Fire safety of wood construction

Science.gov (United States)

Robert H. White; Mark A. Dietenberger

2010-01-01

Fire safety is an important concern in all types of construction. The high level of national concern for fire safety is reflected in limitations and design requirements in building codes. These code requirements and related fire performance data are discussed in the context of fire safety design and evaluation in the initial section of this chapter. Because basic data...

Fire safety regulations and licensing

International Nuclear Information System (INIS)

Berg, H.P.

1998-01-01

Experience of the past tow decades of nuclear power plant operation and results obtained from modern analytical techniques confirm that fires may be a real threat to nuclear safety and should receive adequate attention from the design phase throughout the life of the plant. Fire events, in particular influence significantly plant safety due to the fact that fires have the potential to simultaneously damage components of redundant safety-related equipment. Hence, the importance of fire protection for the overall safety of a nuclear power plant has to be reflected by the fire safety regulations and to be checked during the licensing process of a plant as well as during the continuous supervision of the operating plant

Spacecraft Fire Safety Demonstration

Data.gov (United States)

National Aeronautics and Space Administration — The objective of the Spacecraft Fire Safety Demonstration project is to develop and conduct large-scale fire safety experiments on an International Space Station...

Use of operational experience in fire safety assessment of nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

Fire hazard has been identified as a major contributor to a plant's operational risk and the international nuclear power industry has been studying and developing tools for defending against this hazard. Considerable progress in design and regulatory requirements for fire safety, in fire protection technology and in related analytical techniques has been made in the past two decades. Substantial efforts have been undertaken worldwide to implement these advances in the interest of improving fire safety both at new and existing nuclear power plants. To assist in these efforts, the IAEA initiated a programme on fire safety that was intended to provide assistance to Member States in improving fire safety in nuclear power plants. In order to achieve this general objective, the IAEA programme aimed at the development of guidelines and good practices, the promotion of advanced fire safety assessment techniques, the exchange of state of the art information between practitioners and the provision of engineering safety advisory services and training in the implementation of internationally accepted practices. During the period 1993-1994, the IAEA activities related to fire safety concentrated on the development of guidelines and good practice documents related to fire safety and fire protection of operating plants. One of the first tasks was the development of a Safety Guide that formulates specific requirements with regard to the fire safety of operating nuclear power plants. Several documents, which provide advice on fire safety inspection, were developed to assist in its implementation. In the period 1995-1996, the programme focused on the preparation of guidelines for the systematic analysis of fire safety at nuclear power plants (NPPs). The IAEA programme on fire safety for 1997-1998 includes tasks aimed at promoting systematic assessment of fire safety related occurrences and dissemination of essential insights from this assessment. One of the topics addressed is the

Fires and Food Safety

Science.gov (United States)

... Forms FSIS United States Department of Agriculture Food Safety and Inspection Service About FSIS District Offices Careers ... JSR 286) Actions ${title} Loading... Fires and Food Safety Fire! Few words can strike such terror. Residential ...

Smoking and Home Fire Safety

Science.gov (United States)

... Materials Working with the Media Fire Protection Technology Smoking fire safety outreach materials As a member of ... Not reported 7% In transport 1% 195 incidents Smoking fire safety messages to share It is important ...

How to increase fire safety in buildings: Fire safety engineering

NARCIS (Netherlands)

Herpen, van R.A.P. (Ruud)

2011-01-01

Fire means beside direct (financial)damage often far more indirect costs caused by interruption of operations and loss in sales, market share, property and,in the worst case people can get injured or even get killed (on average around80 persons a year). Fire in buildings is clearly a disaster and

29 CFR 1915.502 - Fire safety plan.

Science.gov (United States)

2010-07-01

... implement a written fire safety plan that covers all the actions that employers and employees must take to ensure employee safety in the event of a fire. (See Appendix A to this subpart for a Model Fire Safety... safety plan for their employees, and this plan must comply with the host employer's fire safety plan. ...

The necessity of periodic fire safety review

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

Effective fire safety requires the coordinated integration of many diverse elements. Clear fire safety objectives are defined by plant management and/or regulatory authorities. Extensive and time-consuming systematic analyses are performed. Fire safety features (both active and passive) are installed and maintained, and administrative programs are established and implemented to achieve the defined objectives. Personnel are rigorously trained. Given the time, effort and monetary resources expended to achieve a specific level of fire safety, conducting periodic assessments to verify that the specified level of fire safety has been achieved and is maintained is a matter of common sense. Periodic fire safety reviews and assessment play an essential role in assuring continual nuclear safety in the world's power plants

34 CFR 668.49 - Institutional fire safety policies and fire statistics.

Science.gov (United States)

2010-07-01

... 34 Education 3 2010-07-01 2010-07-01 false Institutional fire safety policies and fire statistics... fire statistics. (a) Additional definitions that apply to this section. Cause of fire: The factor or...; however, it does not include indirect loss, such as business interruption. (b) Annual fire safety report...

