned from the Fukushima accident concerning the robustness of electrical systems; - Review of the provisions already taken or planned after the Fukushima accident, regarding the sources, the distribution systems and the loads, and documenting the technical basis for these

Analysis of accidents in nine Iranian gas refineries: 2007-2011.

Science.gov (United States)

Mehrdad, R; Bolouri, A; Shakibmanesh, A R

2013-10-01

Occupational accidents are one of the major health hazards in industries and associated with high mortality, morbidity, spiritual damage and economic losses in the world. To determine the incidence of occupational accidents in 9 Iranian gas refineries between March 2007 and February 2011. Data on all occupational accidents occurred between March 2007 and February 2011, as well as other possible associated variables including time of accident, whether the accident was due to a personal or systemic fault, type of accident and its outcomes, age and gender of the victim, the injured parts of the body, job experience, and type of employment, were extracted from HSE reports and notes of health care services. Based on these data, we calculated the incidence rate of accidents and assessed the associated factors. During the 5 studied years, 1129 accidents have been recorded. The incidence of fatal accidents was 1.64 per 100 000 and of nonfatal accidents was 1857 per 100 000 workers per year. 99.4% of injured workers were male. The mean±SD age of injured people was 29.6±7.3 years. Almost 70% of injured workers aged under 30 years. The mean±SD job experience was 5.3±5.3 years. Accidents occurred more commonly around 10:00. More than 60% of accidents happened between 8:00 and 15:00. July had the highest incidence rate. The most common type of accident was being struck by an object (48%). More than 94% of accidents are caused by personal rather than systemic faults. Hands and wrists were the most common injured parts and involved in more than one-third of accidents. 70% of injured workers needed medical treatment and returned to work after primary treatment. The pattern of occupational accidents in Iranian gas refineries is similar to other previous reports in many ways. The incidence did not change significantly over the study period. Establishment of an online network for precise registration, notification and meticulous data collection seems necessary.

Cerebrovascular accidents in patients with a ventricular assist device.

Science.gov (United States)

Tsukui, Hiroyuki; Abla, Adib; Teuteberg, Jeffrey J; McNamara, Dennis M; Mathier, Michael A; Cadaret, Linda M; Kormos, Robert L

2007-07-01

A cerebrovascular accident is a devastating adverse event in a patient with a ventricular assist device. The goal was to clarify the risk factors for cerebrovascular accident. Prospectively collected data, including medical history, ventricular assist device type, white blood cell count, thrombelastogram, and infection, were reviewed retrospectively in 124 patients. Thirty-one patients (25%) had 48 cerebrovascular accidents. The mean ventricular assist device support period was 228 and 89 days in patients with and without cerebrovascular accidents, respectively (P cerebrovascular accidents occurred within 4 months after implantation. Actuarial freedom from cerebrovascular accident at 6 months was 75%, 64%, 63%, and 33% with the HeartMate device (Thoratec Corp, Pleasanton, Calif), Thoratec biventricular ventricular assist device (Thoratec Corp), Thoratec left ventricular assist device (Thoratec), and Novacor device (WorldHeart, Oakland, Calif), respectively. Twenty cerebrovascular accidents (42%) occurred in patients with infections. The mean white blood cell count at the cerebrovascular accident was greater than the normal range in patients with infection (12,900/mm3) and without infection (9500/mm3). The mean maximum amplitude of the thrombelastogram in the presence of infection (63.6 mm) was higher than that in the absence of infection (60.7 mm) (P = .0309). The risk of cerebrovascular accident increases with a longer ventricular assist device support period. Infection may activate platelet function and predispose the patient to a cerebrovascular accident. An elevation of the white blood cell count may also exacerbate the risk of cerebrovascular accident even in patients without infection. Selection of device type, prevention of infection, and meticulous control of anticoagulation are key to preventing cerebrovascular accident.

Aviation Safety Program: Weather Accident Prevention (WxAP) Project Overview and Status

Science.gov (United States)

Nadell, Shari-Beth

2003-01-01

This paper presents a project overview and status for the Weather Accident Prevention (WxAP) aviation safety program. The topics include: 1) Weather Accident Prevention Project Background/History; 2) Project Modifications; 3) Project Accomplishments; and 4) Project's Next Steps.

Analysis of traffic accidents in Romania, 2009.

Science.gov (United States)

Călinoiu, Geovana; Minca, Dana Galieta; Furtunescu, Florentina Ligia

2012-01-01

This paper aimed to underline the main consequences of traffic accidents in Romania 2009 and their associated causes or circumstances. We identified some problematic geographic areas, some critical months or moments of the day and also the most frequent causes; all these should become targets for the future planning. The current analysis provides some priority criteria for public health interventions. So, the future national road safety strategy should be in line with the EU objectives, but also with the national priorities. Romania is far away from the average EU target for 2010 of halving the death by traffic accidents registered in 2001. To describe the circumstances and the consequences related to traffic accidents registered in Romania, for the year 2009. An ecological study was conducted. The traffic accidents circumstances were analyzed in terms of magnitude, geographic space, time and cause. The consequences were analyzed as affected people and damaged cars. A total of 28,627 traffic accidents were registered in Romania during the year 2009. 2,796 people were killed and 27,968 were hospitalized and 42,443 cars were damaged. 3 of 4 accidents were caused by violations on behalf of the car drivers. Most common violations in car drivers were excess of speed and priority violations (52.4%). Among the pedestrians, 7 of 10 accidents were caused by illegal crossing. A higher number of accidents occurred during the summer months and during the evening hours (from 5.00 pm till 8.00 pm). The traffic accidents represent a real public health problem in Romania and a serious burden for the health system. The gap between Romania and the other EU member states needs to be diminished in the next decade. In this purpose, the future national road safety strategy should be in line with the EU objectives, but also with the national priorities. Research is needed to understand the causes and the socio-economical impact of traffic accidents and to define appropriate national

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

A few seconds to have an accident, a long time to recover: consequences for road accident victims from the ESPARR cohort 2 years after the accident.

Science.gov (United States)

Tournier, Charlène; Charnay, Pierrette; Tardy, Hélène; Chossegros, Laetitia; Carnis, Laurent; Hours, Martine

2014-11-01

The aim of the present study was to describe the consequences of a road accident in adults, taking account of the type of road user, and to determine predictive factors for consequences at 2 years. Prospective follow-up study. The cohort was composed of 1168 victims of road traffic accidents, aged ≥16 years. Two years after the accident, 912 victims completed a self-administered questionnaire. Weighted logistic regression models were implemented to compare casualties still reporting impact related to the accident versus those reporting no residual impact. Five outcomes were analysed: unrecovered health status, impact on occupation or studies, on familial or affective life, on leisure or sport activities and but also the financial difficulties related to the accident. 46.1% of respondents were motorised four-wheel users, 29.6% motorised two-wheel (including quad) users, 13.3% pedestrians (including inline skate and push scooter users) and 11.1% cyclists. 53.3% reported unrecovered health status, 32.0% persisting impact on occupation or studies, 25.2% on familial or affective life, 46.9% on leisure or sport activities and 20.2% still had accident-related financial difficulties. Type of user, adjusted on age and gender, was linked to unrecovered health status and to impact on leisure or sport activities. When global severity (as measured by NISS) was integrated in the previous model, type of user was also associated with impact on occupation or studies. Type of user was further associated with impact on occupation or studies and on leisure or sport activities when global severity and the sociodemographic data obtained at inclusion were taken into account. It was not, however, related to any of the outcomes studied here, when the models focused on the injured body region. Finally, type of road user did not seem, on the various predictive models, to be related to financial difficulties due to the accident or to impact on familial or affective life. Overall, victims

Main results of assessing integrity of RNPP-3 steam generator heat exchange tubes in accident management

International Nuclear Information System (INIS)

Shugajlo, Al-j P.; Mustafin, M.A.; Shugajlo, Al-r P.; Ryzhov, D.I.; Zhabin, O.I.

2017-01-01

Tubes integrity evaluation under accident conditions considering drain of SG and current technical state of steam exchange tubes is an important question regarding SG long-term operation and improvement of accident management strategy.The main investigation results prepared for heat exchange surface of RNPP-3 steam generator are presented in this research aimed at assessing integrity of heat exchange tubes under accident conditions, which lead to full or partial drain of heat exchange surface, in particular during station blackout.

Accidents - Chernobyl accident

International Nuclear Information System (INIS)

2004-01-01

This file is devoted to the Chernobyl accident. It is divided in four parts. The first part concerns the accident itself and its technical management. The second part is relative to the radiation doses and the different contaminations. The third part reports the sanitary effects, the determinists ones and the stochastic ones. The fourth and last part relates the consequences for the other European countries with the case of France. Through the different parts a point is tackled with the measures taken after the accident by the other countries to manage an accident, the cooperation between the different countries and the groups of research and studies about the reactors safety, and also with the international medical cooperation, specially for the children, everything in relation with the Chernobyl accident. (N.C.)

Prevention of accidents in SME’s

DEFF Research Database (Denmark)

Jørgensen, Kirsten; Duijm, Nijs Jan; Troen, Hanne

2009-01-01

we developed a method to observe and document the activities and risks in small enterprises, on the basis of the Dutch study. The co-operation between the Dutch and Danish projects has resulted in a very useful web-based risk assessment tool, which towards June 2009 will be accessible in Dutch......, English and Danish. This tool can be used to obtain information, for both industry sectors as well as individual jobs, on real occupational risks divided into 64 categories, along with those safety barriers that are most effective to prevent accidents. The method has been tested in the Danish project...... in a series of small enterprises covering observations of about 120 man-days. These observations demonstrated that maintaining barriers against accidents can only partly be managed by the employer. Especially in enterprises with employees normally working outside the establishment, the daily safety assessment...

Fatal accidents among Danes with multiple sclerosis

DEFF Research Database (Denmark)

Brønnum-Hansen, Henrik; Hansen, Thomas; Koch-Henriksen, Nils

2006-01-01

We compared the rate of fatal accidents among Danes with multiple sclerosis (MS) with that of the general population. The study was based on linkage of the Danish Multiple Sclerosis Registry to the Cause of Death Registry and covered all 10174 persons in whom MS was diagnosed during the period 19...... for deaths from burns (SMR = 8.90) and suffocation (SMR = 5.57). We conclude that persons with MS are more prone to fatal accidents than the general population. The excess risk is due not to traffic accidents but to burns and suffocation.......-1996. The end of follow-up was 1 January 1999. We calculated standardized mortality ratios (SMRs) for various types of fatal accidents. A total of 76 persons (48 men and 28 women) died from accidents, whereas the expected number of fatalities from such causes was 55.7 (31.4 men and 24.3 women). Thus, the risk...... for death from accidents among persons with MS was 37% higher than that of the general population (SMR = 1.37). We found no significant excess risk for fatal road accidents (SMR = 0.80). The risk for falls was elevated (SMR = 1.29) but not statistically significantly so. The risks were particularly high...

Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-3 silicide core

International Nuclear Information System (INIS)

Kaminaga, Masanori

1997-03-01

JRR-3 is a light water moderated and cooled, beryllium and heavy water reflected pool type research reactor using low enriched uranium (LEU) plate-type fuels. Its thermal power is 20 MW. The core conversion program from uranium-aluminum (UAl x -Al) dispersion type fuel (aluminide fuel) to uranium-silicon-aluminum (U 3 Si 2 -Al) dispersion type fuel (silicide fuel) is currently conducted at the JRR-3. This report describes about the steady-state thermal hydraulic analysis results and the flow channel blockage accident analysis result. In JRR-3, there are two operation mode. One is high power operation mode up to 20 MW, under forced convection cooling using the primary and the secondary cooling systems. The other is low power operation mode up to 200 kW, under natural circulation cooling between the reactor core and the reactor pool without the primary and the secondary cooling systems. For the analysis of the flow channel blockage accident, COOLOD code was used. On the other hand, steady-state thermal hydraulic analysis for both of the high power operation mode under forced convection cooling and low power operation under natural convection cooling, COOLOD-N2 code was used. From steady-state thermal hydraulic analysis results of both forced and natural convection cooling, fuel temperature, minimum DNBR etc. meet the design criteria and JRR-3 LEU silicide core has enough safety margin under normal operation conditions. Furthermore, flow channel blockage accident analysis results show that one channel flow blockage accident meet the safety criteria for accident conditions which have been established for JRR-3 LEU silicide core. (author)

Application of Building Information Modeling (3D and 4D in Construction Sector in Iraq

Directory of Open Access Journals (Sweden)

Kadhim Raheem Erzaij

2017-10-01

Full Text Available Building Information Modeling (BIM is becoming a great known established collaboration process in Architecture, Engineering, and Construction (AEC industry. In various cases in many countries, potential benefits and competitive advantages have been reported. However, despite the potentials and benefits of BIM technologies, it is not applied in the construction sector in Iraq just like many other countries of the world. The purpose of this research is to understand the uses and benefits of BIM for construction projects in Iraq. This purpose has been done by establishing a framework to application of BIM and identifying the benefits of this technology that would convince stakeholders for adopting BIM in the construction sector in Iraq. Through this research, the use of this technology has been clarified by using the proposed framework (application Revit software and linking it with the MS Project and Navisworks Manage software on the case study to identify the important benefits to be the beginning to apply the Building Information Modeling technology in the construction sector in Iraq. The research results indicated that such proposed framework can greatly improve the performance of the current state of project management through improving the project quality, cost saving and time-saving.

A criticism of ANSI/ANS-8.3-1986: Criticality accident alarm system

International Nuclear Information System (INIS)

Malenfant, R.E.

1991-01-01

The American National Standard on criticality accident alarm systems has given rise to confusion in interpretation and implementation of the requirements. In addition, some of the standards have recently been incorporated into US Department of Energy (DOE) orders, and others have been paraphrased in the DOE orders. Some of the DOE orders referencing these standards are being incorporated into law by means of the Code of Federal Regulations. As such, the intent of the authors of the standards to recommend a code of good practice is now being codified into law with attendant civil and criminal penalties for failure to comply. It is suggested that ANSI/ANS-8.3-1986, Critically Accident Alarm System, be carefully reviewed to alleviate the confusion that has been experienced in practice, to clarify the minimum accident of concern, to further define the dose (or dose rate) criteria for activation, and to stress the fact that a prime consideration in any safety system is the overall reduction of risk

Accident rates amongst regular bicycle riders in Tasmania, Australia.

Science.gov (United States)

Palmer, Andrew J; Si, Lei; Gordon, Jared M; Saul, Tim; Curry, Beverley A; Otahal, Petr; Hitchens, Peta L

2014-11-01

To characterise the demographics, cycling habits and accident rates of adult cyclists in Tasmania. Volunteers ≥18 years of age who had cycled at least once/week over the previous month provided information on demographics; cycling experience; bicycles owned; hours/km/trips cycled per week; cycling purpose; protective equipment used; and major (required third-party medical treatment or resulted ≥1 day off work) or minor (interfered with individuals' regular daily activities and/or caused financial costs) accidents while cycling. Over 8-months, 136 cyclists (70.6% male) completed the telephone survey. Mean (standard deviation) age was 45.4 (12.1) years with 17.1 (11.4) years of cycling experience. In the week prior to interview, cyclists averaged 6.6 trips/week (totalling 105.7km or 5.0h). The most common reason for cycling was commuting/transport (34% of trips), followed by training/health/fitness (28%). The incidence of major and minor cycling accidents was 1.6 (95% CI 1.1-2.0) and 3.7 (2.3-5.0) per 100,000km, respectively. Male sex was associated with a significantly lower minor accident risk (incidence rate ratio=0.34, p=0.01). Mountain biking was associated with a significantly higher risk of minor accident compared with road or racing, touring, and city or commuting biking (phealth and wellbeing; cyclists also contributed substantially to the local economy. Accident rates are higher in this sample than previously reported in Tasmania and internationally. Mountain biking was associated with higher risks of both major and minor accidents compared to road/racing bike riding. Copyright © 2014 Elsevier Ltd. All rights reserved.

[Motorcycle accidents in the municipality of Rio Branco in the State of Acre: characterization and trends].

Science.gov (United States)

Rocha, Greiciane da Silva; Schor, Néia

2013-03-01

The scope of this paper is to assess traffic accidents involving motorcycles, the victims involved and the increase in the fleet compared with other vehicles in Rio Branco, State of Acre. It is an epidemiological, descriptive and transversal study of accidents between 2005 and 2008 recorded by the Acre State Highway Department. There were 3,582 motorcycle accidents and 3,768 victims in the period. The motorcycle fleet increased by 72.8%, with involvement in accidents increasing by 42.2%, while accidents involving other vehicles only increased by 9.2%. As regards victims, there is a predominance of men, with rates of 561.1, with the age groups of between 20 and 29 and 30 and 39 being the highest, with 755.4 and 542.2, respectively. With reference to accident characteristics, the highest number of accidents - 32.4% - occurred in the afternoon, followed by the morning with 29.2% and the evening with 28.9%. 18.3% occurred on Saturdays and 15.7% on Sundays. Collisions were the commonest kind of accident, with 3,036 (84.8%) occurrences. The conclusion drawn is that it is essential to stage ongoing preventive programs and ensure greater integration among the institutions involved, with planning and campaigns to reverse the current situation.

ACCIDENT PHENOMENA OF RISK IMPORTANCE PROJECT - Continued RESEARCH CONCERNING SEVERE ACCIDENT PHENOMENA AND MANAGEMENT IN Sweden

International Nuclear Information System (INIS)

Rolandson, S.; Mueller, F.; Loevenhielm, G.

1997-01-01

Since 1988 all reactors in Sweden have mitigating measures, such as filtered vents, implemented. In parallel with the work of implementing these measures, a cooperation effort (RAMA projects) between the Swedish utilities and the Nuclear Power Inspectorate was performed to acquire sufficient knowledge about severe accident research work. The on-going project has the name Accident Phenomena of Risk Importance 3. In this paper, we will give background information about severe accident management in Sweden. In the Accident Phenomena of Risk Importance 3 project we will focus on the work concerning coolability of melted core in lower plenum which is the main focus of the In-vessel Coolability Task Group within the Accident Phenomena of Risk Importance 3 project. The Accident Phenomena of Risk Importance 3 project has joined on international consortium and the in-vessel cooling experiments are performed by Fauske and Associates, Inc. in Burr Ridge, Illinois, United States America, Sweden also intends to do one separate experiment with one instrument penetration we have in Swedish/Finnish BWR's. Other parts of the Accident Phenomena of Risk Importance 3 project, such as support to level 2 studies, the research at Royal Institute of Technology and participation in international programs, such as Cooperative Severe Accident Research Program, Advanced Containment Experiments and PHEBUS will be briefly described in the paper

Underreporting of maritime accidents to vessel accident databases.

Science.gov (United States)

Hassel, Martin; Asbjørnslett, Bjørn Egil; Hole, Lars Petter

2011-11-01

Underreporting of maritime accidents is a problem not only for authorities trying to improve maritime safety through legislation, but also to risk management companies and other entities using maritime casualty statistics in risk and accident analysis. This study collected and compared casualty data from 01.01.2005 to 31.12.2009, from IHS Fairplay and the maritime authorities from a set of nations. The data was compared to find common records, and estimation of the true number of occurred accidents was performed using conditional probability given positive dependency between data sources, several variations of the capture-recapture method, calculation of best case scenario assuming perfect reporting, and scaling up a subset of casualty information from a marine insurance statistics database. The estimated upper limit reporting performance for the selected flag states ranged from 14% to 74%, while the corresponding estimated coverage of IHS Fairplay ranges from 4% to 62%. On average the study results document that the number of unreported accidents makes up roughly 50% of all occurred accidents. Even in a best case scenario, only a few flag states come close to perfect reporting (94%). The considerable scope of underreporting uncovered in the study, indicates that users of statistical vessel accident data should assume a certain degree of underreporting, and adjust their analyses accordingly. Whether to use correction factors, a safety margin, or rely on expert judgment, should be decided on a case by case basis. Copyright © 2011 Elsevier Ltd. All rights reserved.

Risk assessment of maintenance operations: the analysis of performing task and accident mechanism.