Work Health & Safety legislation; the fire engineer’s neglected duty?

OpenAIRE

P.A. (Tony) Enright

2014-01-01

Fire engineers are in general, aware of their duties under Building legislation. However, they are often unfamiliar of separate duties under Work Health and Safety legislation. This paper describes an Australian case-study, but one that is presented generally so as to have applicability in those other jurisdictions where similar Work Health and Safety obligations exist. As society becomes safer, Work Health and Safety has evolved from being solely about the employer–employee relationshi...

Fire safety assessment of tunnel structures

DEFF Research Database (Denmark)

Gkoumas, Konstantinos; Giuliani, Luisa; Petrini, Francesco

2011-01-01

.g. structural and non structural, organizational, human behavior). This is even more truth for the fire safety design of such structures. Fire safety in tunnels is challenging because of the particular environment, bearing in mind also that a fire can occur in different phases of the tunnel’s lifecycle. Plans...... for upgrading fire safety provisions and tunnel management are also important for existing tunnels. In this study, following a brief introduction of issues regarding the above mentioned aspects, the structural performance of a steel rib for a tunnel infrastructure subject to fire is assessed by means...

49 CFR 238.103 - Fire safety.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Fire safety. 238.103 Section 238.103..., DEPARTMENT OF TRANSPORTATION PASSENGER EQUIPMENT SAFETY STANDARDS Safety Planning and General Requirements § 238.103 Fire safety. (a) Materials. (1) Materials used in constructing a passenger car or a cab of a...

Key Problems of Fire Safety Enforcement in Traffic and Communication Centers (TCC)

Science.gov (United States)

Medyanik, M.; Zosimova, O.

2017-10-01

A Traffic and Communication Center (TCC) means facilities designed and used to distribute and redirect flows of humans and motor vehicles while they get serviced and operate. This paper sets forth the basic problems of fire safety enforcement on the TCC, and the causes that slow down human and vehicle traffic speeds. It proposes ways to solve the problems of fire safety enforcement on the TCC, in the Russian Federation and elsewhere. Engineering solutions are proposed for TCC design, with key outlooks of TCC future development as an alternative way to organize access in transportation.

Fire safety requirements for electrical cables towards nuclear reactor safety

International Nuclear Information System (INIS)

Raju, M.R.

2002-01-01

Full text: Electrical power supply forms a very important part of any nuclear reactor. Power supplies have been categorized in to class I, II, III and IV from reliability point. The safety related equipment are provided with highly reliable power supply to achieve the safety of very high order. Vast network of cables in a nuclear reactor are grouped and segregated to ensure availability of power to at least one group under all anticipated occurrences. Since fire can result in failures leading to unavailability of power caused by common cause, both passive and active fire protection methods are adopted in addition to fire detection system. The paper describes the requirement for passive fire protection to electrical cables viz. fire barrier and fire breaks. The paper gives an account of the tests required to standardize the products. Fire safety implementation for cables in research reactors is described

Nuclear power plants: a unique challenge to fire safety

International Nuclear Information System (INIS)

Nowlen, S.P.

1992-01-01

The evaluation of fire safety in a nuclear power plant must include the consideration of the impact of a fire on the operability of plant safety equipment and systems. This issue is not typical of the life safety and property protection issues which dominate traditional fire safety concerns. This paper provides a general discussion of the issue of nuclear power plant fire safety as it currently exists in the USA. Included is a discussion of the past history of nuclear power plant fire events, the development of nuclear industry specific fire safety guidelines, the adverse experience associated with the inadvertent operation of fire suppression systems, and the anticipated direction of fire safety requirements for future reactor designs in the USA. (Author)

Investigation of Fire Safety Awareness and Management in Mall

Directory of Open Access Journals (Sweden)

Abdul Rahim N.

2014-03-01

Full Text Available In spite of having sufficient fire safety system installed in buildings, the incidence of fire hazard becomes the furthermost and supreme threat to health and safety, as well as property to any community. In order to make sure that the safety of the building and its users, the fundamental features depends on the fire precaution system and equipment which should be according to the standard requirements. Nevertheless, the awareness on fire safety could necessarily alleviate the damages or rate of fatality during the event of fire. This paper presents the results on the investigation of fire safety awareness and management, concentrating on shopping mall. The endeavour of this study is to explore the level of fire safety knowledge of the users in the mall, and to study the effectiveness level of fire safety management in a mall. From the study, public awareness is highly related to understanding human behaviour and their personal background. The respondents’ levels of awareness are rather low, which reflects on their poor action when facing emergency situation during fire. The most effective methods identified to improve the awareness and effectiveness of fire safety level is through involvement in related fire safety programmes, distribution of pamphlets or brochures on fire safety and appointing specific personnel for Emergency Response Team in the mall.

Safety design guides for fire protection for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide establishes design requirements to ensure the radiological risk to the public due to fire is acceptable and operating personnel are adequately protected from the hazards of fires. This safety design guide also specifies the safety criteria for fire protection to be applied to mitigate fires and recommends the fire protection program to be established to initiate, coordinate and document the design activities associated with fire protection. The requirements for fire protection outlined in this safety design guide shall be satisfied in the design stage and the change status of the regulatory requirements, code and standards should be traced and incorporated into this safety design guide accordingly. 1 fig., (Author) .new

Large-Scale Spacecraft Fire Safety Tests

Science.gov (United States)

Urban, David; Ruff, Gary A.; Ferkul, Paul V.; Olson, Sandra; Fernandez-Pello, A. Carlos; T'ien, James S.; Torero, Jose L.; Cowlard, Adam J.; Rouvreau, Sebastien; Minster, Olivier;

Fire Safety Design of Wood Structures

DEFF Research Database (Denmark)

Hertz, Kristian Dahl

2006-01-01

Lecture Notes on Fire Safety Design of Wood Structures including charring of wood and load bearing capacity of beams, columns, and connections.......Lecture Notes on Fire Safety Design of Wood Structures including charring of wood and load bearing capacity of beams, columns, and connections....

Large Scale Experiments on Spacecraft Fire Safety

Science.gov (United States)

Urban, David; Ruff, Gary A.; Minster, Olivier; Fernandez-Pello, A. Carlos; Tien, James S.; Torero, Jose L.; Legros, Guillaume; Eigenbrod, Christian; Smirnov, Nickolay; Fujita, Osamu;

Frequently Asked Questions in Fire Probabilistic Safety Assessment

International Nuclear Information System (INIS)

Kang, Dae Il; Kim, Kil Yoo; Park, Gee Yong

2010-05-01

The FAQs(Frequently Asked Questions) in the Fire Probabilistic Safety Assessment(FPSA) are the issues occurred during performing the engineering evaluation based on NFPA-805. In this report, the background and resolutions are reviewed and described for 17 FAQs related to FPSA among 57 FAQs. The current FAQs related to FPSA are the issues concerning to NUREG/CR-6850, and are almost resolved but for the some FAQ, the current resolutions would be changed depending on the results of the future or on-going research. Among FAQs related to FPSA, best estimate approaches are suggested concerning to the conservative method of NUREG/CR-6850. If these best estimate solutions are used in the FPSA of nuclear power plants, realistic evaluation results of fire risk would be obtained

Fire Safety Deficiencies

Data.gov (United States)

U.S. Department of Health & Human Services — A list of all fire safety deficiencies currently listed on Nursing Home Compare, including the nursing home that received the deficiency, the associated inspection...

40 CFR 30.18 - Hotel and motel fire safety.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Hotel and motel fire safety. 30.18... EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Pre-Award Requirements § 30.18 Hotel and motel fire safety. The Hotel and Motel Fire Safety Act of 1990 (Public Law 101-391) establishes a number of fire...

The influence of sodium fires on LMFBRs safety analysis

Energy Technology Data Exchange (ETDEWEB)

Justin, F [DSN/Centre de Fontenay-aux-Roses, Fontenay-aux-Roses (France)

1979-03-01

In a sodium cooled reactor, sodium fires are accidental conditions to be taken into account in safety analysis. For the various sodium categories, fire conditions, associated risks, safety analysis objectives and detailed corresponding issues are indicated, An experimental research program can be deduced from these considerations. This report covers the following: safety analysis methodology; primary sodium fires; secondary sodium fires; auxiliary sodium fires, and related experimental research programs.

The influence of sodium fires on LMFBRs safety analysis

International Nuclear Information System (INIS)

Justin, F.

1979-01-01

In a sodium cooled reactor, sodium fires are accidental conditions to be taken into account in safety analysis. For the various sodium categories, fire conditions, associated risks, safety analysis objectives and detailed corresponding issues are indicated, An experimental research program can be deduced from these considerations. This report covers the following: safety analysis methodology; primary sodium fires; secondary sodium fires; auxiliary sodium fires, and related experimental research programs

The fire brigade renovates

CERN Multimedia

2002-01-01

The new fire engine at CERN's Fire Station. A shiny brand-new fire engine is now attracting all the attention of the members of CERN's fire brigade. Since the beginning of last week this engine has taken over from an 18-year-old one, which has now been 'retired' from service. This modern vehicle, built in Brescia, Italy, is much lighter and more powerful than the old one and is equipped to allow the fire service to tackle most call-outs without the support of at least one other vehicle, as is currently necessary. The new fire engine is designed to transport six fire-fighters, 2000 litres of water, and is equipped not only for fire fighting actions but also to respond initially to any other kind of call-out, such as traffic accidents, chemical incidents, pollution, lightning, etc. It goes almost without saying that it is provided with the most modern safety measures, a low centre of gravity, as well as a special chassis and a combination pump (low and high pressure), which improve the safety and performance ...