Science.gov (United States)

Carrillo-Castrillo, Jesús A; Rubio-Romero, Juan Carlos; Guadix, Jose; Onieva, Luis

2015-01-01

Maintenance operations cover a great number of occupations. Most small and medium-sized enterprises lack the appropriate information to conduct risk assessments of maintenance operations. The objective of this research is to provide a method based on the concepts of task and accident mechanisms for an initial risk assessment by taking into consideration the prevalence and severity of the maintenance accidents reported. Data were gathered from 11,190 reported accidents in maintenance operations in the manufacturing sector of Andalusia from 2003 to 2012. By using a semi-quantitative methodology, likelihood and severity were evaluated based on the actual distribution of accident mechanisms in each of the tasks. Accident mechanisms and tasks were identified by using those variables included in the European Statistics of Accidents at Work methodology. As main results, the estimated risk of the most frequent accident mechanisms identified for each of the analysed tasks is low and the only accident mechanisms with medium risk are accidents when lifting or pushing with physical stress on the musculoskeletal system in tasks involving carrying, and impacts against objects after slipping or stumbling for tasks involving movements. The prioritisation of public preventive actions for the accident mechanisms with a higher estimated risk is highly recommended.

Evaluation of heatup and recovery in a loss of feedwater accident with multiple failure

International Nuclear Information System (INIS)

Bang, Young Seok; Seul, Kwang Won; Kim, Hho Jung

1991-01-01

A loss of feedwater accident with multiple failure has been studied in order to identify the potential severity of the accident when compared with the design basis accident in PWR. The PCS heatup and recovery mode in a LOFA with multiple failure was evaluated using the LOFT L9-1/L3-3 experiment. From experimental result, 4 separable subphase were identified and the associated phenomena were also addressed

Development Status of Accident Tolerant Fuel Cladding for LWRs

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il; Park, Dong-Jun; Park, Jung-Hwan; Yang, Jae-Ho; Koo, Yang-Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Hydrogen explosions and the release of radionuclides are caused by severe damage of current nuclear fuels, which are composed of fuel pellets and fuel cladding, during an accident. To reduce the damage to the public, the fuels have to enhance their integrity under an accident environment. Enhanced accident tolerance fuels (ATFs) can tolerate a loss of active cooling in the reactor core for a considerably longer time period during design-basis and beyond design-basis events while maintaining or improving the fuel performance during normal operations as well as operational transients, in comparison with the current UO{sub 2}-Zr alloy system used in the LWR. Surface modified Zr cladding as a new concept was suggested to apply an enhanced ATF cladding. The aim of the partial ODS treatment is to increase the high-temperature strength to suppress the ballooning/rupture behavior of fuel cladding during an accident event. The target of the surface coating is to increase the corrosion resistance during normal operation and increase the oxidation resistance during an accident event. The partial ODS treatment of Zircaloy-4 cladding can be produced using a laser beam scanning method with Y2O3 powder, and the surface Cr-alloy and Cr/FeCrAl coating on Zircaloy-4 cladding can be obtained after the development of 3D laser coating and arc ion plating technologies.

Can we use near-miss reports for accident prevention? A study in the oil and gas industry in Denmark

NARCIS (Netherlands)

Rasmussen, H.B.; Drupsteen, L.; Dyreborg, J.

2013-01-01

Background: The oil and gas industry in the Danish sector of the North Sea has always focused on reducing work-related accidents. Over the years, accident rates have been reduced, and near-miss reporting has gained in importance, because it allows the industry to learn from experience and prevent

EPRI research on accident management

International Nuclear Information System (INIS)

Oehlberg, R.N.; Chao, J.

1991-01-01

The paper discusses Nuclear Regulatory Commission (NRC) efforts regarding severe reactor accident management and the Nuclear Management and Resources Council (NUMAEX), activities. (EPRI) Electric Power Research Institute accident management program consists of the two products just mentioned plus one related to severe accident plant status information and the MAAP 4.0 computer code. These are briefly discussed

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)

Severe Accident Recriticality Analyses (SARA)

Energy Technology Data Exchange (ETDEWEB)

Frid, W. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Hoejerup, F. [Risoe National Lab. (Denmark); Lindholm, I.; Miettinen, J.; Puska, E.K. [VTT Energy, Helsinki (Finland); Nilsson, Lars [Studsvik Eco and Safety AB, Nykoeping (Sweden); Sjoevall, H. [Teoliisuuden Voima Oy (Finland)

1999-11-01

Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B{sub 4}C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding

Severe Accident Recriticality Analyses (SARA)

International Nuclear Information System (INIS)

Frid, W.; Hoejerup, F.; Lindholm, I.; Miettinen, J.; Puska, E.K.; Nilsson, Lars; Sjoevall, H.

1999-11-01

Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B 4 C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding

Report of the US Department of Energy's team analyses of the Chernobyl-4 Atomic Energy Station accident sequence

International Nuclear Information System (INIS)

1986-11-01

In an effort to better understand the Chernobyl-4 accident of April 26, 1986, the US Department of Energy (DOE) formed a team of experts from the National Laboratories including Argonne National Laboratory, Brookhaven National Laboratory, Oak Ridge National Laboratory, and Pacific Northwest Laboratory. The DOE Team provided the analytical support to the US delegation for the August meeting of the International Atomic Energy Agency (IAEA), and to subsequent international meetings. The DOE Team has analyzed the accident in detail, assessed the plausibility and completeness of the information provided by the Soviets, and performed studies relevant to understanding the accident. The results of these studies are presented in this report

Predictive factors for cerebrovascular accidents after thoracic endovascular aortic repair.

Science.gov (United States)

Mariscalco, Giovanni; Piffaretti, Gabriele; Tozzi, Matteo; Bacuzzi, Alessandro; Carrafiello, Giampaolo; Sala, Andrea; Castelli, Patrizio

2009-12-01

Cerebrovascular accidents are devastating and worrisome complications after thoracic endovascular aortic repair. The aim of this study was to determine cerebrovascular accident predictors after thoracic endovascular aortic repair. Between January 2001 and June 2008, 76 patients treated with thoracic endovascular aortic repair were prospectively enrolled. The study cohort included 61 men; mean age was 65.4 +/- 16.8 years. All patients underwent a specific neurologic assessment on an hourly basis postoperatively to detect neurologic deficits. Cerebrovascular accidents were diagnosed on the basis of physical examination, tomography scan or magnetic resonance imaging, or autopsy. Cerebrovascular accidents occurred in 8 (10.5%) patients, including 4 transient ischemic attack and 4 major strokes. Four cases were observed within the first 24-hours. Multivariable analysis revealed that anatomic incompleteness of the Willis circle (odds ratio [OR] 17.19, 95% confidence interval [CI] 2.10 to 140.66), as well as the presence of coronary artery disease (OR 6.86, 95 CI% 1.18 to 40.05), were independently associated with postoperative cerebrovascular accident development. Overall hospital mortality was 9.2%, with no significant difference for patients hit by cerebrovascular accidents (25.0% vs 7.3%, p = 0.102). Preexisting coronary artery disease, reflecting a severe diseased aorta and anomalies of Willis circle are independent cerebrovascular accident predictors after thoracic endovascular aortic repair procedures. A careful evaluation of the arch vessels and cerebral vascularization should be mandatory for patients suitable for thoracic endovascular aortic repair.

Core loss during a severe accident (COLOSS)

International Nuclear Information System (INIS)

Adroguer, B.; Bertrand, F.; Chatelard, P.; Cocuaud, N.; Van Dorsselaere, J.P.; Bellenfant, L.; Knocke, D.; Bottomley, D.; Vrtilkova, V.; Belovsky, L.; Mueller, K.; Hering, W.; Homann, C.; Krauss, W.; Miassoedov, A.; Schanz, G.; Steinbrueck, M.; Stuckert, J.; Hozer, Z.; Bandini, G.; Birchley, J.; Berlepsch, T. von; Kleinhietpass, I.; Buck, M.; Benitez, J.A.F.; Virtanen, E.; Marguet, S.; Azarian, G.; Caillaux, A.; Plank, H.; Boldyrev, A.; Veshchunov, M.; Kobzar, V.; Zvonarev, Y.; Goryachev, A.

2005-01-01

The COLOSS project was a 3-year shared-cost action, which started in February 2000. The work-programme performed by 19 partners was shaped around complementary activities aimed at improving severe accident codes. Unresolved risk-relevant issues regarding H 2 production, melt generation and the source term were studied through a large number of experiments such as (a) dissolution of fresh and high burn-up UO 2 and MOX by molten Zircaloy (b) simultaneous dissolution of UO 2 and ZrO 2 (c) oxidation of U-O-Zr mixtures (d) degradation-oxidation of B 4 C control rods. Corresponding models were developed and implemented in severe accident computer codes. Upgraded codes were then used to apply results in plant calculations and evaluate their consequences on key severe accident sequences in different plants involving B 4 C control rods and in the TMI-2 accident. Significant results have been produced from separate-effects, semi-global and large-scale tests on COLOSS topics enabling the development and validation of models and the improvement of some severe accident codes. Breakthroughs were achieved on some issues for which more data are needed for consolidation of the modelling in particular on burn-up effects on UO 2 and MOX dissolution and oxidation of U-O-Zr and B 4 C-metal mixtures. There was experimental evidence that the oxidation of these mixtures can contribute significantly to the large H 2 production observed during the reflooding of degraded cores under severe accident conditions. The plant calculation activity enabled (a) the assessment of codes to calculate core degradation with the identification of main uncertainties and needs for short-term developments and (b) the identification of safety implications of new results. Main results and recommendations for future R and D activities are summarized in this paper

Criticality accident:

International Nuclear Information System (INIS)

Canavese, Susana I.

2000-01-01

A criticality accident occurred at 10:35 on September 30, 1999. It occurred in a precipitation tank in a Conversion Test Building at the JCO Tokai Works site in Tokaimura (Tokai Village) in the Ibaraki Prefecture of Japan. STA provisionally rated this accident a 4 on the seven-level, logarithmic International Nuclear Event Scale (INES). The September 30, 1999 criticality accident at the JCO Tokai Works Site in Tokaimura, Japan in described in preliminary, technical detail. Information is based on preliminary presentations to technical groups by Japanese scientists and spokespersons, translations by technical and non-technical persons of technical web postings by various nuclear authorities, and English-language non-technical reports from various news media and nuclear-interest groups. (author)

Scalar sector of the 3 3 1 model with three Higgs triplets

International Nuclear Information System (INIS)

Hoang Ngoc Long

1997-10-01

A scalar sector of the 3 3 1 model with three Higgs triplets is considered. The mass spectrum, eigenstates and interactions of the Higgs and the SM gauge bosons are derived. We show that one of the neutral scalars can be identified with the standard model Higgs boson, and in the considered potential there is no mixing between scalars having VEV and ones without VEV. (author)

CP violation in supersymmetry, Higgs sector and the large hadron ...

Indian Academy of Sciences (India)

induced in the Higgs sector due to the above-mentioned CPV in the soft SUSY breaking ... Supersymmetry; CP violation; Higgs sector; large hadron collider. ..... 90 (80.32). > 90 (73.85). > 90 (63.95). Br(tbH+)(%). 4.0–4.2. 4.9–5.1. 4.8–5.11. 4.0–4.3. MH+. < 133.6 (135.1). < 122.7 (124.3). < 113.8 (115.9). < 106.6 (109.7).

Learning Lessons from TMI to Fukushima and Other Industrial Accidents: Keys for Assessing Safety Management Practices

International Nuclear Information System (INIS)

Dechy, N.; Rousseau, J.-M.; Dien, Y.; Montmayeul, R.; Llory, M.

2016-01-01

The main objective of the paper is to discuss and to argue about transfer, from an industrial sector to another industrial sector, of lessons learnt from accidents. It will be achieved through the discussion of some theoretical foundations and through the illustration of examples of application cases in assessment of safety management practices in Nuclear Power Plant (NPP). The nuclear energy production industry has faced three big ones in 30 years (TMI, Chernobyl, Fukushima) involving three different reactor technologies operated in three quite different cultural, organizational and regulatory contexts. Each of those accident has been the origin of questions, but also generator of lessons, some changing the worldview (see Wilpert and Fahlbruch, 1998) of what does cause an accident in addition to the engineering view about the importance of technical failures (human error, safety culture, sociotechnical interactions). Some of their main lessons were implemented such as improvements of human-machine interfaces ergonomics, recast of some emergency operating procedures, severe accident mitigation strategies and crisis management. Some lessons did not really provide deep changes. It is the case for organizational lessons such as, organizational complexity, management of production pressures, regulatory capture, and failure to learn, etc.

Review of nuclear reactor accidents

International Nuclear Information System (INIS)

Connelly, J.W.; Storr, G.J.

1989-01-01

Two types of severe reactor accidents - loss of coolant or coolant flow and transient overpower (TOP) accidents - are described and compared. Accidents in research reactors are discussed. The 1961 SL1 accident in the US is used as an illustration as it incorporates the three features usually combined in a severe accident - a design flaw or flaws in the system, a circumvention of safety circuits or procedures, and gross operator error. The SL1 reactor, the reactivity accident and the following fuel-coolant interaction and steam explosion are reviewed. 3 figs

Factors associated with non-return to work in the severely injured victims 3 years after a road accident: A prospective study.

Science.gov (United States)

Pélissier, C; Fort, E; Fontana, L; Charbotel, B; Hours, M

2017-09-01

Road accidents may impact victims' physical and/or mental health and socio-occupational life, particularly the capacity to return to work. The purpose of our study is to assess modifiable medical and socio-occupational factors of non-return to work in the severely injured 3 years after a road accident. Among1,168 road accidents casualties in the Rhône administrative Département of France followed for five years, 141 of the 222 severely injured (Maximal Abbreviated Injury Scale ≥ 3) aged more than 16 years who were in work at the time of the accident, reported whether they had returned to work in the 3 years following the accident. The subgroups of those who had (n=113) and had not returned to work (n=28) were compared for socio-occupational (gender, age, educational level, marital status, socio-occupational group) accident-related medical factors (type of road user, type of journey, responsibility in the accident, initial care) and post-accident medical factors (pain intensity, post-traumatic stress disorder, physical sequelae, quality of life) by using standardized tools. Severity of initial head, face and lower-limb injury, intense persistent pain, post-traumatic stress disorder, poor self-assessed quality of life and health status at 3 years were associated with non-return to work on univariate analysis. On multivariate analysis, severity of initial head and lower-limb injury, intense persistent pain at 3 years and post-traumatic stress disorder were significantly associated with non-return to work 3 years following severe road-accident injury. Post-traumatic stress disorder and chronic pain were essential modifiable medical determinants of non-return to work in the severely injured after a road accident: early adapted management could promote return to work in the severely injured. Improve early adapted treatment of pain and PTSD in the rehabilitation team should help the severely injured return to work following a road accident. Copyright © 2017 Elsevier

3D analysis of the reactivity insertion accident in VVER-1000

Energy Technology Data Exchange (ETDEWEB)

Abdullayev, A. M.; Zhukov, A. I.; Slyeptsov, S. M. [NSC Kharkov Inst. for Physics and Technology, 1, Akademicheskaya Str., Kharkov 61108 (Ukraine)

2012-07-01

Fuel parameters such as peak enthalpy and temperature during rod ejection accident are calculated. The calculations are performed by 3D neutron kinetics code NESTLE and 3D thermal-hydraulic code VIPRE-W. Both hot zero power and hot full power cases were studied for an equilibrium cycle with Westinghouse hex fuel in VVER-1000. It is shown that the use of 3D methodology can significantly increase safety margins for current criteria and met future criteria. (authors)

10-year evaluation of train accidents.

Science.gov (United States)

Akkaş, Meltem; Ay, Didem; Metin Aksu, Nalan; Günalp, Müge

2011-09-01

Although less frequent than automobile accidents, train accidents have a major impact on victims' lives. Records of patients older than 16 years of age admitted to the Adult Emergency Department of Hacettepe University Medical Center due to train accidents were retrospectively evaluated. 44 patients (30 males, 14 females) with a mean age of 31.8±11.4 years were included in the study. The majority of the accidents occurred during commuting hours. 37 patients were discharged, 22 of them from the emergency department. The mortality rate was 7/44 (16%). Overall mean Revised Trauma Score (RTS) was 10.5 (3 in deaths and 11.9 in survivors). In 5 patients, the cause of death was pelvic trauma leading to major vascular injury and lower limb amputation. In 1 patient, thorax and abdomen trauma and in 1 patient head injury were the causes of mortality. Primary risk factors for mortality were alcohol intoxication (100%), cardiopulmonary resuscitation on admittance (100%), recurrent suicide attempt (75%), presence of psychiatric illness (60%), and low RTS. In this study, most train accidents causing minor injuries were due to falling from the train prior to acceleration. Nevertheless, train accidents led to a mortality rate of 16% and morbidity rate of 37%. These findings draw attention to the importance of developing preventive strategies.

Neural network-based expert system for severe accident management

International Nuclear Information System (INIS)

Klopp, G.T.; Silverman, E.B.

1992-01-01

This paper presents the results of the second phase of a three-phase Severe Accident Management expert system program underway at Commonwealth Edison Company (CECo). Phase I successfully demonstrated the feasibility of Artificial Neural Networks to support several of the objectives of severe accident management. Simulated accident scenarios were generated by the Modular Accident Analysis Program (MAAP) code currently in use by CECo as part of their Individual Plant Evaluations (IPE)/Accident Management Program. The primary objectives of the second phase were to develop and demonstrate four capabilities of neural networks with respect to nuclear power plant severe accident monitoring and prediction. The results of this work would form the foundation of a demonstration system which included expert system performance features. These capabilities included the ability to: (1) Predict the time available prior to support plate (and reactor vessel) failure; (2) Calculate the time remaining until recovery actions were too late to prevent core damage; (3) Predict future parameter values of each of the MAAP parameter variables; and (4) Detect simulated sensor failure and provide best-value estimates for further processing in the presence of a sensor failure. A variety of accident scenarios for the Zion and Dresden plants were used to train and test the neural network expert system. These included large and small break LOCAs as well as a range of transient events. 3 refs., 1 fig., 1 tab

Types and severity of operated supraclavicular brachial plexus injuries caused by traffic accidents.

Science.gov (United States)

Kaiser, Radek; Waldauf, Petr; Haninec, Pavel

2012-07-01

Brachial plexus injuries occur in up to 5% of polytrauma cases involving motorcycle accidents and in approximately 4% of severe winter sports injuries. One of the criteria for a successful operative therapy is the type of lesion. Upper plexus palsy has the best prognosis, whereas lower plexus palsy is surgically untreatable. The aim of this study was to evaluate a group of patients with brachial plexus injury caused by traffic accidents, categorize the injuries according to type of accident, and look for correlations between type of palsy (injury) and specific accidents. A total of 441 brachial plexus reconstruction patients from our department were evaluated retrospectively(1993 to 2011). Sex, age, neurological status, and the type and cause of injury were recorded for each case. Patients with BPI caused by a traffic accident were assessed in detail. Traffic accidents were the cause of brachial plexus injury in most cases (80.7%). The most common type of injury was avulsion of upper root(s) (45.7%) followed by rupture (28.2%), complete avulsion (16.9%) and avulsion of lower root(s) (9.2%). Of the patients, 73.9% had an upper,22.7% had a complete and only 3.4% had a lower brachial plexus palsy. The main cause was motorcycle accidents(63.2%) followed by car accidents (23.5%), bicycle accidents(10.7%) and pedestrian collisions (3.1%) (paccidents had a higher percentage of lower avulsion (22.7%) and a lower percentage of upper avulsion (29.3%), whereas cyclists had a higher percentage of upper avulsion (68.6%) based on the data from the entire group of patients (paccidents (9.3%,paccidents),significantly more upper and fewer lower palsies were present. In the bicycle accident group, upper palsy was the most common (89%). Study results indicate that the most common injury was an upper plexus palsy. It was characteristic of bicycle accidents, and significantly more common in car and motorcycle accidents. The results also indicate that it is important to consider the

Syncope and Its Impact on Occupational Accidents and Employment

DEFF Research Database (Denmark)

Numé, Anna Karin; Kragholm, Kristian; Carlson, Nicolas

2017-01-01

Background - First-time syncopal episodes usually occur in adults of working age, but their impact on occupational safety and employment remains unknown. We examined the associations of syncope with occupational accidents and termination of employment. Methods and Results - Through linkage...... of the syncope event. Over a median follow-up of 3.2 years (first to third quartiles, 2.0-4.5), 622 people with syncope had an occupational accident requiring hospitalization (2.1/100 person-years). In multiple Poisson regression analysis, the incidence rate ratio in the employed syncope population was higher......, 2.34-2.91). Conclusions - In this nationwide cohort, syncope was associated with a 1.4-fold higher risk of occupational accidents and a 2-fold higher risk of termination of employment compared with the employed general population....