SYSTEMS SAFETY ANALYSIS FOR FIRE EVENTS ASSOCIATED WITH THE ECRB CROSS DRIFT

International Nuclear Information System (INIS)

R. J. Garrett

2001-01-01

The purpose of this analysis is to systematically identify and evaluate fire hazards related to the Yucca Mountain Site Characterization Project (YMP) Enhanced Characterization of the Repository Block (ECRB) East-West Cross Drift (commonly referred to as the ECRB Cross-Drift). This analysis builds upon prior Exploratory Studies Facility (ESF) System Safety Analyses and incorporates Topopah Springs (TS) Main Drift fire scenarios and ECRB Cross-Drift fire scenarios. Accident scenarios involving the fires in the Main Drift and the ECRB Cross-Drift were previously evaluated in ''Topopah Springs Main Drift System Safety Analysis'' (CRWMS M and O 1995) and the ''Yucca Mountain Site Characterization Project East-West Drift System Safety Analysis'' (CRWMS M and O 1998). In addition to listing required mitigation/control features, this analysis identifies the potential need for procedures and training as part of defense-in-depth mitigation/control features. The inclusion of this information in the System Safety Analysis (SSA) is intended to assist the organization(s) (e.g., Construction, Environmental Safety and Health, Design) responsible for these aspects of the ECRB Cross-Drift in developing mitigation/control features for fire events, including Emergency Refuge Station(s). This SSA was prepared, in part, in response to Condition/Issue Identification and Reporting/Resolution System (CIRS) item 1966. The SSA is an integral part of the systems engineering process, whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach is used which incorporates operating experiences and recommendations from vendors, the constructor and the operating contractor. The risk assessment in this analysis characterizes the scenarios associated with fires in terms of relative risk and includes recommendations for mitigating all identified hazards. The priority for recommending and implementing mitigation control features is: (1) Incorporate

Appraisal of Fire Safety Management Systems at Educational Buildings

Directory of Open Access Journals (Sweden)

Nadzim N.

2014-01-01

Full Text Available Educational buildings are one type of government asset that should be protected, and they play an important role as temporary communal meeting places for children, teachers and communities. In terms of management, schools need to emphasize fire safety for their buildings. It is well known that fires are not only a threat to the building’s occupants, but also to the property and the school environment. A study on fire safety management has been carried out on schools that have recently experienced fires in Penang. From the study, it was found that the school buildings require further enhancement in terms of both active and passive fire protection systems. For instance, adequate fire extinguishers should be provided to the school and the management should inspect and maintain fire protection devices regularly. The most effective methods to increase the level of awareness on fire safety are by organizing related programs on the management of fire safety involving all staff, teachers and students, educational talks on the dangers of fire and important actions to take in the event of an emergency, and, lastly, to appoint particular staff to join the management safety team in schools.

Safety tests carried out at Cadarache. Sodium fires

International Nuclear Information System (INIS)

Fruchard, M.

1976-01-01

Safety test on sodium fires developed at the Cadarache Nuclear Centre by the Department of Nuclear Safety, section of safety experiments on radioactivity transfer are conducted in two main directions: analysis of the behavior and thermodynamic consequences of accidental fires, working on the basis of typical experimental results; research and development of methods and equipment to control and if possible extinguish these fires. The most important part of this programme is concerned with the sodium pool fires which would result from the failure of a secondary coolant circuit pipe [fr

Fire safety study of Dodewaard and Borssele nuclear power plants

International Nuclear Information System (INIS)

1988-03-01

From the nuclear and conventional fire safety audits of both Dutch nuclear power plants performed under supervision of the Nuclear Safety Inspectorate and the Inspectorate for the Fire Services it turns out that the fire safety is sufficient however amenable for improvement. Besides a detailed description of the method of examination, the study 'Fire Safety' contains the results of the audit and 14 respectively 15 recommendations for improvement of the fire safety in Dodewaard and Borssele. The suggested recommendations which are applicable to both power plants are the following: fire fighting training for operators and guards, a complete emergency ventilation system of the control room, increase in the number of detectors and alarms, an increase in the quantity of water available for high-pressure fire fighting, improvement of fire barriers between several redundancies of nuclear safety systems, an investigation and possible improvement of the heat and radiation protection offered by presently used fire fighting suits. For Dodewaard a closed emergency staircase in the reactor building (secondary containment) is deemed necessary for personnel emergency escape routes and continued fire fighting if required

German data for risk based fire safety assessment

International Nuclear Information System (INIS)

Roewekamp, M.; Berg, H.P.