Professional experience and traffic accidents/near-miss accidents among truck drivers.

Science.gov (United States)

Girotto, Edmarlon; Andrade, Selma Maffei de; González, Alberto Durán; Mesas, Arthur Eumann

2016-10-01

To investigate the relationship between the time working as a truck driver and the report of involvement in traffic accidents or near-miss accidents. A cross-sectional study was performed with truck drivers transporting products from the Brazilian grain harvest to the Port of Paranaguá, Paraná, Brazil. The drivers were interviewed regarding sociodemographic characteristics, working conditions, behavior in traffic and involvement in accidents or near-miss accidents in the previous 12 months. Subsequently, the participants answered a self-applied questionnaire on substance use. The time of professional experience as drivers was categorized in tertiles. Statistical analyses were performed through the construction of models adjusted by multinomial regression to assess the relationship between the length of experience as a truck driver and the involvement in accidents or near-miss accidents. This study included 665 male drivers with an average age of 42.2 (±11.1) years. Among them, 7.2% and 41.7% of the drivers reported involvement in accidents and near-miss accidents, respectively. In fully adjusted analysis, the 3rd tertile of professional experience (>22years) was shown to be inversely associated with involvement in accidents (odds ratio [OR] 0.29; 95% confidence interval [CI] 0.16-0.52) and near-miss accidents (OR 0.17; 95% CI 0.05-0.53). The 2nd tertile of professional experience (11-22 years) was inversely associated with involvement in accidents (OR 0.63; 95% CI 0.40-0.98). An evident relationship was observed between longer professional experience and a reduction in reporting involvement in accidents and near-miss accidents, regardless of age, substance use, working conditions and behavior in traffic. Copyright © 2016 Elsevier Ltd. All rights reserved.

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

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)

Level of health of cleaners taking part in the Chernobyl accident consequences

International Nuclear Information System (INIS)

Margine, L.; Vicol, C.

2009-01-01

During the period of 1986-1988 about 3,000 Moldova citizens took part in Chernobyl NPP accident consequences elimination. In this article the level of morbidity, disability and mortality among Chernobyl accident consequences liquidation participants is analyzed. As a result of analysis of medical documentation and statistical data was revealed that the sickness rate among disaster fighters 2,3 times higher than general sickness rate of the population in Moldova. Disability in this category is at average of 73 per cent as opposed to the overall index for the population of Moldova - 4,4%, this means it is 17 times higher. Mortality among the participants of the accident at Chernobyl NPP is 6 times higher of general data. The participants of the breakdown elimination of Chernobyl accident consequences are equal in their right with the participants and invalids of war and with the disabled workers. Medical and social security of this group is regulated by the legislation of the Republic of Moldova

Road accidents at night in the Netherlands : a national analysis according to official road accident data. Contribution to OECD Research Group TS 3 on Improving Road Safety at Night.

NARCIS (Netherlands)

Harris, S.

1979-01-01

The questionnaire about night-time accident data of the OECD Research Group TS 3 on Improving Road Safety at Night was filled in for the Netherlands. Thereafter a national analysis was written, using the already completed accident data questionnaire. Guidelines for the contents and presentation

3-Dimensional Methodology for the Control Rod Ejection Accident Analysis Using UNICORN{sup TM}

Energy Technology Data Exchange (ETDEWEB)

Jang, Chan-su; Um, Kil-sup; Ahn, Dawk-hwan [Korea Nuclear Fuel Company, Taejon (Korea, Republic of); Kim, Yo-han; Sung, Chang-kyung [KEPRI, Taejon (Korea, Republic of); Song, Jae-seung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

2006-07-01

The control rod ejection accident has been analyzed with STRIKIN-II code using the point kinetics model coupled with conservative factors to address the three dimensional aspects. This may result in a severe transient with very high fuel enthalpy deposition. KNFC, under the support of KEPRI and KAERI, is developing 3-dimensional methodology for the rod ejection accident analysis using UNICORNTM (Unified Code of RETRAN, TORC and MASTER). For this purpose, 3-dimensional MASTER-TORC codes, which have been combined with the dynamic-link library by KAERI, are used in the transient analysis of the core and RETRAN code is used to estimate the enthalpy deposition in the hot rod.

Three Mile Island accident

International Nuclear Information System (INIS)

Barre, B.; Olivier, E.; Roux, J.P.; Pelle, P.

2010-01-01

Deluded by equivocal instrumentation signals, operators at TMI-2 (Three Mile Island - unit 2) misunderstood what was going on in the reactor and for 2 hours were taking inadequate decisions that turned a reactor incident into a major nuclear event that led to the melting of about one third of the core. The TMI accident had worldwide impacts in the domain of nuclear safety. The main consequences in France were: 1) the introduction of the major accident approach and the reinforcement of crisis management; 2) the improvement of the reactor design, particularly that of the pressurizer valves; 3) the implementation of safety probabilistic studies; 4) a better taking into account of the feedback experience in reactor operations; and 5) a better taking into account of the humane factor in reactor safety. (A.C.)

[Accidents and injuries at work].

Science.gov (United States)

Standke, W

2014-06-01

In the case of an accident at work, the person concerned is insured by law according to the guidelines of the Sozialgesetzbuch VII as far as the injuries have been caused by this accident. The most important source of information on the incident in question is the accident report that has to be sent to the responsible institution for statutory accident insurance and prevention by the employer, if the accident of the injured person is fatal or leads to an incapacity to work for more than 3 days (= reportable accident). Data concerning accidents like these are sent to the Deutsche Gesetzliche Unfallversicherung (DGUV) as part of a random sample survey by the institutions for statutory accident insurance and prevention and are analyzed statistically. Thus the key issues of accidents can be established and used for effective prevention. Although the success of effective accident prevention is undisputed, there were still 919,025 occupational accidents in 2011, with clear gender-related differences. Most occupational accidents involve the upper and lower extremities. Accidents are analyzed comprehensively and the results are published and made available to all interested parties in an effort to improve public awareness of possible accidents. Apart from reportable accidents, data on the new occupational accident pensions are also gathered and analyzed statistically. Thus, additional information is gained on accidents with extremely serious consequences and partly permanent injuries for the accident victims.

49 CFR 195.50 - Reporting accidents.

Science.gov (United States)

2010-10-01

... 49 Transportation 3 2010-10-01 2010-10-01 false Reporting accidents. 195.50 Section 195.50 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY... PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.50 Reporting accidents. An accident...

48 CFR 636.513 - Accident prevention.

Science.gov (United States)

2010-10-01

... CONTRACTING CONSTRUCTION AND ARCHITECT-ENGINEER CONTRACTS Contract Clauses 636.513 Accident prevention. (a) In... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Accident prevention. 636... contracting activities shall insert DOSAR 652.236-70, Accident Prevention, in lieu of FAR clause 52.236-13...

[Motorcycle couriers: characteristics of traffic accidents in southern Brazil].

Science.gov (United States)

Soares, Dorotéia Fátima Pelissari de Paula; Mathias, Thais Aidar de Freitas; da Silva, Daniela Wosiack; de Andrade, Selma Maffei

2011-09-01

This study aimed at understanding characteristics of traffic accidents with motorcycle couriers in the cities of Londrina and Maringá, in the State of Paraná (Brazil). A total of 327 couriers who reported, in 2005/2006, motorcycle accident in the previous 12 months took part in the study (147 in Londrina and 180 in Maringá). Of all the interviewed, 39.6% reported more than one traffic accident. The accidents were perceived as serious by 21.4% of them and 56.3% reported knowing a convalescing courier due to a traffic accident. Most injuries (82.9%) occurred during work hours. Significant differences were observed between the cities concerning climatic conditions (p=0.013), time of the day (p=0.002), pre-hospital care (p=0.032) and hospital admission (paccidents highlight the susceptibility of motorcycle couriers to these events and the need for strategies and specific prevention policies.

Visualization of Traffic Accidents

Science.gov (United States)

Wang, Jie; Shen, Yuzhong; Khattak, Asad

2010-01-01

Traffic accidents have tremendous impact on society. Annually approximately 6.4 million vehicle accidents are reported by police in the US and nearly half of them result in catastrophic injuries. Visualizations of traffic accidents using geographic information systems (GIS) greatly facilitate handling and analysis of traffic accidents in many aspects. Environmental Systems Research Institute (ESRI), Inc. is the world leader in GIS research and development. ArcGIS, a software package developed by ESRI, has the capabilities to display events associated with a road network, such as accident locations, and pavement quality. But when event locations related to a road network are processed, the existing algorithm used by ArcGIS does not utilize all the information related to the routes of the road network and produces erroneous visualization results of event locations. This software bug causes serious problems for applications in which accurate location information is critical for emergency responses, such as traffic accidents. This paper aims to address this problem and proposes an improved method that utilizes all relevant information of traffic accidents, namely, route number, direction, and mile post, and extracts correct event locations for accurate traffic accident visualization and analysis. The proposed method generates a new shape file for traffic accidents and displays them on top of the existing road network in ArcGIS. Visualization of traffic accidents along Hampton Roads Bridge Tunnel is included to demonstrate the effectiveness of the proposed method.

[Incidence of non-fatal work-related accidents in Southeast Brazil].

Science.gov (United States)

Cordeiro, Ricardo; Prestes, Simone Cristina Chiodi; Clemente, Ana Paula Grotti; Diniz, Cíntia Ségre; Sakate, Mirian; Donalisio, Maria Rita

2006-02-01

Incidence of work-related accidents in Botucatu, São Paulo, Brazil, was estimated according to gender, age, employment status, occupation, and type of work. A household survey was conducted by systematic random group sampling (195 census tracts). Information was collected from all residents 10 years or older in each household. Of those who had worked during the 90 days prior to the interview, we obtained information on occupation, job position, and employment contract. The study included 9,626 households (sample fraction 0.26). The proportion of non-fatal work accidents in the municipal area was 3.3% (95%CI: 2.7-3.9), higher for men 4.5% (95%CI: 3.6-5.5) and varying with type of employment contract and occupation. Compared to results from previous studies, we observed a decline in work-related accident risk.

Thermal Hydraulic design parameters study for severe accidents using neural networks

Energy Technology Data Exchange (ETDEWEB)

Roh, Chang Hyun; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Chang, Keun Sun [Sunmoon University, Asan (Korea, Republic of)

1998-12-31

To provide the information on severe accident progression is very important for advanced or new type of nuclear power plant (NPP) design. A parametric study, therefore, was performed to investigate the effect of thermal hydraulic design parameters on severe accident progression of pressurized water reactors (PWRs). Nine parameters, which are considered important in NPP design or severe accident progression, were selected among the various thermal hydraulic design parameters. The backpropagation neural network (BPN) was used to determine parameters, which might more strongly affect the severe accident progression, among nine parameters. For training, different input patterns were generated by the latin hypercube sampling (LHS) technique and then different target patterns that contain core uncovery time and vessel failure time were obtained for Young Gwang Nuclear (YGN) Units 3 and 4 using modular accident analysis program (MAAP) 3.0B code. Three different severe accident scenarios, such as two loss of coolant accidents (LOCAs) and station blackout (SBO), were considered in this analysis. Results indicated that design parameters related to refueling water storage tank (RWST), accumulator and steam generator (S/G) have more dominant effects on the progression of severe accidents investigated, compared to the other six parameters. 9 refs., 5 tabs. (Author)

Thermal Hydraulic design parameters study for severe accidents using neural networks

Energy Technology Data Exchange (ETDEWEB)

Roh, Chang Hyun; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Chang, Keun Sun [Sunmoon University, Asan (Korea, Republic of)

1997-12-31

To provide the information on severe accident progression is very important for advanced or new type of nuclear power plant (NPP) design. A parametric study, therefore, was performed to investigate the effect of thermal hydraulic design parameters on severe accident progression of pressurized water reactors (PWRs). Nine parameters, which are considered important in NPP design or severe accident progression, were selected among the various thermal hydraulic design parameters. The backpropagation neural network (BPN) was used to determine parameters, which might more strongly affect the severe accident progression, among nine parameters. For training, different input patterns were generated by the latin hypercube sampling (LHS) technique and then different target patterns that contain core uncovery time and vessel failure time were obtained for Young Gwang Nuclear (YGN) Units 3 and 4 using modular accident analysis program (MAAP) 3.0B code. Three different severe accident scenarios, such as two loss of coolant accidents (LOCAs) and station blackout (SBO), were considered in this analysis. Results indicated that design parameters related to refueling water storage tank (RWST), accumulator and steam generator (S/G) have more dominant effects on the progression of severe accidents investigated, compared to the other six parameters. 9 refs., 5 tabs. (Author)

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

In-depth investigation of escalator riding accidents in heavy capacity MRT stations.

Science.gov (United States)

Chi, Chia-Fen; Chang, Tin-Chang; Tsou, Chi-Lin

2006-07-01

In 2000, the accident rate for escalator riding was about 0.815 accidents per million passenger trips through Taipei Metro Rapid Transit (MRT) heavy capacity stations. In order to reduce the probability and severity of escalator riding accidents and enhance the safety of passengers, the Drury and Brill model [Drury, C.G., Brill, M., 1983. Human factors in consumer product accident investigation. Hum. Factors 25 (3), 329-342] for in-depth investigation was adopted to analyze the 194 escalator riding accidents in terms of victim, task, product and environment. Prevention measures have been developed based on the major causes of accidents and other related contributing factors. The results from the analysis indicated that the majority of the escalator riding accidents was caused by passengers' carrying out other tasks (38 cases, including carrying luggage 24 cases, looking after accompany persons 9 cases, and 5 others), loss of balance (26 cases, 13.4%), not holding the handrail (20 cases, 10.3%), unhealthy passengers (18 cases, 9.3%), followed by people struck by other passenger (16 cases, 8.2%). For female passengers aged 15-64 years, their rushing for trains accidents could have been prevented by wearing safer footwear or by appropriate signing being provided indicating the location and traveling direction of escalators. Female passengers aged 65 years and above whose accidents were caused by loss of balance, should be encouraged to take the elevator instead. To prevent entrapment injuries, following a stricter design code can be most effective. Further in-depth accident investigation is suggested to cover the activity of the victim prior to the accident, any involved product, the location of the accident on the escalator, any medical treatment, what went wrong, opinion of the respondent on the causes of the accident, and personal characteristics of the passengers. Also, management must trade off productivity and safety appropriately to prevent "Organizational

Hazards and accident analyses, an integrated approach, for the Plutonium Facility at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pan, P.Y.; Goen, L.K.; Letellier, B.C.; Sasser, M.K.

1995-01-01

This paper describes an integrated approach to perform hazards and accident analyses for the Plutonium Facility at Los Alamos National Laboratory. A comprehensive hazards analysis methodology was developed that extends the scope of the preliminary/process hazard analysis methods described in the AIChE Guidelines for Hazard Evaluations. Results fro the semi-quantitative approach constitute a full spectrum of hazards. For each accident scenario identified, there is a binning assigned for the event likelihood and consequence severity. In addition, each accident scenario is analyzed for four possible sectors (workers, on-site personnel, public, and environment). A screening process was developed to link the hazard analysis to the accident analysis. Specifically the 840 accident scenarios were screened down to about 15 accident scenarios for a more through deterministic analysis to define the operational safety envelope. The mechanics of the screening process in the selection of final scenarios for each representative accident category, i.e., fire, explosion, criticality, and spill, is described

[Peculiarities and aims of first aid training in the road haulage sector].

Science.gov (United States)

Rosso, G L; Bruno, Santina; Feola, M; Zanelli, R; Corino, P

2008-01-01

Four years after the law concerning first aid in the workplace was passed in Italy (inter-ministerial decree 388/2003), which is a useful tool in improving safety at work, it is necessary to organize first aid courses specifically for those working in the road haulage sector which would also be effective in case of traffic accidents. In view of the characteristics of the working environment in this sector (the road) and of the working conditions (generally workers are isolated and far from the company's headquarters), it would be necessary to organize ad hoc first aid courses at the workplace for the category of professional drivers. The aim of this article is to discuss some possible organizational aspects of first aid in the road haulage sector, such as: number of workers responsible for first aid, how to train workers for specific risks of traffic accidents, the requirements for teachers responsible for first aid and course targets that must be achieved. A good level of training, achieved during the first aid course at the workplace, might therefore be useful to improve road safety and increase the quality of basic and advanced first aid in road traffic injuries.

The contribution of human factors to accidents in the offshore oil industry

International Nuclear Information System (INIS)

Gordon, Rachael P.E.

1998-01-01

Accidents such as the Piper Alpha disaster illustrate that the performance of a highly complex socio-technical system, is dependent upon the interaction of technical, human, social, organisational, managerial and environmental factors and that these factors can be important co-contributors that could potentially lead to a catastrophic event. The purpose of this article is to give readers an overview of how human factors contribute to accidents in the offshore oil industry. An introduction to human errors and how they relate to human factors in general terms is given. From here the article discusses some of the human factors which were found to influence safety in other industries and describes the human factors codes used in accident reporting forms in the aviation, nuclear and marine industries. Analysis of 25 accident reporting forms from offshore oil companies in the UK sector of the North Sea was undertaken in relation to the human factors. Suggestions on how these accident reporting forms could be improved are given. Finally, this article describes the methods by which accidents can be reduced by focusing on the human factors, such as feedback from accident reporting in the oil industry, auditing of unsafe acts and auditing of latent failures

Accident-tolerant control rod

International Nuclear Information System (INIS)

Ohta, Hirokazu; Sawabe, Takashi; Ogata, Takanari

2013-01-01

Boron carbide (B 4 C) and hafnium (Hf) metal are used for the neutron absorber materials of control rods in BWRs, and silver-indium-cadmium (Ag-In-Cd) alloy is used in PWRs. These materials are clad with stainless steel. The eutectic point of B 4 C and iron (Fe) is about 1150 deg. C and the melting point of Ag-In-Cd alloy is about 800 deg. C, which are lower than the temperature of zircaloy - steam reaction increases rapidly (∼1200 deg. C). Accordingly, it is possible that the control rods melt and collapse before the reactor core is significantly damaged in the case of severe accidents. Since the neutron absorber would be separated from the fuels, there is a risk of re-criticality, when pure water or seawater is injected for emergency cooling. In order to ensure sub-criticality and extend options of emergency cooling in the course of severe accidents, a concept of accident-tolerant control rod (ACT) has been derived. ACT utilises a new absorber material having the following properties: - higher neutron absorption than current control rod; - higher melting or eutectic temperature than 1200 deg. C where rapid zircaloy oxidation occurs; - high miscibility with molten fuel materials. The candidate of a new absorber material for ATC includes gadolinia (Gd 2 O 3 ), samaria (Sm 2 O 3 ), europia (Eu 2 O 3 ), dysprosia (Dy 2 O 3 ), hafnia (HfO 2 ). The melting point of these materials and the liquefaction temperature with Fe are higher than the rapid zircaloy oxidation temperature. ACT will not collapse before the core melt-down. After the core melt-down, the absorber material will be mixed with molten fuel material. The current absorber materials, such as B 4 C, Hf and Ag-In-Cd, are charged at the tip of ATC in which the neutron flux is high, and a new absorber material is charged in the low-flux region. This design could minimise the degradation of a new absorber material by the neutron absorption and the influence of ATC deployment on reactor control procedure. As a

Technology, safety and costs of decommissioning reference light water reactors following postulated accidents

International Nuclear Information System (INIS)

Konzek, G.J.; Smith, R.I.

1990-12-01

The estimated costs for post-accident cleanup at the reference BWR (developed previously in NUREG/CR-2601, Technology, Safety and Costs of Decommissioning Reference Light Water Reactors Following Postulated Accidents) are updated to January 1989 dollars in this report. A simple formula for escalating post-accident cleanup costs is also presented. Accident cleanup following the most severe accident described in NUREG/CR-2601 (i.e., the Scenario 3 accident) is estimated to cost from $1.22 to 1.44 billion, in 1989 dollars, for assumed escalation rates of 4% or 8% in the years following 1989. The time to accomplish cleanup remained unchanged from the 8.3 years originally estimated. No reanalysis of current information on the technical aspects of TMI-2 cleanup has been performed. Only the cost of inflation has been evaluated since the original PNL analysis was completed. 32 refs., 12 tabs

Assessment of accident severity in the construction industry using the Bayesian theorem.

Science.gov (United States)

Alizadeh, Seyed Shamseddin; Mortazavi, Seyed Bagher; Mehdi Sepehri, Mohammad

2015-01-01

Construction is a major source of employment in many countries. In construction, workers perform a great diversity of activities, each one with a specific associated risk. The aim of this paper is to identify workers who are at risk of accidents with severe consequences and classify these workers to determine appropriate control measures. We defined 48 groups of workers and used the Bayesian theorem to estimate posterior probabilities about the severity of accidents at the level of individuals in construction sector. First, the posterior probabilities of injuries based on four variables were provided. Then the probabilities of injury for 48 groups of workers were determined. With regard to marginal frequency of injury, slight injury (0.856), fatal injury (0.086) and severe injury (0.058) had the highest probability of occurrence. It was observed that workers with severe and fatal accidents, involved workers ≥ 50 years old, married, with 1-5 years' work experience, who had no past accident experience. The findings provide a direction for more effective safety strategies and occupational accident prevention and emergency programmes.

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

Allometric scaling and accidents at work

Science.gov (United States)

Cempel, Czesław; Tabaszewski, Maciej; Ordysiński, Szymon

2016-01-01

Allometry is the knowledge concerning relations between the features of some beings, like animals, or cities. For example, the daily energy rate is proportional to a mass of mammals rise of 3/4. This way of thinking has spread quickly from biology to many areas of research concerned with sociotechnical systems. It was revealed that the number of innovations, patents or heavy crimes rises as social interaction increases in a bigger city, while other urban indexes such as suicides decrease with social interaction. Enterprise is also a sociotechnical system, where social interaction and accidents at work take place. Therefore, do these interactions increase the number of accidents at work or, on the contrary, are they reduction-driving components? This article tries to catch such links and assess the allometric exponent between the number of accidents at work and the number of employees in an enterprise. PMID:26655044

32 CFR 634.29 - Traffic accident investigation reports.

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Traffic accident investigation reports. 634.29... records. Installation law enforcement officials will record traffic accident investigations on Service/DLA... traffic accident investigation reports pertaining to accidents investigated by military police that...

PCTRAN-3: The third generation of personal computer-based plant analyzer for severe accident management

International Nuclear Information System (INIS)

Li-Chi Cliff Po; Link, John M.

2004-01-01

PCTRAN is a plant analyzer that uses a personal computer to simulate plant response. The plant model is recently expanded to accommodate beyond design-basis severe accidents. In the event of multiple failures of the plant safety systems, the core may experience heatup and extensive failure. Using a high-powered personal computer (PC), PCTRAN-3 is designed to operate at a speed significantly faster than real-time. A convenient, interactive and user-friendly graphics interface allows full control by the operator. The plant analyzer is intended for use in severe accident management. In this paper the code's component models and sample runs ranging from normal operational transients to severe accidents are reviewed. (author)

Accidents and complications associated to third molar surgeries performed by dentistry students.

Science.gov (United States)

Azenha, Marcelo Rodrigues; Kato, Rogerio Bentes; Bueno, Renan Barros Lima; Neto, Patricio Jose Oliveira; Ribeiro, Michel Campos

2014-12-01

The aim of this work is to demonstrate the accidents and complications rates on third molars surgeries performed by senior dentistry students. A retrospective study of 122 patient charts submitted to third molars surgeries was done. Patient age, gender, dental in arch position, and accidents/complications were considered with the charts presenting incomplete dates being excluded from the study. After all, 88 patients (210 surgeries) were included. The majority of the patients were female (70.4 %), with the average age of 24 years. Mandibular molars represented more than half of the surgical procedures (56.2 %), with teeth at vertical position the most found (60.3 %). The cases of accidents and complications totalized 10.4 % of all performed procedures, being hemorrhage (1.9 %), root fractures (1.9 %), and maxillary tuberosity fracture (1.9 %) the most found. Suture dehiscence (1.4 %), dry socket (1.4 %), oroantral communications (0.9 %), paresthesia (0.9 %), and infection (0.4 %) were also observed. Surgeons' inexperience was not considered a determinant factor to modify the rates of accidents and complications at third molars surgeries when compared to previous works developed by experienced surgeons. It is important to highlight the necessity of the students' knowledge of the most adequate treatments of each of the accidents and complications.

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

International Nuclear Information System (INIS)

Imanaka, T.

1998-03-01

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

Accident management for severe accidents

International Nuclear Information System (INIS)

Bari, R.A.; Pratt, W.T.; Lehner, J.; Leonard, M.; Disalvo, R.; Sheron, B.

1988-01-01

The management of severe accidents in light water reactors is receiving much attention in several countries. The reduction of risk by measures and/or actions that would affect the behavior of a severe accident is discussed. The research program that is being conducted by the US Nuclear Regulatory Commission focuses on both in-vessel accident management and containment and release accident management. The key issues and approaches taken in this program are summarized. 6 refs

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

Characteristics of motorcyclists involved in road traffic accidents attended at public urgent and emergency services.

Science.gov (United States)

Mascarenhas, Márcio Dênis Medeiros; Souto, Rayone Moreira Costa Veloso; Malta, Deborah Carvalho; Silva, Marta Maria Alves da; Lima, Cheila Marina de; Montenegro, Marli de Mesquita Silva

2016-12-01

Injuries resulting from motorcycle road traffic accidents are an important public health issue in Brazil. This study aimed to describe the characteristics of motorcyclists involved in traffic accidents attended in public urgent and emergency services in the state capitals and the Federal District. This is a cross-sectional study based on data from the Violence and Accident Surveillance System (VIVA Survey) in 2014. Data were analyzed according to sociodemographic, event and attendance characteristics. Proportional differences between genders were analyzed by chi-square test (Rao-Scott) with 5% significance level. Motorcyclist-related attendances (n = 9,673) reported a prevalence of men (gender ratio = 3.2), young people aged 20-39 years (65.7%), black / brown (73.6%), paid work (76.4%). Helmet use was reported by 79.1% of the victims, 13.3% had consumed alcohol in the six hours prior to the accident, 41.4% of the events were related to the victim's work. Accidents were more frequent on weekends, in the morning and late afternoon. These characteristics can support the development of public accident prevention policies and health promotion.

Accidents in the greenhouse-construction industry of SE Spain.

Science.gov (United States)

Pérez-Alonso, José; Carreño-Ortega, Angel; Vázquez-Cabrera, Fernando J; Callejón-Ferre, Angel Jesús

2012-01-01

This work analyses the labour accidents in the greenhouse-construction industry of SE Spain for the period 1999-2007 through a sample of 180 accident reports. The accidents were characterised by studying 5 variables in order to know the day of the week in which the accident occurred, the hour of the day of the accident, type of accident, the region of Spain in which the accident happened, and the resulting injury. The data characterising the accidents were submitted to a descriptive multiple-correspondence analysis. The incidence of accidents in the greenhouse-construction industry presented a high mean value of 15133.7 per 100,000 workers per year. The days with the greatest incidence of accidents were Thursday and Monday, while the period of greatest number of accidents occurred in the first 4h of the workday. No significant correspondence was found between the day of the week, the hour of the day, or any of the other 3 variables studied. The types of accidents with most frequency were: cuts, punctures, contact with hard or rough material, overexertion, and falls from one level to another. The most affected parts of the anatomy were the eyes, thorax, back, sides, lower legs, and feet. The most common types of injury were bone fractures, twists and sprains, distended muscles, contusions, and being crushed. The study calls attention to the high number of accidents at work, which needs to be corrected by fulfilment of safety regulations at work, on the part of the company. Finally, recommendations are made to correct this situation of high number of accidents at work. Copyright © 2011 Elsevier Ltd and The Ergonomics Society. All rights reserved.

Method for consequence calculations for severe accidents

International Nuclear Information System (INIS)

Nielsen, F.

1988-01-01

This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Ringhals reactor No 3/4. The accident sequence chosen for the calcualtions was a release caused by total power failure. The calculations were made by means of the PLUCON4 code. A decontamination factor of 500 is used to account for the scrubber effect. Meteorological data for two years from the Ringhals meteorological tower were analysed to find representative weather situations. As typical weather, Pasquill D, was chosen with a wind speed of 10 m/s, and as extreme weather, Pasquill E, with a wind speed of 2 m/s. 19 refs. (author)

DEFORM-4: fuel pin characterization and transient response in the SAS4A accident analysis code system

International Nuclear Information System (INIS)

Miles, K.J.; Hill, D.J.

1986-01-01

The DEFORM-4 module is the segment of the SAS4A Accident Analysis Code System that calculates the fuel pin characterization in response to a steady state irradiation history, thereby providing the initial conditions for the transient calculation. The various phenomena considered include fuel porosity migration, fission gas bubble induced swelling, fuel cracking and healing, fission gas release, cladding swelling, and the thermal-mechanical state of the fuel and cladding. In the transient state, the module continues the thermal-mechanical response calculation, including fuel melting and central cavity pressurization, until cladding failure is predicted and one of the failed fuel modules is initiated. Comparisons with experimental data have demonstrated the validity of the modeling approach

Accident management information needs for a BWR with a MARK I containment

Energy Technology Data Exchange (ETDEWEB)

Chien, D.N.; Hanson, D.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1991-05-01

In support of the US Nuclear Regulatory Commission Accident Management Research Program, information needs during severe accidents have been evaluated for Boiling Water Reactors (BWRs) with MARK 1 containments. This evaluation was performed using a methodology that identifies plant information needs necessary for personnel to: (a) diagnose that an accident is in progress, (b) select and implement strategies to prevent or mitigate the accident, and (c) monitor the effectiveness of these strategies. The information needs and capabilities identified are intended to form a basis for more comprehensive information needs assessments. The assessments will be performed during the analysis and development of specific strategies, which will be used in accident management prevention and mitigation. 3 refs., 4 figs., 2 tabs.

Accident management information needs for a BWR with a MARK I containment

International Nuclear Information System (INIS)

Chien, D.N.; Hanson, D.J.

1991-05-01

In support of the US Nuclear Regulatory Commission Accident Management Research Program, information needs during severe accidents have been evaluated for Boiling Water Reactors (BWRs) with MARK 1 containments. This evaluation was performed using a methodology that identifies plant information needs necessary for personnel to: (a) diagnose that an accident is in progress, (b) select and implement strategies to prevent or mitigate the accident, and (c) monitor the effectiveness of these strategies. The information needs and capabilities identified are intended to form a basis for more comprehensive information needs assessments. The assessments will be performed during the analysis and development of specific strategies, which will be used in accident management prevention and mitigation. 3 refs., 4 figs., 2 tabs

Risk factors affecting the severity of traffic accidents at Shanghai river-crossing tunnel.

Science.gov (United States)

Lu, Jian John; Xing, Yingying; Wang, Chen; Cai, Xiaonan

2016-01-01

With increasing traffic volume and urban development, increasing numbers of underground tunnels have been constructed to relieve conflict between strained land and heavy traffic. However, as more long tunnels are constructed, tunnel traffic safety is becoming increasingly serious. Thus, it is necessary to acquire their implications and impacts. This study examined 4,539 traffic accidents that have occurred in 14 Shanghai river-crossing tunnels for the period 2011-2012 and analyze the correlation between potential factors and accident injury severity. An ordered logit model was developed to examine the correlation between potential factors and accident injury severity. Results show that increased injury severity is associated with male drivers, drivers aged 65 years or older, accident time from midnight to dawn, weekends, wet road surface, goods vehicles, 3 or more vehicles, 4 or more lanes, middle speed limits (50-79 km/h), zone 3, extra-long tunnels (over 3,000 m), and maximum longitudinal gradient. This article aims to provide useful information for engineers to develop interventions and countermeasures to improve tunnel safety in China.

Construction of the jet-vortex condenser at the Kozloduy NPP units 3 and 4

International Nuclear Information System (INIS)

Genovski, I.; Bonev, B.; Grigorov, A.; Sabinov, S.; Petlov, M.

2003-01-01

The paper present the behavior of the accident localization system in case of pipeline rupture in the primary circuit of the units 3 and 4 after the implementation of the modernization program. The program includes installation of a jet-vortex condenser. The cases with double rapture of a pipeline D y 200 mm and D y 500 mm are described. In the result of the program implementation the radiation consequences are significantly limited due to the condenser playing the role of a filter during the first second of the accident as well as due to the low values of the pressure during the whole accident. Thus the modernization program fulfills its purpose to assure non-exceeding of the radiation limits in case of double rupture of a main circulation pipeline

Let's consider 'structural disaster' lying behind the Fukushima nuclear accident. From the viewpoint of sociology of science

International Nuclear Information System (INIS)

Matsumoto, Miwao

2015-01-01

As for the relationship between 'science and technology' and society, a huge gap exists between the question and expectation toward sociology given by ordinary people and the actual state of sociology. Sociology of science tries to provide a platform for transforming this kind of situation. What is currently talked about the Fukushima nuclear accident would be required to be revised according to the revealed fact in the future. Although there is such a limitation, what should be done at present is described from the viewpoint of sociology of science. The structure disaster is taken up from the viewpoint for not alienating the Fukushima accident, and the following five characteristics are involved in a complex manner. (1) To preserve precedent problems even if the precedents are wrong. (2) The complexity and mutual dependency of system amplify problems. (3) The informal norms of small groups hollow the official norms over a long term. (4) Stopgap measures based on ad hock presumption proliferate in face of measures against problems. (5) The secrecy principle obscures the whereabouts of responsibility throughout sectors. As for the way to operate SPEEDI (system for prediction of environmental emergency dose information) immediately after the Fukushima accident, this paper discusses the ideal way of responsibility attribution in consideration of the implication of structural disaster. In order not to invite such social conditions again as causing a serious accident due to the easy belief of unsafe conditions as safe, it is essential to create a mechanism that everyone publicly shares the issues associated with unlimited liability by means of the re-designing of the system. (A.O.)

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.)

[Accidents with biological material at West Paraná University Hospital].

Science.gov (United States)

Murofuse, Neide Tiemi; Marziale, Maria Helena Palucci; Gemelli, Lorena Moraes Goetem

2005-08-01

It is a descriptive and retrospective study with the purpose of investigating labor accidents with biological material involving workers and trainees occurred in 2003 and 2004 in a University Hospital of Parana. For data collection, the electronic form of the Net of Occupational Accidents Prevention - REPAT has been utilized. Out of the 586 hospital workers, there was a register of 20 (3,4%) injured workers in 2003 and 23 (3,8%) in 2004, representing an increase of 15% in the notifications from one year to the other.

Radiation accidents and defence of population

International Nuclear Information System (INIS)

Memmedov, A.M.

2002-01-01

), don't pollute the industry environ and surroundings, don't do real danger of reirradiation and pollution but demand investigation of their origin; accidents as a result when personal and persons from population have gotten a doze of outward irradiation (over PN); accidents as a result when industry or surroundings have been polluted (over PN);.accidents, as a result of outward and inside irradiation of personal, persons from population (over NPP-norms of radiation safety). Volume and character of measures by foregoing radiation accidents and their consequence depend on groups and scale of accident. They include investigation of the accident reasons; realization the radiation control for estimation degree of ionizing radiation pressure to personal and individual persons from population; rendering medical help to victims; definition of surroundings pollution level; equipment, industrial and habitable places; prevention of further influence of ionizing radiation to population and spreading radionuclides in surroundings; elimination of disrepairs and liquidation of radiation accident source. Radiation accident in the nuclear engineering establishments and industry have been divided into accident and proper-crash. At present international organizations have divided a school of crashes and accidents at NPP. According to that scale 3 levels of accidents and 4 levels of crashes have been chosen. The accidents have been qualified: insignificant (1 level), middle difficulty (2 level), serious (3 level), but crashes - within the NPP (4 level), at the risk of surroundings (5 level), difficult (6 level), global (7 level). Character, volume and forms of measures by defence of population in the crashes at NPP depend on both the level of crash and the concrete radiation situation and stage of crash development. Those measures include: notification about crash; rendering medical help to victims, primary measures of personal and population defence (cover, iodine precautions

Harmonic analysis of occupational-accident time-series as a part of the quantified risk evaluation in worksites: Application on electric power industry and construction sector

International Nuclear Information System (INIS)

Marhavilas, P.K.; Koulouriotis, D.E.; Spartalis, S.H.

2013-01-01

The development of an integrated risk analysis scheme, which will combine a well-considered selection of widespread techniques, would enable the companies to achieve efficient results on risk assessment. In this study, we develop a methodological framework (as a part of the quantified risk evaluation), by incorporating a new technique, that is implemented by the harmonic-analysis of time-series of occupational-accidents (called as HATS). Our objective is therefore, twofold: (i) the development of a new risk assessment framework (HATS technique) and the subsequent application of HATS on the worksites of electric power industry and construction sector, and (ii) the enrichment of the harmonic-analysis theoretical background, as far as the significance-level of spectral peaks is concerned, with fully-completed practical tables, that they have been produced by using the scientific literature. In fact, we apply HATS on occupational-accident time-series, which were (a) observed in the worksites of the Greek Public electric Power Corporation (PPC) and the Greek construction-companies (GCCs), and (b) recorded in great statistical-databases of PPC, and IKA (the Greek Social Insurance Institute/Ministry of Health), respectively. The results of HATS were tested statistically by using Shimshoni's significance-test. Moreover, the results of the comparative time/frequency-domain analysis of the accident time-series in PPC (for 1993–2009) and GCCs (for 1999–2007), prove that they are characterized by the existence of a periodic factor which (a) constitutes a permanent feature for the dynamic behavior of PPC's and GCCs' OHSS (occupational health and safety system), and (b) could be taken into account by risk managers in risk assessment, i.e., immediate suppressive measures must be taken place to abolish the danger source which is originated from the quasi-periodic appearance of the most important hazard sources

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

Epidemiology o.f· Traffic Accidents

African Journals Online (AJOL)

Accidents. An analysis of some 2 100 fatal traffic accidents gave the following results: males-79%; females-21%; a ratio of 4: 1. The high proportion of males to females killed in traffic accidents may be due to the fact that (a) more males commute daily in private and commercial vehicles;. (b) more females commute daily in ...

Analysis of metal fuel transient overpower experiments with the SAS4A accident analysis code

International Nuclear Information System (INIS)

Tentner, A.M.; Kalimullah; Miles, K.J.

1990-01-01

The results of the SAS4A analysis of the M7 TREAT Metal fuel experiment are presented. New models incorporated in the metal fuel version of SAS4A are described. The computational results are compared with the experimental observations and this comparison is used in the interpretation of physical phenomena. This analysis was performed using the integrated metal fuel SAS4A version and covers a wide range of events, providing an increased degree of confidence in the SAS4A metal fuel accident analysis capabilities

Containment accident analysis using CONTEMPT4/M0D2 compared with experimental data

International Nuclear Information System (INIS)

Metcalfe, L.J.; Hargroves, D.W.; Wells, R.A.

1978-01-01

CONTEMPT4/MOD2 is a new computer program developed to predict the long-term thermal hydraulic behavior of light-water reactor and experimental containment systems during postulated loss-of-coolant accident (LOCA) conditions. Improvements over previous containment codes include multicompartment capability and ice condenser analytical models. A program description and comparisons of calculated results with experimental data are presented

CarSim: Automatic 3D Scene Generation of a Car Accident Description

NARCIS (Netherlands)

Egges, A.; Nijholt, A.; Nugues, P.

2001-01-01

The problem of generating a 3D simulation of a car accident from a written description can be divided into two subtasks: the linguistic analysis and the virtual scene generation. As a means of communication between these two system parts, we designed a template formalism to represent a written

32 CFR 636.13 - Traffic accident investigation reports.

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Traffic accident investigation reports. 636.13... Stewart, Georgia § 636.13 Traffic accident investigation reports. In addition to the requirements in § 634... record traffic accident investigations on DA Form 3946 (Military Police Traffic Accident Report) and DA...