1998-01-01

Different types of data are necessary to perform risk based fire safety assessments and, in particular, to quantify the fire event tree considering the plant specific conditions. Data on fire barriers, fire detection and extinguishing, including also data on secondary effects of a fire, have to be used for quantifying the potential hazard and damage states. The existing German database on fires in nuclear power plants (NPPs) is very small. Therefore, in general generic data, mainly from US databases, are used for risk based safety assessments. Due to several differences in the plant design and conditions generic data can only be used as conservative assumptions. World-wide existing generic data on personnel failures in case of fire fighting have only to be adapted to the plant specific conditions inside the NPP to be investigated. In contrary, unavailabilities of fire barrier elements may differ strongly depending on different standards, testing requirements, etc. In addition, the operational behaviour of active fire protection equipment may vary depending on type and manufacturer. The necessity for more detailed and for additional plant specific data was the main reason for generating updated German data on the operational behaviour of active fire protection equipment/features in NPPs to support risk based fire safety analyses being recommended to be carried out as an additional tool to deterministic fire hazard analyses in the frame of safety reviews. The results of these investigations revealed a broader and more realistic database for technical reliability of active fire protection means, but improvements as well as collection of further data are still necessary. (author)

Impact of fires on nuclear safety

International Nuclear Information System (INIS)

Skvarka, P.; Zmajkovic, I.

1990-01-01

Factors which are relevant with respect to fire hazard are summarized based on Revision 1 of IAEA Safety Guide No. 50-SG-D2, ''Fire Protection in Nuclear Power Plants'', of 1990. They include data acquisition, quantification of fire risks, assessment of adequacy of fire protection measures, modification of the fire protection system proposed. According to the above document, fire hazard analysis should define and document those parts of the fire protection system that must be present in order to secure safe operation of the nuclear power plant. (Z.M.). 2 appendices, 4 refs

Examination of alternatives to upgrade fire safety in operating NPPs

International Nuclear Information System (INIS)

Park, J. H.; Jung, I. S.

2003-01-01

For the Kori unit 2,3,4, Younggwang 1,2 and Ulchin 1,2 fire protection vulnerabilities and further improvement items are investigated. The most major problem is that those plants do not have plant-specific Fire Hazard Analysis Report. To improve fire safety of those plants, their own Fire Hazard Analysis should be proceed at first. Then, according to results of Fire Hazard Analysis, fire protection improvement program should be implemented. For the assurance of long term fire safety, result of Fire Hazard Analysis should be incorporated in the FSAR and periodically reviewed the impact of design change to fire safety

Presentation of a Software Method for Use of Risk Assessment in Building Fire Safety Measure Optimization

Directory of Open Access Journals (Sweden)

A. R. Koohpaei

2012-05-01

Full Text Available Background and aims: The property loss and physical injuries due to fire events in buildings demonstrate the necessity of implementation of efficient and performance based fire safety measures. Effective and high efficiency protection is possible when design and selection of protection measures are based on risk assessment. This study aims at presenting a software method to make possible selection and design of building fire safety measures based upon quantitative risk assessment and building characteristics. Methods: based on “Fire Risk Assessment Method for Engineer (FRAME” a program in MATLB software was written. The first section of this program, according to the FRAME method and based on the specification of a building, calculates the potential risk and acceptable risk level. In the second section, according to potential risk, acceptable risk level and the fire risk level that user want, program calculate concession of protective factor for that building.Results: The prepared software make it possible to assign the fire safety measure based on quantitative risk level and all building specifications. All calculations were performed with 0.001 of precision and the accuracy of this software was assessed with handmade calculations. During the use of the software if an error occurs in calculations, it can be distinguished in the output. Conclusion: Application of quantitative risk assessment is a suitable tool for increasing of efficiency in designing and execution of fire protection measure in building. With using this software the selected fire safety measure would be more efficient and suitable since the selection of fire safety measures performed on risk assessment and particular specification of a building. Moreover fire risk in the building can be managed easily and carefully.