A preliminary study for the implementation of general accident management strategies

International Nuclear Information System (INIS)

Yang, Soo Hyung; Kim, Soo Hyung; Jeong, Young Hoon; Chang, Soon Heung

1997-01-01

To enhance the safety of nuclear power plants, implementation of accident management has been suggested as one of most important programs. Specially, accident management strategies are suggested as one of key elements considered in development of the accident management program. In this study, generally applicable accident management strategies to domestic nuclear power plants are identified through reviewing several accident management programs for the other countries and considering domestic conditions. Identified strategies are as follows; 1) Injection into the Reactor Coolant System, 2) Depressurize the Reactor Coolant System, 3) Depressurize the Steam Generator, 4) Injection into the Steam Generator, 5) Injection into the Containment, 6) Spray into the Containment, 7) Control Hydrogen in the Containment. In addition, the systems and instrumentation necessary for the implementation of each strategy are also investigated

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)

Analysis of Occupational Accidents in Underground and Surface Mining in Spain Using Data-Mining Techniques

Science.gov (United States)

Sanmiquel, Lluís; Bascompta, Marc; Rossell, Josep M.; Anticoi, Hernán Francisco; Guash, Eduard

2018-01-01

An analysis of occupational accidents in the mining sector was conducted using the data from the Spanish Ministry of Employment and Social Safety between 2005 and 2015, and data-mining techniques were applied. Data was processed with the software Weka. Two scenarios were chosen from the accidents database: surface and underground mining. The most important variables involved in occupational accidents and their association rules were determined. These rules are composed of several predictor variables that cause accidents, defining its characteristics and context. This study exposes the 20 most important association rules in the sector—either surface or underground mining—based on the statistical confidence levels of each rule as obtained by Weka. The outcomes display the most typical immediate causes, along with the percentage of accidents with a basis in each association rule. The most important immediate cause is body movement with physical effort or overexertion, and the type of accident is physical effort or overexertion. On the other hand, the second most important immediate cause and type of accident are different between the two scenarios. Data-mining techniques were chosen as a useful tool to find out the root cause of the accidents. PMID:29518921

Analysis of Occupational Accidents in Underground and Surface Mining in Spain Using Data-Mining Techniques

Directory of Open Access Journals (Sweden)

Lluís Sanmiquel

2018-03-01

Full Text Available An analysis of occupational accidents in the mining sector was conducted using the data from the Spanish Ministry of Employment and Social Safety between 2005 and 2015, and data-mining techniques were applied. Data was processed with the software Weka. Two scenarios were chosen from the accidents database: surface and underground mining. The most important variables involved in occupational accidents and their association rules were determined. These rules are composed of several predictor variables that cause accidents, defining its characteristics and context. This study exposes the 20 most important association rules in the sector—either surface or underground mining—based on the statistical confidence levels of each rule as obtained by Weka. The outcomes display the most typical immediate causes, along with the percentage of accidents with a basis in each association rule. The most important immediate cause is body movement with physical effort or overexertion, and the type of accident is physical effort or overexertion. On the other hand, the second most important immediate cause and type of accident are different between the two scenarios. Data-mining techniques were chosen as a useful tool to find out the root cause of the accidents.

Developing a comprehensive and accountable database after a radiological accident

International Nuclear Information System (INIS)

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

1986-09-01

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

Sleep Apnea Related Risk of Motor Vehicle Accidents is Reduced by Continuous Positive Airway Pressure: Swedish Traffic Accident Registry Data

Science.gov (United States)

Karimi, Mahssa; Hedner, Jan; Häbel, Henrike; Nerman, Olle; Grote, Ludger

2015-01-01

Study Objectives: Obstructive sleep apnea (OSA) is associated with an increased risk of motor vehicle accidents (MVAs). The rate of MVAs in patients suspected of having OSA was determined and the effect of continuous positive airway pressure (CPAP) was investigated. Design: MVA rate in patients referred for OSA was compared to the rate in the general population using data from the Swedish Traffic Accident Registry (STRADA), stratified for age and calendar year. The risk factors for MVAs, using demographic and polygraphy data, and MVA rate before and after CPAP were evaluated in the patient group. Setting: Clinical sleep laboratory and population based control (n = 635,786). Patients: There were 1,478 patients, male sex 70.4%, mean age 53.6 (12.8) y. Interventions: CPAP. Measurements and Results: The number of accidents (n = 74) among patients was compared with the expected number (n = 30) from a control population (STRADA). An increased MVA risk ratio of 2.45 was found among patients compared with controls (P accident risk was most prominent in the elderly patients (65–80 y, seven versus two MVAs). In patients, driving distance (km/y), EDS (Epworth Sleepiness score ≥ 16), short habitual sleep time (≤ 5 h/night), and use of hypnotics were associated with increased MVA risk (odds ratios 1.2, 2.1, 2.7 and 2.1, all P ≤ 0.03). CPAP use ≥ 4 h/night was associated with a reduction of MVA incidence (7.6 to 2.5 accidents/1,000 drivers/y). Conclusions: The motor vehicle accident risk in this large cohort of unselected patients with obstructive sleep apnea suggests a need for accurate tools to identify individuals at risk. Sleep apnea severity (e.g., apnea-hypopnea index) failed to identify patients at risk. Citation: Karimi M, Hedner J, Häbel H, Nerman O, Grote L. Sleep apnea related risk of motor vehicle accidents is reduced by continuous positive airway pressure: Swedish traffic accident registry data. SLEEP 2015;38(3):341–349. PMID:25325460

Severe accident recriticality analyses (SARA)

Energy Technology Data Exchange (ETDEWEB)

Frid, W. E-mail: wiktor.frid@ski.se; Hoejerup, F.; Lindholm, I.; Miettinen, J.; Nilsson, L.; Puska, E.K.; Sjoevall, H

2001-11-01

Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies, the following issues have been investigated in the SARA project: (1) the energy deposition in the fuel during super-prompt power burst; (2) the quasi steady-state reactor power following the initial power burst; and (3) containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality--both super-prompt power bursts and quasi steady-state power generation--for the range of parameters studied, i.e. with core uncovering and heat-up to maximum core temperatures of approximately 1800 K, and water flow rates of 45-2000 kg s{sup -1} injected into the downcomer. Since recriticality takes place in a small fraction of the core, the power densities are high, which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal g{sup -1}, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate of 2000 kg s{sup -1}. In most cases, however, the predicted energy deposition was smaller, below the regulatory limits for fuel failure, but close to or above recently observed thresholds for fragmentation and dispersion of high burn-up fuel. The highest calculated

Severe accident recriticality analyses (SARA)

International Nuclear Information System (INIS)

Frid, W.; Hoejerup, F.; Lindholm, I.; Miettinen, J.; Nilsson, L.; Puska, E.K.; Sjoevall, H.

2001-01-01

Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies, the following issues have been investigated in the SARA project: (1) the energy deposition in the fuel during super-prompt power burst; (2) the quasi steady-state reactor power following the initial power burst; and (3) containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality--both super-prompt power bursts and quasi steady-state power generation--for the range of parameters studied, i.e. with core uncovering and heat-up to maximum core temperatures of approximately 1800 K, and water flow rates of 45-2000 kg s -1 injected into the downcomer. Since recriticality takes place in a small fraction of the core, the power densities are high, which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal g -1 , was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate of 2000 kg s -1 . In most cases, however, the predicted energy deposition was smaller, below the regulatory limits for fuel failure, but close to or above recently observed thresholds for fragmentation and dispersion of high burn-up fuel. The highest calculated quasi steady

SAS3DC - A computer program to describe accidents in LMFBRs

International Nuclear Information System (INIS)

Angerer, G.; Arnecke, G.; Polch, A.

1981-02-01

The code system SAS3D - developed in the ANL - is at present the most adequate instrument for simulating accidents in the LMFBRs. SAS3DC is an improved version of this code system: the routine CLAZAS - modelling in SAS3D the motion of the fuel cladding - is replaced in the SAS3DC by the routine CMOT. CMOT describes the moving material not in the Lagrangian - as CLAZAS - but in the Eulerian system and is so able to register even small cladding-displacements. To complete the description of the SAS3DC-code the results of some sample problems are included. (orig.) [de

Containment Response Analysis for Equipment Qualification of Kori Nuclear Power Plant Unit 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Byun, Choong Sup; Song, Dong Soo; Hwang, Yong Jun [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Seo, Kwi Hyun; Song, Wan Jung [ENERGEO Inc., Sungnam (Korea, Republic of)

2006-07-01

Equipment that is used to perform a necessary safety function must be capable of maintaining functional operability under all service condition postulated to occur during the installed life for the time it is required. The pressure and temperature analyses for loss of coolant accident and main steam line break accident provide the bounding test envelope inside containment for the operability evaluation of safety equipment in harsh environmental. This paper describes the results of the containment pressure and temperature analysis for the equipment qualification (EQ) envelopes of Kori unit 3 and 4.

A highly predictive A 4 flavor 3-3-1 model with radiative inverse seesaw mechanism

Science.gov (United States)

Cárcamo Hernández, A. E.; Long, H. N.

2018-04-01

We build a highly predictive 3-3-1 model, where the field content is extended by including several SU(3) L scalar singlets and six right handed Majorana neutrinos. In our model the {SU}{(3)}C× {SU}{(3)}L× U{(1)}X gauge symmetry is supplemented by the {A}4× {Z}4× {Z}6× {Z}16× {Z}16{\\prime } discrete group, which allows to get a very good description of the low energy fermion flavor data. In the model under consideration, the {A}4× {Z}4× {Z}6× {Z}16× {Z}16{\\prime } discrete group is broken at very high energy scale down to the preserved Z 2 discrete symmetry, thus generating the observed pattern of SM fermion masses and mixing angles and allowing the implementation of the loop level inverse seesaw mechanism for the generation of the light active neutrino masses, respectively. The obtained values for the physical observables in the quark sector agree with the experimental data, whereas those ones for the lepton sector also do, only for the case of inverted neutrino mass spectrum. The normal neutrino mass hierarchy scenario of the model is ruled out by the neutrino oscillation experimental data. We find an effective Majorana neutrino mass parameter of neutrinoless double beta decay of m ee = 46.9 meV, a leptonic Dirac CP violating phase of -81.37° and a Jarlskog invariant of about 10-2 for the inverted neutrino mass hierarchy. The preserved Z 2 symmetry allows for a stable scalar dark matter candidate.

THE WORK IN INTERIOR OF BAHIA: ASSESSMENT FOR REPORTING ACCIDENTS AT WORK

Directory of Open Access Journals (Sweden)

Cleber Souza de Jesus

2010-07-01

Full Text Available The relationship between work and health are interconnected to a variety of situations, characterized by different stages of technological incorporation, multiple forms of organization and management, and a precarious employment relation, reflected on morbidity and mortality of workers. Thus, this study aimed to identify the profile of work accidents from the chips of communication of occupational accidents notified in the regional occupational health center in Jequié/BA. A cross-sectional study was conducted for year 2006. Data analysis was performed with SPSS software 11.0. Were analyzed 141 records of communicationof occupational accidents, of which 57.9% were i ssued by theemployer, there was a male predominance (68.1%, unmarried individuals (52.5% living in urban area (90.8%, with emphasis on the affections of the upper limbs (55.3%. Regarding foroccupational aspects, 63.8% of diagnoses were for neuromuscular disorders. Removals to treatment 85.8% of workers, as well as 48.2% of reports were from the sector of manufacturing industry. Statistically significant association was found between sex and body part affected with the type of accident (p <0.05.Therefore, the composition of the accidents, according to its severity and its various types of classification, have shown that these do not constitute a single and isolated event, being unevenly distributed. It becomes essential the valorization of employee as integral and fundamental part to the economic development process of the country. Public policies to encourage prevention and health promotion in workplaces should be implemented, aiming at a possible change in the scenario of health workers in the interior of Bahia.

Accidents with biological material and immunization against hepatitis B among students from the health area.

Science.gov (United States)

Gir, Elucir; Netto, Jeniffer Caffer; Malaguti, Silmara Elaine; Canini, Silvia Rita Marin da Silva; Hayashida, Miyeko; Machado, Alcyone Artioli

2008-01-01

Undergraduate students from the health area often handle piercing-cutting instruments in their academic activities, which exposes them to the risk of contracting infections. This study aimed to analyze accidents with biological material among these students. Out of 170 accidents registered, 83 (48.8%) occurred with Dentistry students, 69 (40.6%) with Medical students, 11 (6.5%) with Nursing students and in 06 (3.5%) of the cases there was no such information in the files. Most accidents, 106 (62.4%), occurred with students from private schools and 55 (32.3%) with those from public schools. Percutaneous accidents occurred in 133 (78.2%) exposures and there was immediate search for specialized health care in only 38 (21.3%) accidents. In 127 (74.7%) accidents, the immunization schedule against hepatitis B was complete. Therefore, schools need to offer courses and specific class subjects regarding biosafety measures, including aspects related to immunization, especially the vaccine against hepatitis B.

SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4

International Nuclear Information System (INIS)

Hagrman, D.T.

1995-06-01

The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light -- water-reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume, Volume IV, describes the material properties correlations and computer subroutines (MATPRO) used by SCDAP/RELAP5. formulation of the materials properties are generally semi-empirical in nature. The materials property subroutines contained in this document are for uranium, uranium dioxide, mixed uranium-plutonium dioxide fuel, zircaloy cladding, zirconium dioxide, stainless steel, stainless steel oxide, silver-indium-cadmium alloy, cadmium, boron carbide, Inconel 718, zirconium-uranium-oxygen melts, fill gas mixtures, carbon steel, and tungsten. This document also contains descriptions of the reaction and solution rate models needed to analyze a reactor accident

41 CFR 101-39.407 - Accident records.

Science.gov (United States)

2010-07-01

...-INTERAGENCY FLEET MANAGEMENT SYSTEMS 39.4-Accidents and Claims § 101-39.407 Accident records. If GSA's records... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Accident records. 101-39.407 Section 101-39.407 Public Contracts and Property Management Federal Property Management...

Manual for the energy consultant: Sector profiles: Part 3: Non Food and other services; Handboek voor de energieconsulent: Brancheprofielen: Deel 3: Non Food en overige dienstverlening

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

At the Information Center for the Built Environment of the Netherlands Agency for Energy and Environment (NOVEM) in Apeldoorn, Netherlands, manuals are available in the following categories: (1) Basic Information (f.e. indicators, climate data, calculation factors and examples); (2) Information on Energy Management (`seven-steps plan`, tasks for the energy consultant and the client, aftercare); (3) Information of the Target Groups (overall characteristics, energy conservation options, methods and approaches); and (4) sector profiles. The aim of this manual is to support the energy consultant in developing an energy strategy for the non-food and service sector. Special attention is paid to the home furnishing sector, the textile retail trade, service stations, repair services, beauty parlors, do-it-yourself stores, and dry-cleaners

Injury severity and seating position in accidents with German EMS helicopters.

Science.gov (United States)

Hinkelbein, Jochen; Spelten, Oliver; Neuhaus, Christopher; Hinkelbein, Mandy; Özgür, Enver; Wetsch, Wolfgang A

2013-10-01

Accident rates and fatality rates for Helicopter Emergency Medical Service (HEMS) missions have been investigated recently, but none of these studies considered the influence of the seating position in the helicopter. The aim of the present descriptive and observational study was to analyze injury severity depending on the seating position during HEMS accidents in Germany. Data from the German Federal Agency for Flight Accident Investigation was gathered for a period of 40 years (from 1970 to 2009). The seating position in the aircraft during the accident and the resulting injury severity (i.e., 1=no; 2=slight; 3=severe; and 4=fatal) were recorded. Injury severity was compared using the Fisher's exact test. P values accidents were investigated (n=61 accidents did not lead to any injuries in the occupants, n=7 accidents resulted in minor, and n=6 in severe injuries, and lethal injuries resulted from n=15 accidents). The occupant in the "patient" position was most likely to suffer from deadly injuries (44.9%), followed by the HEMS crew member rear seat (25.0%), compared to lower lethality rates in the other seating positions (9.4-11.2%). Sitting on the HEMS crew member rear seat also was associated with the highest percentage of severe and minor injuries (12.5% each). In HEMS accidents, the patients' position and the HEMS crew member rear seat were found to be at the highest risk for fatal or severe injuries. These results support the urgent requirement of a large international data base for HEMS accidents as a basis for further studies to improve the safety in HEMS missions. Copyright © 2013 Elsevier Ltd. All rights reserved.

Reporting and analysis of NMAs - a tool for accidents prevention (case studies)

International Nuclear Information System (INIS)

Chougaonkar, A.; Vincy, M.U.; Pisharody, N.N.; Varshney, Aloke; Khot, Pankaj

2016-01-01

Nuclear Power Corporation of India Limited (NPCIL) is a Public Sector Enterprise under Department of Atomic Energy (DAE), Government of India. NPCIL is operating 21 nuclear power plants and 5 nuclear power plants are under construction. NPCIL has an established organizational set-up to implement Industrial and Fire Safety requirements as per the applicable statutes and regulations. As part of industrial activities, sometimes there could be accidents due to unsafe conditions, unsafe acts or both. However, most of the accidents are preventable. The organization has issued a Head Quarter Instruction (HQI) for reporting and investigation of all types of accidents including Near Miss Accidents (NMAs). NMAs are the unplanned events, which have occurred, but did not result into injury or damage. It is very important that all NMAs are identified, reported, analyzed and corrective action taken to eliminate unsafe conditions or unsafe acts, which have caused these incidents. 'Reporting, analyzing and correcting the causes of NMAs' is one of such efforts enhanced in NPCIL to prevent accidents. Also, there exists a system for dissemination of information on incidents including NMAs among the NPCIL Units. This paper gives case study on some NMAs reported at NPCIL units during the year -2015 demonstrating the importance of the accidents prevention program. (author)

THE CONSTRUCTION SECTOR CHAIN DISASTER THEORY AND A CASE STUDY

Directory of Open Access Journals (Sweden)

Amir S. GOHARDANI

2013-11-01

Full Text Available Management approaches are of paramount importance in the built environment. Efficient management approaches ensure timely project completions and consequently lead to economic growth. However, there are also challenges within the construction industry that could lead to disastrous effects and to significant death tolls. In this article, the Construction Sector Chain Disaster Theory (CSCDT is presented. This theory mirrors the construction sector as an ongoing disaster zone. In light of CSCDT, a limited number of past accidents within the global construction industry will be investigated with respect to the building blocks of the theory and in view of inadequate management practices that have made positive contributions to triggering disasters. The identified shortcomings will enable a more comprehensive approach to management in favor of disaster minimization in the construction sector.

Estimation of cost per severe accident for improvement of accident protection and consequence mitigation strategies

International Nuclear Information System (INIS)

Silva, Kampanart; Ishiwatari, Yuki; Takahara, Shogo

2013-01-01

To assess the complex situations regarding the severe accidents such as what observed in Fukushima Accident, not only radiation protection aspects but also relevant aspects: health, environmental, economic and societal aspects; must be all included into the consequence assessment. In this study, the authors introduce the “cost per severe accident” as an index to analyze the consequences of severe accidents comprehensively. The cost per severe accident consists of various costs and consequences converted into monetary values. For the purpose of improvement of the accident protection and consequence mitigation strategies, the costs needed to introduce the protective actions, and health and psychological consequences are included in the present study. The evaluations of these costs and consequences were made based on the systematic consequence analysis using level 2 and 3 probabilistic safety assessment (PSA) codes. The accident sequences used in this analysis were taken from the results of level 2 seismic PSA of a virtual 1,100 MWe BWR-5. The doses to the public and the number of people affected were calculated using the level 3 PSA code OSCAAR of Japan Atomic Energy Agency (JAEA). The calculations have been made for 248 meteorological sequences, and the outputs are given as expectation values for various meteorological conditions. Using these outputs, the cost per severe accident is calculated based on the open documents on the Fukushima Accident regarding the cost of protective actions and compensations for psychological harms. Finally, optimized accident protection and consequence mitigation strategies are recommended taking into account the various aspects comprehensively using the cost per severe accident. The authors must emphasize that the aim is not to estimate the accident cost itself but to extend the scope of “risk-informed decision making” for continuous safety improvements of nuclear energy. (author)

Instrumentation availability for a pressurized water reactor with a large dry containment during severe accidents

International Nuclear Information System (INIS)

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

1991-03-01

In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, the availability of instruments to supply accident management information during a broad range of severe accidents is evaluated for a pressurized water reactor with a large dry containment. Results from this evaluation include the following: (a) identification of plant conditions that would impact instrument performance and information needs during severe accidents, (b) definition of envelopes of parameters that would be important in assessing the performance of plant instrumentation for a broad range of severe accident sequences, and (c) assessment of the availability of plant instrumentation during severe accidents. 16 refs., 3 figs., 4 tabs

Sleep habits and road traffic accident risk for Iranian occupational drivers.