Organization and conduct of IAEA fire safety reviews at nuclear power plants

International Nuclear Information System (INIS)

1998-01-01

The importance of fire safety in the safe and productive operation of nuclear power plants is recognized worldwide. Lessons learned from experience in nuclear power plants indicate that fire poses a real threat to nuclear safety and that its significance extends far beyond the scope of a conventional fire hazard. With a growing understanding of the close correlation between the fire hazard in nuclear power plants and nuclear safety, backfitting for fire safety has become necessary for a number of operating plants. However, it has been recognized that the expertise necessary for a systematic independent assessment of fire safety of a NPP may not always be available to a number of Member States. In order to assist in enhancing fire safety, the IAEA has already started to offer various services to Member States in the area of fire safety. At the request of a Member State, the IAEA may provide a team of experts to conduct fire safety reviews of varying scope to evaluate the adequacy of fire safety at a specific nuclear power plant during various phases such as construction, operation and decommissioning. The IAEA nuclear safety publications related to fire protection and fire safety form a common basis for these reviews. This report provides guidance for the experts involved in the organization and conduct of fire safety review services to ensure consistency and comprehensiveness of the reviews

Fire protection and fire fighting in nuclear installations

International Nuclear Information System (INIS)

1989-01-01

Fires are a threat to all technical installations. While fire protection has long been a well established conventional discipline, its application to nuclear facilities requires special considerations. Nevertheless, for a long time fire engineering has been somewhat neglected in the design and operation of nuclear installations. In the nuclear industry, the Browns Ferry fire in 1975 brought about an essential change in the attention paid to fire problems. Designers and plant operators, as well as insurance companies and regulators, increased their efforts to develop concepts and methods for reducing fire risks, not only to protect the capital investment in nuclear plants but also to consider the potential secondary effects which could lead to nuclear accidents. Although the number of fires in nuclear installations is still relatively large, their overall importance to the safety of nuclear power plants was not considered to be very high. Only more recently have probabilistic analyses changed this picture. The results may well have to be taken into account more carefully. Various aspects of fire fighting and fire protection were discussed during the Symposium, the first of its kind to be organized by the IAEA. It was convened in co-operation with several organizations working in the nuclear or fire protection fields. The intention was to gather experts from nuclear engineering areas and the conventional fire protection field at one meeting with a view to enhancing the exchange of information and experience and to presenting current knowledge on the various disciplines involved. The presentations at the meeting were subdivided into eight sessions: standards and licensing (6 papers); national fire safety practices (7 papers); fire safety by design (11 papers); fire fighting (2 papers); computer fire modeling (7 papers); fire safety in fuel center facilities (7 papers); fire testing of materials (3 papers); fire risk assessment (5 papers). A separate abstract was

Fire and blast safety manual for fuel element manufacture

International Nuclear Information System (INIS)

Ensinger, U.; Koehler, B.; Mester, W.; Riotte, H.G.; Sehrbrock, H.W.

1988-01-01

The manual aims to enable people involved in the planning, operation, supervision, licensing or appraisal of fuel element factories to make a quick and accurate assessment of blast safety. In Part A, technical plant principles are shown, and a summary lists the flammable materials and ignition sources to be found in fuel element factories, together with theoretical details of what happens during a fire or a blast. Part B comprises a list of possible fires and explosions in fuel element factories and ways of preventing them. Typical fire and explosion scenarios are analysed more closely on the basis of experiments. Part B also contains a list and an assessment of actual fires and explosions which have occurred in fuel element factories. Part C contains safety measures to protect against fire and explosion, in-built fire safety, fire safety in plant design, explosion protection and measures to protect people from radiation and other hazards when fighting fires. A distinction is drawn between UO 2 , MOX and HTR fuel elements. (orig./DG) [de

Safety guide on fire protection in nuclear power plants

International Nuclear Information System (INIS)

1976-01-01

The purpose of the Safety Guide is to give specific design and operational guidance for protection from fire and explosion in nuclear power plants, based on the general guidance given in the relevant sections of the 'Safety Code of Practice - Design' and the 'Safety Code of Practice - Operation' of the International Atomic Energy Agency. The guide will confine itself to fire protection of safety systems and items important to safety, leaving the non-safety matters of fire protection in nuclear power plants to be decided upon the basis of the various available national and international practices and regulations. (HP) [de

National and international standards and recommendations on fire protection and fire safety assessment

International Nuclear Information System (INIS)

Berg, H.P.

2007-01-01

Experience feedback from events in nuclear facilities worldwide has shown that fire can represent a safety significant hazard. Thus, the primary objectives of fire protection programmes are to minimize both the probability of occurrence and the consequences of a fire. The regulator body expects that the licensees justify their arrangements for identifying how fires can occur and spread, assess the vulnerability of plant equipment and structures, determine how the safe operation of a plant is affected, and introduce measures to prevent a fire hazard from developing and propagating as well as to mitigate its effects in case the fire cannot be prevented. For that purpose usually a comprehensive regulatory framework for fire protection has been elaborated, based on national industrial regulations, nuclear specific regulations as well as international recommendations or requirements. Examples of such national and international standards and recommendations on fire protection and fire safety assessment as well as ongoing activities in this field are described. (orig.)