Science.gov (United States)

Ebrahimi, Mohammad Hossein; Sadeghi, Masoumeh; Dehghani, Mohsen; Niiat, Khosro Sadegh

2015-01-01

The aim of this study is to assess the sleep quality and sleep disorders (prevalence of obstructive sleep apnea and sleepiness) among occupational drivers in Iran and to determine which demographic factors and occupational habits are linked to road traffic accidents. In this analytic cross-sectional study 556 occupational road drivers from Shahroud city (in the northeast of Iran) participated, upon a prior verbal informed consent, during 2013-2014. The Pittsburgh Sleep Quality Index (PSQI) standard questionnaire that scored on 7 point scale, the 8-item Epworth Sleepiness Scale (ESS) questionnaire and the 8-question STOP-Bang questionnaire along with demographic information and occupational data were used. To explore the independent factors associated with odds of poor sleep quality and road accident, multiple logistic regression models were used. Prevalence of previous road accidents, sleepiness while driving, and obstructive sleep apnea scored ≥ 3 in the study, and drivers accounted for 23.8%, 29%, and 24.8%, respectively. The global mean score of sleep quality and excessive sleepiness score were 5.2 and 4.8, respectively. The main factors related to the odds of poor sleep quality were snoring (odds ratio (OR) = 2.34; 95% confidence interval (CI): 1.15-4.77), smoking (OR = 2.12; 95% CI: 1.15-3.97), and driving times in a day (OR = 1.12; 95% CI: 1.03-1.21). The Epworth Sleepiness Scale (OR = 1.13; 95% CI: 1.07-1.23) and suffering from apnea (OR = 4.89; 95% CI: 1.07-23.83) were the best predictors for odds (increased risk) of road accidents. A considerable proportion of Iranian drivers had records of road accidents; poor sleep quality, sleepiness while driving, and sleep disorder breathing (obstructive sleep apnea - OSA). Snoring, smoking, driving time in a day, excessive sleepiness, and presumably apnea increase the odds of poor sleep quality and road traffic accident for Iranian occupational drivers. This work is available in Open Access model and licensed under

Probabilistic Accident Progression Analysis with application to a LMFBR design

International Nuclear Information System (INIS)

Jamali, K.M.

1982-01-01

A method for probabilistic analysis of accident sequences in nuclear power plant systems referred to as ''Probabilistic Accident Progression Analysis'' (PAPA) is described. Distinctive features of PAPA include: (1) definition and analysis of initiator-dependent accident sequences on the component level; (2) a new fault-tree simplification technique; (3) a new technique for assessment of the effect of uncertainties in the failure probabilities in the probabilistic ranking of accident sequences; (4) techniques for quantification of dependent failures of similar components, including an iterative technique for high-population components. The methodology is applied to the Shutdown Heat Removal System (SHRS) of the Clinch River Breeder Reactor Plant during its short-term (0 -2 . Major contributors to this probability are the initiators loss of main feedwater system, loss of offsite power, and normal shutdown

Report on a radiotherapy underdose accident

Energy Technology Data Exchange (ETDEWEB)

Christodoulides, G; Christofides, S [Medical Physics Department, Nicosia General Hospital, 1450 Nicosia (Cyprus)

1999-12-31

Reporting information on accidents and incidents involving radiation sources provides a body of knowledge which can help to prevent accidents of a similar nature. Accident information has to be made available to users, manufacturers and regulators; An international effort to pool and analyse incident and accident information will provide more complete and reliable indicators of root causes and trends and recommendations for future accident avoidance. An accident due to human error involving a superficial x-ray therapy machine and patients treated for postoperative breast cancer is reported here. 43 women receiving radiotherapy treatment have received significantly less radiation dose than the prescribed dose. The worst dose percentage within the radiation field was 20% of the prescribed dose. The worst dose percentage on the operation scar of the breast was 52% of the prescribed radiation dose. The response to accidents/incidents in radiotherapy is discussed. (authors) 4 refs., 5 figs., 1 tabs.

Cost per severe accident as an index for severe accident consequence assessment and its applications

International Nuclear Information System (INIS)

Silva, Kampanart; Ishiwatari, Yuki; Takahara, Shogo

2014-01-01

The Fukushima Accident emphasizes the need to integrate the assessments of health effects, economic impacts, social impacts and environmental impacts, in order to perform a comprehensive consequence assessment of severe accidents in nuclear power plants. “Cost per severe accident” is introduced as an index for that purpose. The calculation methodology, including the consequence analysis using level 3 probabilistic risk assessment code OSCAAR and the calculation method of the cost per severe accident, is proposed. This methodology was applied to a virtual 1,100 MWe boiling water reactor. The breakdown of the cost per severe accident was provided. The radiation effect cost, the relocation cost and the decontamination cost were the three largest components. Sensitivity analyses were carried out, and parameters sensitive to cost per severe accident were specified. The cost per severe accident was compared with the amount of source terms, to demonstrate the performance of the cost per severe accident as an index to evaluate severe accident consequences. The ways to use the cost per severe accident for optimization of radiation protection countermeasures and for estimation of the effects of accident management strategies are discussed as its applications. - Highlights: • Cost per severe accident is used for severe accident consequence assessment. • Assessments of health, economic, social and environmental impacts are included. • Radiation effect, relocation and decontamination costs are important cost components. • Cost per severe accident can be used to optimize radiation protection measures. • Effects of accident management can be estimated using the cost per severe accident

46 CFR 97.30-5 - Accidents to machinery.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Accidents to machinery. 97.30-5 Section 97.30-5 Shipping... Reports of Accidents, Repairs, and Unsafe Equipment § 97.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use of...

HIV surveillance in needlestick accidents with health workers - doi: 10.5020/18061230.2010.p325

Directory of Open Access Journals (Sweden)

Janete Lane Amadei

2012-01-01

Full Text Available Objective: To characterize the occurrence of needlestick accidents with health professionals submitted to rapid HIV tests. Methods: A descriptive, epidemiological study, carried out by notification of the occurrence of needlestick accidents in the Epidemiology Sector of the State Health Secretariat, in 2008. The following variables were assessed: gender, age, exposed biological material, type of exposure, source patient, and injured patient, progression of the case, accident situation, and use of personal protective equipment (PPE, 180 days serology and occupational area. Results: There have been reports of 143 accidents, prevailing in nursing, female, 20 to 30 years, involving the blood and biological material by percutaneous puncture. We found no standardization in the use of PPE. The HIV test revealed no positive cases. Conclusion: This study helped to characterize the occurrence of accidents reported in health care professionals and evaluate the protocol of care given. It also revealed non-contamination by HIV.

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

International Nuclear Information System (INIS)

Dubiau, Ph.

2007-01-01

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

A Preliminary Study on the Containment Integrity following BIT Removal for Kori NPP Unit 3,4

Energy Technology Data Exchange (ETDEWEB)

Song, Dong Soo; Byun, Choong Sup [KEPRI, Nuclear Power Generation Laboratory, Daejeon (Korea, Republic of); Jo, Jong Young [ENERGEO Inc., Sungnam (Korea, Republic of)

2008-05-15

The Boron Injection Tank (BIT) is to provide high concentrated boric acid to the reactor in order to mitigate the consequences of postulated Main Steam Line Break accidents (MSLB). Although BIT plays an important role in mitigating the accident, high concentration of 20,000ppm causes valve leakage, pipe clog, precipitation and continuous heat tracing have to be provided. This paper is for the feasibility study of containment integrity using CONTEMPT code for BIT removal of Kori Nuclear Power Plant (NPP) Unit 3, 4.

A Preliminary Study on the Containment Integrity following BIT Removal for Kori NPP Unit 3,4

International Nuclear Information System (INIS)

Song, Dong Soo; Byun, Choong Sup; Jo, Jong Young

2008-01-01

The Boron Injection Tank (BIT) is to provide high concentrated boric acid to the reactor in order to mitigate the consequences of postulated Main Steam Line Break accidents (MSLB). Although BIT plays an important role in mitigating the accident, high concentration of 20,000ppm causes valve leakage, pipe clog, precipitation and continuous heat tracing have to be provided. This paper is for the feasibility study of containment integrity using CONTEMPT code for BIT removal of Kori Nuclear Power Plant (NPP) Unit 3, 4

An analysis on human factor issues in criticality accident at a uranium processing plant. Investigation on human behavior contributing to the criticality accident. Interim report

International Nuclear Information System (INIS)

Sasou, Kuonihide; Goda, Hideki; Hirotsu, Yuko

1999-01-01

At 10:30 am, September 30th, 1999, a criticality accident occurred in a conversion building of a uranium processing plant in Tokai, Ibaraki prefecture. 69 people including 3 workers who then worked at the building, 3 fire fighters who dispatched to rescue them were exposed to the radiation. People with a 350 m-radius of the site were recommended to evacuate themselves from the region to a temporarily prepared evacuation center. And about one hundred thousand people within a 10 km-radius were also advised to stay inside of their home. Nuclear Safety Commission's Accident Investigation Committee is investigating causes of this accident and have been revealing that deviation from government-authorized processing method and negligence of its illegal procedure had contributed to the accident. The influence of this accident is expanding not only to the plant operating company, local people but also to Japanese nuclear power policy, the whole nuclear industry in Japan. Especially pervasion of 'Safety Culture' is strongly being required. This report analyses latent factors of some human behavior directly contributing to the criticality accident. It also mentions that 4 critical points on the poor climate for safety in the work place, the inadequate safety management, the unsuitable equipment and the production-biased company's policy are the latent factors of this accident. It also finds that the poor climate and the production-biased policy are the most important factors. It can be said that some people directly or indirectly having caused the accident are the victims of them. (author)

Containment severe accident thermohydraulic phenomena

International Nuclear Information System (INIS)

Frid, W.

1991-08-01

This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phenomenological knowledge, including an account of relevant experimental investigations and to discuss, to some extent, the modelling approach used in the MAAP 3.0 computer code. The MAAP code has been used in Sweden as the main tool in the analysis of severe accidents. The dependence of the containment accident progression and containment phenomena on the initial conditions, which in turn are heavily dependent on the in-vessel accident progression and phenomena as well as associated uncertainties, is emphasized. The report is in three parts dealing with: * Swedish reactor containments, the severe accident mitigation programme in Sweden and containment accident progression in Swedish PWRs and BWRs as predicted by the MAAP 3.0 code. * Key non-energetic ex-vessel phenomena (melt fragmentation in water, melt quenching and coolability, core-concrete interaction and high temperature in containment). * Early containment threats due to energetic events (hydrogen combustion, high pressure melt ejection and direct containment heating, and ex-vessel steam explosions). The report concludes that our understanding of the containment severe accident progression and phenomena has improved very significantly over the parts ten years and, thereby, our ability to assess containment threats, to quantify uncertainties, and to interpret the results of experiments and computer code calculations have also increased. (au)

Fission product behaviour in severe accidents

International Nuclear Information System (INIS)

Jokiniemi, J.; Auvinen, A.; Maekynen, J.; Valmari, T.

1998-01-01

The understanding of fission product (FP) behaviour in severe accidents is important for source term assessment and accident mitigation measures. For example in accident management the operator needs to know the effect of different actions on the behaviour and release of fission products. At VTT fission product behaviour have been studied in different national and international projects. In this presentation the results of projects in EU funded 4th framework programme Nuclear Fission Safety 1994-1998 are reported. The projects are: fission product vapour/aerosol chemistry in the primary circuit (FI4SCT960020), aerosol physics in containment (FI4SCT950016), revaporisation of test samples from Phebus fission products (FI4SCT960019) and assessment of models for fission product revaporisation (FI4SCT960044). Also results from the national project 'aerosol experiments in the Victoria facility' funded by IVO PE and VTT Energy are reported

Statistical Analysis And Treatment Of Accident Black Spots: A Case Study Of Nandyal Mandal

Science.gov (United States)

Sudharshan Reddy, B.; Vishnu Vardhan Reddy, L.; Sreenivasa Reddy, G., Dr

2017-08-01

Background: Increased, economic activity raised the consumption levels of the people across the country. This created scope for increase in travel and transportation. The increase in the vehicles since last 10 years has put lot of pressure on the existing roads and ultimately resulting in road accidents. Nandyal Mandal is located in the Kurnool district of Andhra Pradesh and well developed in both agricultural and industrial sectors after Kurnool. 567 accidents occurred in the last seven years at 143 locations shows the severity of the accidents in the Nandyal Mandal. There is a need to carry out some work in the Nandyal Mandal to improve the accidents black spots for reducing the accidents. Methods: Last seven years (2010-2016) of accident data collected from Police Stations. Weighted Severity Index (WSI), a scientific method is used for identifying the accident black spots. Statistical analysis has carried out for the collected data using Chi-Square Test to determine the independence of accidents with other attributes. Chi-Square Goodness of fit test conducted for test whether the accidents are occurring by chance or following any pattern. Results: WSI values are determined for the 143 locations. The Locations with high WSI are treated as accident black spots. Five black spots are taken for field study. After field observations and interaction with the public, some improvements are suggested for improving the accident black spots. There is no relationship between the severity of accidents and the other attributes like month, season, day, hours in day and the age group except type of vehicle. Road accidents are distributed throughout the Year, Month and Season. Road accidents are not distributed throughout the day.

Analysis of occupational accidents with biological material among professionals in pre-hospital services.

Science.gov (United States)

de Oliveira, Adriana Cristina; Paiva, Maria Henriqueta Rocha Siqueira

2013-02-01

To estimate the prevalence of accidents due to biological material exposure, the characteristics and post-accident conduct among professionals of pre-hospital services of the four municipalities of Minas Gerais, Brazil. A cross-sectional study, using a structured questionnaire that was developed to enable the calculation of prevalence, descriptive analysis and analytical analysis using logistic regression. The study included 228 professionals; the prevalence of accidents due to biological material exposure was 29.4%, with 49.2% percutaneous, 10.4% mucousal, 6.0% non-intact skin, and 34.4% intact skin. Among the professionals injured, those that stood out were nursing technicians (41.9%) and drivers (28.3%). Notification of the occurrence of the accident occurred in 29.8% of the cases. Percutaneous exposure was associated with time of work in the organization (OR=2.51, 95% CI: 1.18 to 5.35, paccidents with biological material should be encouraged, along with professional evaluation/monitoring.

Severe accident assessment. Results of the reactor safety research project VAHTI

International Nuclear Information System (INIS)

Sairanen, R.

1997-10-01

The report provides a summary of the publicly funded nuclear reactor safety research project Severe Accident Management (VAHTI). The project has been conducted at the Technical Research Centre of Finland (VTT) during the years 1994-96. The main objective was to assist the severe accident management programmes of the Finnish nuclear power plants. The project was divided into five work packages: (1) thermal hydraulic validation of the APROS code, (2) core melt progression within a BWR pressure vessel, (3) failure mode of the BWR pressure vessel, (4) Aerosol behaviour experiments, and (5) development of a computerized severe accident training tool

A Web-based survey on students' conceptions of 'accident'.

Science.gov (United States)

Blank, Danilo; Hohgraefe Neto, Guilherme; Grando, Elisa; Siqueira, Pauline Z; Lunkes, Roberta P; Pietrobeli, João Leonardo; Marzola, Norma Regina; Goldani, Marcelo Z

2009-12-01

To report the implementation of an open source web survey application and a case study of its first utilisation, particularly as to aspects of logistics and response behaviour, in a survey of Brazilian university students' conceptions about injury causing events. We developed an original application capable of recruiting respondents, sending personal e-mail invitations, storing responses and exporting data. Students of medical, law, communication and education schools were asked about personal attributes and conceptions of the term accident, as to associations and preventability. The response rate was 34.5%. Half of the subjects responded by the second day, 66.3% during the first week. Subjects around 4.2% (95% CI 3.3-5.4) refused to disclose religious persuasion, and 19.2% (95% CI 17.2-21.3) refused to disclose political persuasion, whereas only 2.8% (95% CI 2.1-3.8), on average, refused to answer questions on conceptions and attitudes. There was no significant difference between early and late respondents in respect to selected attributes and conceptions of accident (P-value varied from 0.145 to 0.971). The word accident evoked the notion of preventability to 85.1% (95% CI 83.2 to 87.0) of the subjects, foreseeability to 50.3% (95% CI 47.7-53.0), fatality to 15.1% (95% CI 13.3-17.1) and intentionality to 2.3% (95% CI 1.6-3.2). Web surveying university students' conceptions about injuries is feasible in a middle-income country setting, yielding response rates similar to those found in the literature.

Accident management: What is it and how do you do it?

International Nuclear Information System (INIS)

Henry, Robert E.; Hammersley, Robert J.

2004-01-01

Accident management is the composite of those actions that would prevent, stop and/or mitigate a severe accident in a nuclear power plant. Since they act to prevent core damage, the Emergency Operating Procedures (EOPs) are an integral part of accident management. Each of the Owners Groups have developed EOPs that are well thought out for instructing the operator to respond to accident conditions which could threaten the core. However, for those very low probability events in which the core could be uncovered and damaged, accident management actions arise from a logical evaluation of possible actions (strategies) for recovering from the accident state and protecting the public health and safety. To understand the character of accident management it is first necessary to define: 1. What is threatened as a result of the accident? 2. Fundamentally, what needs to be protected? 3. What is known during an accident? 4. What have we learned from the TMI-2 accident? 5. What have we learned from the plant specific IPEs? Once these subjects are reviewed on a utility specific and plant specific basis, accident management actions become relatively straightforward and likely can be effectively addressed using the total capability available in a given design. This paper discusses these five questions in a global manner with the aim being to aid plant specific implementation. (author)

INSTITUTIONAL SUPPORT SOSIAL INSURANCE AGAINST OCCUPATIONAL ACCIDENTS IN UKRAINE

Directory of Open Access Journals (Sweden)

O. Gamankova

2015-04-01

Full Text Available The paper deals with the peculiarities of formation of relationships in the reform of social security. Examines institutional support provided social insurance accidents with the latest trends reform of the sector. The study notes that the organization of social security is lost insurance principle, the general principles of the Social Insurance Institute, added other excess principles that form the basis for misappropriation of funds and various abuses. These problems are urgent and require research. The paper reviews the basic principles to achieve the optimal balance of economic and social needs of providing social protection of citizens of Ukraine. The results emphasize the need for heightened security procedures for consolidation of compulsory state social insurance against industrial accidents and the State Mandatory Social Insurance against disability.

Development of a severe accident training simulator using a MELCOR code

International Nuclear Information System (INIS)

Kim, Ko Ryu; Jeong, Kwang Sub; Ha, Jae Joo; Jung, Won Dae

2002-03-01

Nuclear power plants' severe accidents are, despite of their rareness, very important in safety aspects, because of their huge damages when occurred. For the appropriate execution of severe accident strategy, more information for decision-making are required because of the uncertainties included in severe accidents. Earlier NRC raised concerns over severe accident training in the report NUREC/CR-477, and accordingly, developing effective training tools for severe accident were emphasized. In fact the training tools were requested from industrial area, nevertheless, few training tools were developed due to the uncertainties in severe accidents, lacks of analysis computer codes and technical limitations. SATS, the severe accident training simulator, is developed as a multi-purpose tools for severe accident training. SATS uses the calculation results of MELCOR, an integral severe accident analysis code, and with the help of SL-GMS graphic tools, provides dynamic displays of severe accident phenomena on the terminal of IBM PC. It aimed to have two main features: one is to provide graphic displays to represent severe accident phenomena and the other is to process and simulate severe accident strategy given by plant operators and TSC staffs. Severe accident strategies are basically composed of series of operations of available pumps, valves and other equipments. Whenever executing strategies with SATS, the trainee should follow the HyperKAMG, the on line version of the recently developed severe accident guidance (KAMG). Severe accident strategies are closely related to accidents scenarios. TLOFW and LOCA , two representative severe accident scenarios of Uljin 3,4, are developed as a built-in scenarios of SATS. Although SATS has some minor problems at this time, we expect SATS will be a good severe accident training tool after the appropriate addition of accident scenarios. Moreover, we also expect SATS will be a good advisory tool for the severe accident research

National plan of response to a major nuclear or radiological accident

International Nuclear Information System (INIS)

2014-02-01

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

[Accidents and injuries in the EU. Results of the EuroSafe Reports].

Science.gov (United States)

Bauer, R; Steiner, M; Kisser, R; Macey, S M; Thayer, D

2014-06-01

Accidents and injuries are a relevant although largely preventable public health problem. Information on the causes of accidents is the basis for accident prevention and product safety. The current report "Injuries in the European Union", edited by EuroSafe, the European Association for Injury Prevention and Safety Promotion, is a summary of key statistics on accidents and injuries at the EU level. In addition to international data on cause of death, the data of the European Injury Data Base (IDB) in particular are presented. The IDB is a unique data source for the EU based on an internationally standardized dataset of external causes and circumstances of injuries, which is collected in the emergency department of hospitals. Thus, the IDB covers the entire spectrum of accidents and injuries in sufficient detail as is necessary for the derivation of preventive measures and the knowledge of involved products. The currently available IDB data are collected by the participating Member States (2012: Austria, Cyprus, Denmark, Germany, Italy, Latvia, Malta, The Netherlands, Norway, Portugal, Slovenia, and Sweden) in self-interest (i.e., without legal obligation) with the support of the EU health programs. The central database for the IDB is run by the European Commission and provides public access to the aggregated data of the participating countries. Currently, over 100 IDB hospitals in the EU upload around 300,000 cases per year into the EU database. The IDB contains information on all accident sectors (transport, workplace, school etc.) with a focus on leisure and sports accidents. Depending on the accident sector, up to 25 variables (activities, products involved, means of transport etc.) and often also short narratives are recorded for each case. The report shows that 40 million people are treated in a hospital annually in the EU after accidents and violence, and that about 233,000 people die as a consequence of injury. There are large differences between countries

High-sensitivity determination of radioactive cesium in Japanese foodstuffs. 3 years after the Fukushima accident

International Nuclear Information System (INIS)

Katsumi Shozugawa; Mayumi Hori; Motoyuki Matsuo

2016-01-01

We analyzed 134 Cs, 137 Cs and 40 K in 96 foodstuffs in supermarkets with high sensitivity over 3 years after Fukushima accident. Milk, yoghurt, rice, tea, salmon, cereal, blueberry, miso, and apples had a trace of 134 Cs and 137 Cs from 10 -3 to 100 Bq/kg, however, some mushrooms that were bought in the outer Fukushima prefecture were contaminated by radioactive cesium over the regulatory limit (100 Bq/kg). In view of the 134 Cs/ 137 Cs radioactivity ratio, we can conclude that 137 Cs detected in remote areas 300 km or more from Fukushima Nuclear power plant contained activity from Pre-Fukushima events such as Chernobyl accident (1986) and atmospheric nuclear explosions (from 1945). (author)

Modern principles used in conformity assessment of machinery from forestry sector

Directory of Open Access Journals (Sweden)

Antonov Anca Elena

2017-01-01

Full Text Available The paper is aiming to implement the general principles of risk prevention at employer’s level, with respect to occupational risks evaluation, the elimination of risk and accident factors, and information of workers which are using the machinery in the forestry sector. For the use of machinery in the forestry sector in terms of economic performance and a level of maximum safety, it is necessary to ensure the user guides set by the manufacturer in terms of commissioning, use and to provide appropriate safe working operations and interventions and to guarantee the technical and environmental requirements, including appropriate measures and means of protection against accidents and occupational disease. The impact of occupational risks for machinery used in this sector can be reduced through the application of modern principles in conformity assessment and certification and, where appropriate, through technical diagnostics and inspection, taking into account the provisions of the new Machinery Directive 2006/42 / EC which is imposing the obligation of manufacturer to implement conformity assessment procedures in accordance with the methods of assessment and verification of safety at the certification bodies, notified at the European Commission. The paper aims to develop modern technical tools for conformity assessment and verification of this category of machines used in the forestry sector that would provide prerequisite for increasing competitiveness of employers in the market economy. Applying these tools of modern technology for manufacturers and users of this category of machinery provides the necessary conditions for placing on the market of safe products with a appropriate safety level, in the intended using conditions, in order to guarantee the essential requirements for safety and health, technical and environmental conditions, including measures and means of protection. The result of this research is to develop technical tools needed to

Parameterization of the driving time in the evacuation or fast relocation model of an accident consequence code

International Nuclear Information System (INIS)

Pfeffer, W.; Hofer, E.; Nowak, E.; Schnadt, H.

1988-01-01

The model of protective measures in the accident consequence code system UFOMOD of the German Risk Study, Phase B, requires the driving times of the population to be evacuated for the evaluation of the dose received during the evacuation. The parameter values are derived from evacuation simulations carried out with the code EVAS for 36 sectors from various sites. The simulations indicated that the driving time strongly depends on the population density, whereas other influences are less important. It was decided to use different driving times in the consequence code for each of four population density classes as well as for each of three or four fractions of the population in a sector. The variability between sectors of a class was estimated from the 36 sectors, in order to derive subjective probability distributions that are to model the uncertainty in the parameter value to be used for any of the fractions in a particular sector for which an EVAS simulation has not yet been performed. To this end also the impact of the uncertainties in the parameters and modelling assumptions of EVAS on the simulated times was quantified using expert judgement. The distributions permit the derivation of a set of driving times to be used as so-called ''best estimate'' or reference values in the accident consequence code. Additionally they are directly applicable in an uncertainty and sensitivity analysis

Traffic Accidents on Slippery Roads

DEFF Research Database (Denmark)

Fonnesbech, J. K.; Bolet, Lars

2014-01-01

Police registrations from 65 accidents on slippery roads in normally Danish winters have been studied. The study showed: • 1 accident per 100 km when using brine spread with nozzles • 2 accidents per 100 km when using pre wetted salt • 3 accidents per 100 km when using kombi spreaders The results...... of accidents in normally Danish winter seasons are remarkable alike the amount of salt used in praxis in the winter 2011/2012. • 2.7 ton NaCl/km when using brine spread with nozzles • 5 ton NaCl/km when using pre wetted salt. • 5.7 ton NaCl/km when using kombi spreaders The explanation is that spreading...

LOFA [loss of flow accident] and LOCA [loss of coolant accident] in the TIBER-II engineering test reactor: Appendix A-4

International Nuclear Information System (INIS)

Sviatoslavsky, I.N.; Attaya, H.M.; Corradini, M.L.; Lomperski, S.

1987-01-01

This paper describes the preliminary analysis of LOFA (loss of flow accident) and LOCA (loss of coolant accident) in the TIBER-II engineering test reactor breeding shield. TIBER-II is a compact reactor with a major radius of 3 m and thus requires a thin, high efficiency shield on the inboard side. The use of tungsten in the inboard shield implies a rather high rate of afterheat upon plasma shutdown, which must be dissipated in a controlled manner to avoid the possibility of radioactivity release or threatening the investment. Because the shield is cooled with an aqueous solution, LOFA does not pose a problem as long as natural convection can be established. LOCA, however, has more serious consequences, particularly on the inboard side. Circulation of air by natural convection is proposed as a means for dissipating the inboard shield decay heat. The safety and environmental implications of such a scheme are evaluated. It is shown that the inboard shield temperature never exceeds 510 0 C following LOCA posing no hazard to reactor personnel and not threatening the investment. 7 refs., 6 figs

Postulated accidents

International Nuclear Information System (INIS)

Ullrich, W.

1980-01-01

This lecture on 'Postulated Accidents' is the first of a series of lectures on the dynamic and transient behaviour of nuclear power plants, especially pressurized water reactors. The main points covered will be: Reactivity Accidents, Transients (Intact Loop) and Loss of Cooland Accidents (LOCA) including small leak. This lecture will discuss the accident analysis in general, the definition of the various operational phases, the accident classification, and, as an example, an accident sequence analysis on the basis of 'Postulated Accidents'. (orig./RW)

A stochastic assessment of cavity flooding strategy involving operator action for Yonggwang 3 and 4 units

International Nuclear Information System (INIS)

Kim, J.; Yu, D.; Ha, J.

1997-01-01

The author presents a new approach to the evaluation of an accident management strategy when an operator action is involved. This approach classifies the failure in implementing a given strategy into 4 possible states, and provides their corresponding quantification methods: 1) the failure of a diagnosis and decision-making by operators, 2) the failure of taking an action following a correct diagnosis, 3) the failure of a system operation following an adequate action, and 4) the failure due to a delayed action. The proposed methods were applied to assess a cavity flooding strategy that uses containment spray system (CSS), and the result shows that the methods are more appropriate in evaluating accident management strategies when human actions are involved

First international workshop on severe accidents and their consequences. [Chernobyl Accident

Energy Technology Data Exchange (ETDEWEB)

1989-07-01

An international workshop on past severe nuclear accidents and their consequences was held in Dagomys region of Sochi, USSR on October 30--November 3, 1989. The plan of this meeting was approved by the USSR Academy of Sciences and by the USSR State Committee of the Utilization of Atomic Energy. The meeting was held under the umbrella of the ANS-SNS agreement of cooperation. Topics covered include analysis of the Chernobyl accident, safety measures for RBMK type reactors and consequences of the Chernobyl accident including analysis of the ecological, genetic and psycho-social factors. Separate reports are processed separately for the data bases. (CBS)

Accident management information needs

International Nuclear Information System (INIS)

Hanson, D.J.; Ward, L.W.; Nelson, W.R.; Meyer, O.R.

1990-04-01

In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate the accident, and monitor the effectiveness of these strategies. This report describes the methodology and presents an application of this methodology to a Pressurized Water Reactor (PWR) with a large dry containment. A risk-important severe accident sequence for a PWR is used to examine the capability of the existing measurements to supply the necessary information. The method includes an assessment of the effects of the sequence on the measurement availability including the effects of environmental conditions. The information needs and capabilities identified using this approach are also intended to form the basis for more comprehensive information needs assessment performed during the analyses and development of specific strategies for use in accident management prevention and mitigation. 3 refs., 16 figs., 7 tabs

Accident management information needs

Energy Technology Data Exchange (ETDEWEB)

Hanson, D.J.; Ward, L.W.; Nelson, W.R.; Meyer, O.R. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-04-01

In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate the accident, and monitor the effectiveness of these strategies. This report describes the methodology and presents an application of this methodology to a Pressurized Water Reactor (PWR) with a large dry containment. A risk-important severe accident sequence for a PWR is used to examine the capability of the existing measurements to supply the necessary information. The method includes an assessment of the effects of the sequence on the measurement availability including the effects of environmental conditions. The information needs and capabilities identified using this approach are also intended to form the basis for more comprehensive information needs assessment performed during the analyses and development of specific strategies for use in accident management prevention and mitigation. 3 refs., 16 figs., 7 tabs.

Core-melting accidents in Chernobyl and Harrisburg

International Nuclear Information System (INIS)

Loon, A.J. van; Vonderen, A.C.M. van

1987-01-01

This publication deals with the essences of the reactor accident in Chernobylsk and the conclusions to be drawn from these with regard to reactor safety. Therein the technical differences between the reactor types in the West and the East play an important role. Also attention is spent to the now generally accepted philosophy that by simplification and making use of proven technologies, a further deminishing of the risks can be achieved step by step. In ch.'s 2 and 4 the origin and course of the accidents in respectively Chernobylsk and Harrisburg are analyzed; in the analysis of the Chernobylsk accident also date have been used which were provided by the Sovjet-Union, supplied with results of studies of the U.S. Department of Energy (DOE). In ch. 3 this information is compared with the insights which have grown at KEMA about these on the base of reactor physical and thermohydraulic considerations and of computer calculations reproducing the course of the accident. An important question is if, and if so: to which extent, an accident such as the one in Chernobylsk also can take place in the West. In order to answer that question as accurate as possible the consequences of core meltings accidents and the risk for such an accident taking place are pursued. In ch. 6 the legal frameworks are indicated by which the risk may be limited and by which eventually yet occurring damage may be arranged. Ch. 7 finally deals with the lessons which the accidents in Chernobylsk and Harrisburg have learnt us and with the possible consequences of these for the further application of nuclear power in the Netherlands. (H.W.). 105 refs.; 42 figs.; 17 refs

Effective Factors in Severity of Traffic Accident-Related Traumas; an Epidemiologic Study Based on the Haddon Matrix.

Science.gov (United States)

Masoumi, Kambiz; Forouzan, Arash; Barzegari, Hassan; Asgari Darian, Ali; Rahim, Fakher; Zohrevandi, Behzad; Nabi, Somayeh

2016-01-01

Traffic accidents are the 8(th) cause of mortality in different countries and are expected to rise to the 3(rd) rank by 2020. Based on the Haddon matrix numerous factors such as environment, host, and agent can affect the severity of traffic-related traumas. Therefore, the present study aimed to evaluate the effective factors in severity of these traumas based on Haddon matrix. In the present 1-month cross-sectional study, all the patients injured in traffic accidents, who were referred to the ED of Imam Khomeini and Golestan Hospitals, Ahvaz, Iran, during March 2013 were evaluated. Based on the Haddon matrix, effective factors in accident occurrence were defined in 3 groups of host, agent, and environment. Demographic data of the patients and data regarding Haddon risk factors were extracted and analyzed using SPSS version 20. 700 injured people with the mean age of 29.66 ± 12.64 years (3-82) were evaluated (92.4% male). Trauma mechanism was car-pedestrian in 308 (44%) of the cases and car-motorcycle in 175 (25%). 610 (87.1%) cases were traffic accidents and 371 (53%) occurred in the time between 2 pm and 8 pm. Violation of speed limit was the most common violation with 570 (81.4%) cases, followed by violation of right-of-way in 57 (8.1%) patients. 59.9% of the severe and critical injuries had occurred on road accidents, while 61.3% of the injuries caused by traffic accidents were mild to moderate (p accidents (p severity of traffic accident-related traumas were age over 50, not using safety tools, and undertaking among host-related factors; insufficient environment safety, road accidents and time between 2 pm and 8 pm among environmental factors; and finally, rollover, car-pedestrian, and motorcycle-pedestrian accidents among the agent factors.

Identification of NPP accidents using support vector classification

Energy Technology Data Exchange (ETDEWEB)

Back, Ju Hyun; Yoo, Kwae Hwan; Na, Man Gyun [Chosun University, Gwangju (Korea, Republic of)

2016-10-15

In case of the accidents that happens in a nuclear power plants (NPPs), it is very important to identify its accidents for the operator. Therefore, in order to effectively manage the accidents, the initial short time trends of major parameters have to be observed and NPP accidents have to accurately be identified to provide its information to operators and technicians. In this regard, the objective of this study is to identify the accidents when the accidents happen in NPPs. In this study, we applied the support vector classification (SVC) model to classify the initiating events of critical accidents such as loss of coolant accidents (LOCA), total loss of feedwater (TLOFW), station blackout (SBO), and steam generator tube rupture (SGTR). Input variables were used as the initial integral value of the signal measured in the reactor coolant system (RCS), steam generator, and containment vessel after reactor trip. The proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. In this study, the proposed SVC model is verified by using the simulation data of the modular accident analysis program (MAAP4) code. We used an initial integral value of the simulated sensor signals to identify the NPP accidents. The training data was used to train the SVC model. And, the trained model was confirmed using the test data. As a result, it was known that it can accurately classify five events.

49 CFR 225.11 - Reporting of accidents/incidents.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Reporting of accidents/incidents. 225.11 Section... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD ACCIDENTS/INCIDENTS: REPORTS CLASSIFICATION, AND INVESTIGATIONS § 225.11 Reporting of accidents/incidents. Each railroad subject to this part shall submit to FRA...

Proceedings of the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 3-5 March 2015, OECD-NEA HQ

International Nuclear Information System (INIS)

Bischoff, Jeremy; Gandrille, Pascal; Forgeron, Thierry; Brachet, Jean-Christophe; Lorrette, Christophe; Valot, C.; Freyss, M.; Braun, J.; Sauder, C.; Moatti, Marie; Waeckel, Nicolas; Ambard, Antoine; Pasamehmetoglu, Kemal; Johnston, Emma; Bragg-Sitton, Shannon M.; Kurata, M.; Hallstadius, Lars; Ohta, H.; Ogata, T.; Besmann, T.; Chauvin, Nathalie; Cornet, Stephanie; Massara, S.; Kohyama, Akira; Kishimoto, Hirotatsu; Park, Joon Soo; Nakazato, Naofumi; Hayasaka, Daisuke; Asakura, Yuuki; Kanda, Chisato; Kohyama, Akira; Terrani, Kurt; Katoh, Yutai; Yamamoto, Yukinori; Field, Kevin; Snead, Lance; Hu, Xunxiang; Dryepondt, Sebastien; Unocic, Kinga A.; Hoelzer, David T.; Pint, Bruce A.; Besmann, T.; Steinbrueck, M.; Grosse, M.; Jianu, A.; Weisenburger, A.; Avincola, V.; Ahmad, S.; Tang, C.; Heuser, Brent J.; Sickafus, Kurt; Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il; Park, Dong-Jun; Park, Jung-Hwan; Park, Jeong-Yong; Koo, Yang-Hyun; Lee, B.O.; Van Nieuwenhove, Rudi; Kim, Young; Rebak, Raul; Dolly, Evan; Dolley, E.J.; Rebak, R.B.; Maloy, Stu; Yang, Jae-Ho; Kim, Dong-Joo; Kim, Keon-Sik; Koo, Yang-Hyun; Lee, Won Jae; Tulenko, James S.; Puide, Mattias; Liu, T.; Gueneau, C.; Gosse, S.; Dupin, N.; Barber, D.; Corcoran, E.; Dumas, J.C.; Hania, R.; Kaye, M.; Turchi, P.

2015-03-01

Under the guidance of the OECD-NEA Nuclear Science Committee, the expert group acts as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance. The expert group focusses on the fundamental properties and behaviour under normal operations and accident conditions for advanced core materials and components (fuels, cladding, control rods, etc.). The materials considered are applicable to Gen II and Gen III Light Water Reactors, as well as Gen III+ reactors under construction. The objective of the expert group is to define and coordinate a programme of work to help advance the scientific knowledge needed to provide the technical underpinning for the development of advanced LWR fuels with enhanced accident tolerance compared to currently used zircaloy/UO 2 fuel systems, as well as other non-fuel core components with important roles in LWR performance under accident conditions. This document brings together the available presentations (slides) given at the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs. Content: 1 - Task Force 1 (Systems assessment) meeting, 3-4 March 2015: - French evaluation of ATF Concepts (J. Bischoff, AREVA); - Technology Readiness Levels - TRL - for Fuels (K. Pasamehmetoglu, INL); - TRL-definition for advanced fuel concept applied for commercial LWRs in Japan (M. Kurata, JAEA); - Application of TRLs in NNL (E. Johnston, NNL); - Technology Readiness Levels for Advanced Nuclear Fuel and Materials (S. Bragg-Sitton, INL); 1a - Definition of the illustrative scenarios: - AREVA's proposal concerning scenario for Accident Tolerant Fuel studies (P. Gandrille); - A Simplified Accident Scenario (L. Hallstadius); - Accident Scenarios for ATF Performance Evaluation of BWR and PWR in Japan (H. Ohta, CRIEPI); 1b - Related NEA activities: - Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems - WPMM, Expert

Accident management

International Nuclear Information System (INIS)

Lutz, R.J.; Monty, B.S.; Liparulo, N.J.; Desaedeleer, G.

1989-01-01

The foundation of the framework for a Severe Accident Management Program is the contained in the Probabilistic Safety Study (PSS) or the Individual Plant Evaluations (IPE) for a specific plant. The development of a Severe Accident Management Program at a plant is based on the use of the information, in conjunction with other applicable information. A Severe Accident Management Program must address both accident prevention and accident mitigation. The overall Severe Accident Management framework must address these two facets, as a living program in terms of gathering the evaluating information, the readiness to respond to an event. Significant international experience in the development of severe accident management programs exist which should provide some direction for the development of Severe Accident Management in the U.S. This paper reports that the two most important elements of a Severe Accident Management Program are the Emergency Consultation process and the standards for measuring the effectiveness of individual Severe Accident Management Programs at utilities

Assessing information needs and instrument availability for a pressurized water reactor during severe accidents

Energy Technology Data Exchange (ETDEWEB)

Hanson, Duane J. (Idaho National Engineering Laboratory, Idaho Falls, ID 83415 (United States)); Arcieri, William C. (Idaho National Engineering Laboratory, Idaho Falls, ID 83415 (United States)); Ward, Leonard W. (Idaho National Engineering Laboratory, Idaho Falls, ID 83415 (United States))

1994-07-01

A five-step methodology was 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 that 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 severe accident conditions, to evaluate the availability of the instrumentation to supply needed plant information. This methodology was applied to a pressurized water reactor with a large dry containment and the results are presented. A companion article describes application of the methodology to a boiling water reactor with a Mark I containment. ((orig.))

Assessing information needs and instrument availability for a pressurized water reactor during severe accidents

International Nuclear Information System (INIS)

Hanson, Duane J.; Arcieri, William C.; Ward, Leonard W.

1994-01-01

A five-step methodology was 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 that 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 severe accident conditions, to evaluate the availability of the instrumentation to supply needed plant information. This methodology was applied to a pressurized water reactor with a large dry containment and the results are presented. A companion article describes application of the methodology to a boiling water reactor with a Mark I containment. ((orig.))

Dose assessment around TR-2 reactor due to maximum credible accident

International Nuclear Information System (INIS)

Turgut, M. H.; Adalioglu, U.; Aytekin, A.

2001-01-01

The revision of safety analysis report of TR-2 research reactor had been initiated in 1995. The whole accident analysis and accepted scenario for maximum credible accident has been revised according to the new safety concepts and the impact to be given to the environment due to this scenario has been assessed. This paper comprises all results of these calculations. The accepted maximum credible accident scenario is the partial blockage of the whole reactor core which resulted in the release of 25% of the core inventory. The DOSER code which uses very conservative modelling of atmospheric distributions were modified for the assessment calculations. Pasquill conditions based on the local weather observations, topography, and building affects were considered. The thyroid and whole body doses for 16 sectors and up to 10 km of distance around CNAEM were obtained. Release models were puff and a prolonged one of two hours of duration. Release fractions for the active isotopes were chosen from literature which were realistic

Associations between psychological distress, workplace accidents, workplace failures and workplace successes.

Science.gov (United States)

Hilton, Michael F; Whiteford, Harvey A

2010-12-01

This study investigates associations between psychological distress and workplace accidents, workplace failures and workplace successes. The Health and Work Performance Questionnaire (HPQ) was distributed to employees of 58 large employers. A total of 60,556 full-time employees were eligible for analysis. The HPQ probed whether the respondent had, in the past 30-days, a workplace accident, success or failure ("yes" or "no"). Psychological distress was quantified using the Kessler 6 (K6) scale and categorised into low, moderate and high psychological distress. Three binomial logistic regressions were performed with the dependent variables being workplace accident, success or failure. Covariates in the models were K6 category, gender, age, marital status, education level, job category, physical health and employment sector. Accounting for all other variables, moderate and high psychological distress significantly (P work failures and decrease the OR of workplace successes at similar levels. As the prevalence of moderate psychological distress is approximately double that of high psychological distress moderate distress consequentially has a greater workplace impact.

The Chernobyl accident: Causes and consequences

International Nuclear Information System (INIS)

Malinauskas, A.P.

1987-01-01

Two explosions, one immediately following the other, in Unit 4 of the Chernobyl nuclear power station in the Soviet Union signaled the worst disaster ever to befall the commercial nuclear power production industry. This accident, which occurred at 1:24 a.m. on April 26, 1986, resulted from an almost incredible series of operational errors associated, ironically, with an attempt to enhance the capability of the reactor to safely accommodate station blackout accidents (i.e., accidents arising from a loss of station electrical power). Disruption of the core, due to a prompt criticality excursion, resulted in the destruction of the core vault and reactor building and the sudden dispersal of about 3% of the fuel from the core region into the environment. Lesser but significant releases of radioactivity continued through May 6, 1986, before attempts to certain the radioactivity and cool the remnants of the core were successful. The amount and composition of material released in the course of the accident remain somewhat uncertain, and inconsistencies in the release estimates are evident. The Soviet estimates, in addition to the dispersal of about 3% of the fuel, include complete release of the noble gas core inventory, 20% of the fission product iodine inventory, 15% of the tellurium inventory, and 10 to 13% of the fission product cesium inventory. The iodine and cesium release estimates are not consistent with the noble gas values, and are as much as a factor of two less than some estimates made by experts outside the Soviet Union

The technical requirements concerning severe accident management in nuclear power plants

International Nuclear Information System (INIS)

Okamoto, Koji; Sugiyama, Tomoyuki; Kamata, Shinya

2014-01-01

The Great East Japan Earthquake with a magnitude of 9.0 (The 2011 off the Pacific coast of Tohoku Earthquake) occurred on March 11, 2011, and the beyond design-basis tsunami descended on the Fukushima Daiichi Nuclear Power Plant by the earthquake. Eventually, the core cooling systems of the units 1, 2 and 3 could not operate stably, they all suffered severe accident, and hydrogen explosions were triggered in the reactor buildings of units 1, 3 and 4. In the light of these circumstances, Atomic Energy Society of Japan (AESJ) decided to establish a standard that consolidates the concept of maintaining and improving severe accident management. In the SAM standard, the combination of hardware and software measures based on the risk assessment enables a scientific and rational approach to apply to scenarios of various severe accidents including low-frequency, high-impact events, and assures safety with functionality and flexibility. The SAM standard is already established in March, 2014. After publication of the SAM standard, with regard to effectiveness assessment for accident management and treatment of the uncertainty of severe accident analysis code, for example, the detailed guideline will be prepared as appendices of the standard. (author)

Comparisons of the emissions in the Windscale and Chernobyl accidents

International Nuclear Information System (INIS)

Chamberlain, A.C.

1987-02-01

The contents are summarized under the following headings: 1) Windscale accident summary 2) Emission of 137 Cs from Windscale 3) Emission of other fission products from Windscale 4) Environmental effects - iodine 5) Environmental effects - caesium. A bibliography is attached and where figures are available, comparisons are made with the Chernobyl fallout, including thyroid iodine burdens for U.K. students who were in Russia at the time of the Chernobyl accident, and milk measurements of Caesium 137 in the U.K. (UK)

[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.

Defining a List of Accidents to be Considered as a First Step of Forging Effective Level 4 of Defense-in Depth

Energy Technology Data Exchange (ETDEWEB)

Lankin, M., E-mail: lankin@secnrs.ru [Scientific and Engineering Center for Nuclear and Radiation Safety, Moscow (Russian Federation)

2014-10-15

Russian national regulatory documents require consideration of beyond design basis accidents (BDBAs) while organizing defence-in-depth for nuclear power plants. Consideration of BDBAs in plant design analysis forms the basis for development accident prevention and mitigation strategies. Since sheer quantity of possible beyond design basis accidents is limitless, we face a necessity of working out selection criteria for choosing scenarios of such accidents to be taken into consideration while assessing adequacy of Level 4 of Defence-in-Depth for NPPs. This paper presents possible algorithm for defining a list of beyond design basis accidents that are to be taken into account for NPPs. Developing such a list is to include examination of the following criteria: a) Representativity of set of scenarios covered by the list (representativity to be assessed from the point of view of organizing emergency response actions); b) Cumulative occurrence probability of the scenarios not covered by the list (this probability should be low); and c) Necessity to cover scenarios recommended by current international state-of the art practices. (author)

Hypothetical accidents at disposal facilities for high-level liquid radioactive wastes and pulps

International Nuclear Information System (INIS)

Kabakchi, S.A.; Zagainov, V.A.; Lishnikov, A.A.; Nazin, E.R.

1994-01-01

Four accidents are postulated and analyzed for interim storage of high-level, liquid radioactive wastes at a fuel reprocessing facility. Normal waste storage operation is based on wastes stored in steel drums, partially buried in concrete canyons, and equipped with heat exchangers for cooling and ventilation systems for removal of explosive gases and vapors. The accident scenarios analyzed are: (1) shutdown of ventilation with open entrance and exit ventilation pipes, (2) shutdown of ventilation with closed entrance and exit ventilation pipes, (3) shutdown of the cooling system with normally functioning ventilation, and (4) simultaneous cooling and ventilation system failure (worst case). A mathematical model was developed and used to calculate radiation consequences of various accidents. Results are briefly presented for the worst case scenario and compared to an actual accident for model validation. 17 refs., 3 figs., 1 tab

[Description of communications of work accidents registered in the National Institute of Social Security of Santa Maria, RS, in the year 2000].

Science.gov (United States)

Kirchhof, Ana Lúcia Cardoso; Capellari, Claudia

2004-08-01

The communication of work accident is the document which warrants to the worker who suffered an accident the right to social benefit, and also serves as a source of epidemiological data. This study described the work accidents notified to the National Institute of Social Security of Santa Maria, RS, Brazil, in the year of 2000, attributing to them classifications that could be compared to Brazilian data and similar studies, among those the kind of accident, production sector and the worker's days off. It was possible to evidence the significant increase of notifications registered during the year of 2000 in relation to 1999, beyond the sub-register, specially in the scope of less serious accidents.

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)

Trend and Seasonal Patterns of Injuries and Mortality Due to Motorcyclists Traffic Accidents; A Hospital-Based Study.

Science.gov (United States)

Hosseinpour, Marjan; Mohammadian-Hafshejani, Abdollah; Esmaeilpour Aghdam, Mohammad; Mohammadian, Mahdi; Maleki, Farzad

2017-01-01

To investigate trend and seasonal pattern of occurrence and mortality of motorcycle accidents in patients referred to hospitals of Isfahan. This cross-sectional study was carried out using traffic accidents data of Isfahan province, extracted from Ministry of Health (MOH) database from 2006 to 2010. During the study period, 83648 people injured due to motorcycle traffic accidents were referred to hospitals, all of them entered in the study. Logistic regression model was used to calculate the hospital mortality odds ratio, and Cochrane-Armitage test was used for assessment of linear trend. During the study period, the hospital admission for motorcycle accident was 83,648 and 89.3% (74743) of them were men. Mean age in accidents time was 26.41±14.3 years. The injuries and death sex ratio were 8.4 and 16.9, respectively. Lowest admission rate was during autumn and highest during summer. The injury mortality odds ratio was 1.01 (CI 95% 0.73-1.39) in the Spring, 1.34 (CI95% 1.01-1.79) in summer and 1.17 (CI95% 0.83-1.63). It was also calculated to be 2.51 (CI95% 1.36-4.64) in age group 40-49, 2.39 (CI95% 1.51-5.68) in 50-59 and 4.79 (CI95% 2.49-9.22) in 60-69 years. The mortality odds ratio was 3.53 (CI95% 2.77-4.5) in rural place, 1.33 (CI95% 1.15-1.54) in men, and 2.44 (CI95% 2.09-2.85) in the road out of town and village. In addition, trend of motorcycle accidents mortality was increasing ( p accidents injuries are more common in men, summer, young age and rural roads. These high risk groups need more attention, care and higher training.

Role of the private sector in vaccination service delivery in India: evidence from private-sector vaccine sales data, 2009-12.

Science.gov (United States)

Sharma, Abhishek; Kaplan, Warren A; Chokshi, Maulik; Zodpey, Sanjay P

2016-09-01

India's Universal Immunization Programme (UIP) provides basic vaccines free-of-cost in the public sector, yet national vaccination coverage is poor. The Government of India has urged an expanded role for the private sector to help achieve universal immunization coverage. We conducted a state-by-state analysis of the role of the private sector in vaccinating Indian children against each of the six primary childhood diseases covered under India's UIP. We analyzed IMS Health data on Indian private-sector vaccine sales, 2011 Indian Census data and national household surveys (DHS/NFHS 2005-06 and UNICEF CES 2009) to estimate the percentage of vaccinated children among the 2009-12 birth cohort who received a given vaccine in the private sector in 16 Indian states. We also analyzed the estimated private-sector vaccine shares as function of state-specific socio-economic status. Overall in 16 states, the private sector contributed 4.7% towards tuberculosis (Bacillus Calmette-Guérin (BCG)), 3.5% towards measles, 2.3% towards diphtheria-pertussis-tetanus (DPT3) and 7.6% towards polio (OPV3) overall (both public and private sectors) vaccination coverage. Certain low income states (Uttar Pradesh, Rajasthan, Madhya Pradesh, Orissa, Assam and Bihar) have low private as well as public sector vaccination coverage. The private sector's role has been limited primarily to the high income states as opposed to these low income states where the majority of Indian children live. Urban areas with good access to the private sector and the ability to pay increases the Indian population's willingness to access private-sector vaccination services. In India, the public sector offers vaccination services to the majority of the population but the private sector should not be neglected as it could potentially improve overall vaccination coverage. The government could train and incentivize a wider range of private-sector health professionals to help deliver the vaccines, especially in the low

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)

Method for consequence calculations for severe accidents

International Nuclear Information System (INIS)

Nielsen, F.

1988-07-01

This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Forsmark reactor No 3. The accident sequence chosen for the calculating was a release caused by total power failure. The calculations were made by means of the PLUCON4 code. Meteorological data for two years from the Forsmark meteorological tower were analysed to find representative weather situations. As typical weather, Pasquill D was chosen with a wind speed of 5 m/s, and as extreme weather, Pasquill F with a wind speed of 2 m/s. 23 tabs., 37 ills., 20 refs. (author)

INTRODUCTION OF A SECTORAL APPROACH TO TRANSPORT SECTOR FOR POST-2012 CLIMATE REGIME

Directory of Open Access Journals (Sweden)

Atit TIPPICHAI

2009-01-01

% reduction, the total abatement is equal to 1,026.4 MtCO2 with a total cost of 116.17 billion USD. The emission reductions according to the total targets of the five developed regions could cover around 3% to 15% of global CO2 emissions in the transport sector in 2020.

Interaction of radionuclides in severe accident conditions

International Nuclear Information System (INIS)

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

2015-01-01

Nuclear power plants are designed with inherent engineering safety systems and associated operational procedures that provide an in-depth defence against accidents. Radionuclides such as Iodine, Cesium, Tellurium, Barium, Strontium, Rubidium, Molybdenum and many others may get released during a severe accident. Among these, Iodine, one of the fission products, behaviour is significant for the analysis of severe accident consequences because iodine is a chemically more active to the potential components released to the environment. During severe accident, Iodine is released and transported in aqueous, organic and inorganic forms. Iodine release from fuel, iodine transport in primary coolant system, containment, and reaction with control rods are some of the important phases in a severe accident scenario. The behaviour of iodine is governed by aerosol physics, depletion mechanisms gravitational settling, diffusiophoresis and thermophoresis. The presence of gaseous organic compounds and oxidizing compounds on iodine, reactions of aerosol iodine with boron and formation of cesium iodide which results in more volatile iodine release in containment play significant roles. Water radiolysis products due to presence of dissolved impurities, chloride ions, organic impurities should be considered while calculating iodine release. Containment filtered venting system (CFVS) consists of venturi scrubber and a scrubber tank which is dosed with NaOH and NaS_2O_3 in water where iodine will react with the chemicals and convert into NaI and Na_2SO_4. This paper elaborates the issues with respect to interaction of radionuclides and its consideration in modeling of severe accident. (author)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-02-15

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

[An analysis of 148 outpatient treated occupational accidents].

Science.gov (United States)

Nicaeus, T; Erb, C; Rohrbach, M; Thiel, H J

1996-10-01

The most common eye injuries are non-perforating. Eye injuries in the workplace are a major cause of socioeconomical damage, morbidity and disability, despite well publicised standards for industrial eye protection. This study investigates the epidemiological and clinical aspects of 148 occupational cases. At the University Eye Clinic of Tübingen, 709 non-perforating eye injuries were registered as occupational accidents between 1995 and 1996. Of these cases, 148 were analysed retrospectively per random. The 5 most common injuries of 148 patients (m/f = 138/10; mean age 33.4 +/- 12 years) were related to corneal foreign body injuries (35%), chemical burns (15.5%), sub-conjunctival foreign bodies (12%), thermal/ultraviolet injuries (11%) and contusions (7.4%). Of these patients, 22.3% were employed as construction workers and 16.2% as metal workers. At the time of examination the visual acuity of the traumatic eye was 0.9 +/- 0.3. The interval between the beginning of work and accident was 6.2 +/- 6.4 hours in average (0.5-13.5 h). Of all accidents, 8.5% were caused during the first hour of work; in contrast 45.5% of all accidents were caused after 6 hours of work. Another 12.4 +/- 14.5 hours (5min.-72 h; median 7 h) passed by until the patients arrived for eye examination at the Eye Clinic of Tübingen. Only 6% of all patients arrived within the first hour, and 29.7% after 12 hours. Of all cases, 30.4% received first-aid treatment in their company by the factory doctor or by the eye doctor before examination at the Eye Clinic. Only 6.8% of all patients had protective spectacles during work. Incapacity was seen in 30.4%; the average in total was 5.5 +/- 10 days. Despite the late examination at the Eye Clinic the functional loss was mostly little except after chemical burns. Nevertheless, most occupational accidents can be avoided with better protective devices in order to reduce the incidence of injuries and socioeconomical damage. Therefore an intense campaign

Serious work accidents and their causes - An analysis of data from Eurostat

DEFF Research Database (Denmark)

Jørgensen, Kirsten

2015-01-01

In the two years 2009-2010 EU countries reported a total of 4.5 million occupational accidents with more than three days absence from work to Eurostat, the Statistical Office of the European Communities (Eurostat 2013,1). The European database offers comparable statistics on accidents at work...... by economic activity and severity for the EU27 countries from this period and Norway. (Eurostat request DK533) The individual countries estimated their underreporting to be between 33% and 40% which means that, if this underreporting is accounted for, around 3.5 million of work accidents are taking place...

Croatian Energy Sector Reform - Results Achieved

International Nuclear Information System (INIS)

Nota, R.

2001-01-01

During the past ten years, the energy sector has passed through significant changes including fundamental market, economic, legislative and institutional aspects of sector operation. As the main goal of the Republic of Croatia is the integration into the European Union, the energy sector reform ought to be conducted in keeping with the present market development processes of the EU in such a way as to fulfil all safety criteria. In view of the above mentioned, the Croatian Parliament brought a number of laws during its session in July 2001 (''Official Gazette'' 68/01): 1. Energy Law 2. Energy Activities Regulation Law 3. Electricity Market Law 4. Gas Market Law 5. Oil and Oil Derivatives Market Law, which present the commencement of the energy sector reform (www.mingo.hr).(author)

The corporate quest for zero accidents: A case study into the response to safety transgressions in the industrial sector

NARCIS (Netherlands)

Twaalfhoven, S.F.M.; Kortleven, W.J.

2016-01-01

Since the 1990s, the idea that accidents should be reduced to zero is gaining growing acclaim in the fields of road safety and occupational safety and health. As most of the literature on this so-called Zero Accident Vision (ZAV) deals exclusively with its application to road safety, which is a

Substance use among Iranian drivers involved in fatal road accidents

Directory of Open Access Journals (Sweden)

Shervin eAssari

2014-08-01

Full Text Available Background: Although the problem of substance use among drivers is not limited to a special part of the world, most published epidemiological reports on this topic is from industrial world.Aim: To determine drug use among Iranian adults who were imprisoned for vehicle accidents with fatality. Methods: This study enrolled 51 Iranian adults who were imprisoned for vehicle accidents with fatality. This sample came from a national survey of prisoners. Data was collected at entry to prisons during the last 4 months of 2008 in 7 prisons in different parts of the country. Self reported drug use was registered. Commercial substance use screening tests were also done. Results: Drug test was positive for opioids, cannabis and both in 37.3%, 2.0% and 13.7%, respectively. 29.4% tested positive for benzodiazepines. Using test introduced 23.5% of our sample as drug users, who had declined to report any drug use. Conclusion: Opioids are the most used illicit drug in the case of vehicle accidents with fatality, however, 20% of users do not declare their use. This high rate of drug use in vehicle accidents with fatality reflects the importance of drug use control as a part of injury prevention in Iran. There might be a need for drug screening after severe car accidents.

Interplanetary sector boundaries 1971--1973

International Nuclear Information System (INIS)

Klein, L.; Burlaga, L.F.

1980-01-01

Eighteen interplanetary sector boundary crossings observed at 1 AU during the period January 1971 to January 1974 by the magnetometer on the Imp 6 spacecraft was discussed. The events were examined on many different time scales ranging from days on either side of the boundary to high-resolution measurements of 12.5 vectors per second. Two categories of boundaries were found, one group being relatively thin (averaging approx. =10 4 km) and the other being thick (averaging approx. =10 6 km). In many cases the field vector rotated in a plane from polarity to the other. Only two of the transitions were null sheets. Using the minimum variance analysis to determine the normals to the plane of rotationa and assuming that this is the same as the normal to the sector boundary surface, it was found that the normals were close to ( 0 ) the ecliptic plane. The high inclination of the sector boundary surfaces during 1971--1973 verifies a published prediction and may be related to the presence of large equatorial coronal holes at this time. An analysis of tangential discontinuities contained in 4-day periods about our events showed that their orientations were generally not related to the orientations of the sector boundary surface, but rather their characteristics were about the same as those for discontinuities outside the sector boundaries. Magnetic holes were found in thick sector boundaries, at a rate about 3 times that elsewhere. The holes were especially prevalent near stream interfaces, suggesting that they might be related to the convergence and/or slip of adjacent solar wind streams

Parametric and experimentally informed BWR Severe Accident Analysis Utilizing FeCrAl - M3FT-17OR020205041

Energy Technology Data Exchange (ETDEWEB)