Experimental Technique of Titanium Fire in Aero-engine

Directory of Open Access Journals (Sweden)

MI Guangbao

2016-06-01

Full Text Available Titanium fire is the typical catastrophic fault in the aero-engine. Aiming at the urgent demand for experimental technique of titanium fire from advanced high thrust-weight ratio aero-engine, the combustion technology and theory of titanium alloy based on friction oxygen concentration method (FOC were systematically studied. The evaluation method of fireproof property and the friction ignition model were built, and the fireproof mechanism was illustrated. By generalizing recent progress in experimental technique of titanium fire from three levels, including evolutionary rule, mechanism and prevention and control technology, the ideas and directions of experimental technique associated with the application research of titanium fire in the future were proposed, namely overall evaluation of fireproof property close to air flow environment of the aero-engine, prediction model of fireproof property and experimental verification of fireproof technique under the air flow environment of aero-engine. It is necessary to establish the prevention system of titanium fire in aero-engine, which contributes to the realization of "full titanium" in compressor and to the increase of high thrust-weight ratio.

Fire Safety. Managing School Facilities, Guide 6.

Science.gov (United States)

Department for Education and Employment, London (England). Architects and Building Branch.

This booklet discusses how United Kingdom schools can manage fire safety and minimize the risk of fire. The guide examines what legislation school buildings must comply with and covers the major risks. It also describes training and evacuation procedures and provides guidance on fire precautions, alarm systems, fire fighting equipment, and escape…

Human Factors in Fire Safety Management and Prevention

Directory of Open Access Journals (Sweden)

M.A. Othuman Mydin

2014-07-01

Full Text Available Fire protection is the study and practice of mitigating the unwanted effects of potentially destructive fires. It involves the study of the behavior, compartmentalization, and investigation of fire and its related emergencies, as well as the research and development, production, testing and application of mitigating systems. Problems still occurred despite of the adequate fire safety systems installed. For most people in high-risk buildings, not all accidents were caused by them. They were more likely to be the victims of a fire that occurred. Besides damaging their properties and belongings, some people were burned to death for not knowing what to do if fire happens in their place. This paper will present the human factors in fire safety management and prevention system.

Fire Safety Trianing in Health Care Institutions.

Science.gov (United States)

American Hospital Association, Chicago, IL.

The manual details the procedures to be followed in developing and implementing a fire safety plan. The three main steps are first, to organize; second, to set up a procedure and put it in writing; and third, to train and drill employees and staff. Step 1 involves organizing a safety committee, appointing a fire marshall, and seeking help from…

Fire science at LLNL: A review

Energy Technology Data Exchange (ETDEWEB)

Hasegawa, H.K. (ed.)

1990-03-01

This fire sciences report from LLNL includes topics on: fire spread in trailer complexes, properties of welding blankets, validation of sprinkler systems, fire and smoke detectors, fire modeling, and other fire engineering and safety issues. (JEF)

The Safety Analysis of Shipborne Ammunition in Fire Environment

Science.gov (United States)

Ren, Junpeng; Wang, Xudong; Yue, Pengfei

2017-12-01

The safety of Ammunition has always been the focus of national military science and technology issues. And fire is one of the major safety threats to the ship’s ammunition storage environment, In this paper, Mk-82 shipborne aviation bomb has been taken as the study object, simulated the whole process of fire by using the FDS (Fire Detection System) software. According to the simulation results of FDS, ANSYS software was used to simulate the temperature field of Mk-82 carrier-based aviation bomb under fire environment, and the safety of aviation bomb in fire environment was analyzed. The result shows that the aviation bombs under the fire environment can occur the combustion or explosion after 70s constant cook-off, and it was a huge threat to the ship security.

Education of mining engineers with the specialization in Rescue, fire and safety technique at the BERG Faculty of the Technical University of Košice

Directory of Open Access Journals (Sweden)

Sedlatý Václav

2002-12-01

Full Text Available After the separation of Czechoslovakia, in 1993, the Mining Faculty (now BERG Faculty of the Technical University of Košice started a teaching program with the specialization in mining rescue, fire guard and safety technique at the Detachment in Prievidza, because of all the needs and conditions related to the education of engineers in the mentioned areas. During the last 10 years, the Detachment in Prievidza has been growing in terms of number of students. From the beginning of this period to present days 75 students graduated. The full-time studies last five years and the academic years are divided into two semesters of 15 weeks each. The semesters are finished by examination sessions. The first 2 years, in principle, include basic studies in mathematics, scientific subjects and some subjects related to earth sciences. The third and fourth year are generally devoted to basic technical subjects of mining and underground works, and then to rescue, fire and safety subjects. A practical work experience has to be gained by students in a mine or fire and safety stations. The practical training term is scheduled after the third academic year. During the last two semesters the students are preparing their Master’s degree thesis using a stay in the mine company or other firms to receive the necessary information and data.

Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium

International Nuclear Information System (INIS)

1998-04-01

The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper

Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper Refs, figs, tabs

Development of Large-Scale Spacecraft Fire Safety Experiments

DEFF Research Database (Denmark)

Ruff, Gary A.; Urban, David L.; Fernandez-Pello, A. Carlos

2013-01-01

exploration missions outside of low-earth orbit and accordingly, more complex in terms of operations, logistics, and safety. This will increase the challenge of ensuring a fire-safe environment for the crew throughout the mission. Based on our fundamental uncertainty of the behavior of fires in low...... of the spacecraft fire safety risk. The activity of this project is supported by an international topical team of fire experts from other space agencies who conduct research that is integrated into the overall experiment design. The large-scale space flight experiment will be conducted in an Orbital Sciences...

A probabilistic method for optimization of fire safety in nuclear power plants

International Nuclear Information System (INIS)

Hosser, D.; Sprey, W.

1986-01-01

As part of a comprehensive fire safety study for German Nuclear Power Plants a probabilistic method for the analysis and optimization of fire safety has been developed. It follows the general line of the American fire hazard analysis, with more or less important modifications in detail. At first, fire event trees in selected critical plant areas are established taking into account active and passive fire protection measures and safety systems endangered by the fire. Failure models for fire protection measures and safety systems are formulated depending on common parameters like time after ignition and fire effects. These dependences are properly taken into account in the analysis of the fire event trees with the help of first-order system reliability theory. In addition to frequencies of fire-induced safety system failures relative weights of event paths, fire protection measures within these paths and parameters of the failure models are calculated as functions of time. Based on these information optimization of fire safety is achieved by modifying primarily event paths, fire protection measures and parameters with the greatest relative weights. This procedure is illustrated using as an example a German 1300 MW PWR reference plant. It is shown that the recommended modifications also reduce the risk to plant personnel and fire damage

Behavior based safety approach towards fire

International Nuclear Information System (INIS)

Suresh Kumar, R.

2009-01-01

The behavior of the individual who notice fire first is very important because it affect the safety of all occupants of the area. Human behavior on fire depends on variables of the buildings in which fire occurs and by the appearance of the fire when it is detected. Altruistic behavior of human being will help to handle the critical conditions due to fire emergencies. NPCIL have developed a culture of systematic approach to safeguard men and materials from fire by training and awareness. In our Nuclear Power Plants, we have an effective plan and system to test the plans. In each emergency exercises, the behavior of individuals will be monitored and recorded

Evaluation of the Ventilation and Air Cleaning System Design Concepts for Safety Requirements during Fire Conditions in Nuclear Applications

International Nuclear Information System (INIS)

Rashad, S.; El-Fawal, M.; Kandil, M.

2013-01-01

The ventilation and air cleaning system in the nuclear or radiological installations is one of the essential nuclear safety concerns. It is responsible for confining the radioactive materials involved behind suitable barriers during normal and abnormal conditions. It must be designed to prevent the release of harmful products (radioactive gases, or airborne radioactive materials) from the system or facility, impacting the public or workers, and doing environmental damage. There are two important safety functions common to all ventilation and air cleaning system in nuclear facilities. They are: a) the requirements to maintain the pressure of the ventilated volume below that of surrounding, relatively non-active areas, in order to inhibit the spread of contamination during normal and abnormal conditions, and b) the need to treat the ventilated gas so as to minimize the release of any radioactive or toxic materials. Keeping the two important safety functions is achieved by applying the fire protection for the ventilation system to achieve safety and adequate protection in nuclear applications facilities during fire and accidental criticality conditions.The main purpose of this research is to assist ventilation engineers and experts in nuclear installations for safe operation and maintaining ventilation and air cleaning system during fire accident in nuclear facilities. The research focuses on fire prevention and protection of the ventilation systems in nuclear facilities. High-Efficiency particulate air (HEPA) filters are extremely susceptible to damage when exposed to the effects of fire, smoke, and water; it is the intent of this research to provide the designer with the experience gained over the years from hard lessons learned in protecting HEPA filters from fire. It describes briefly and evaluates the design safety features, constituents and working conditions of ventilation and air cleaning system in nuclear and radioactive industry.This paper provides and

Building safety and human behaviour in fire: A literature review

NARCIS (Netherlands)

Kobes, M.; Helsloot, I.; de Vries, B.; Post, J.

2010-01-01

The most crucial aspect of a building's safety in the face of fire is the possibility of safe escape. An important precondition is that its fire safety facilities enable independent and adequate fire response performances by the building's occupants. In practice, it appears that the measures

IRSN global process for leading a comprehensive fire safety analysis for nuclear installations

International Nuclear Information System (INIS)

Ormieres, Yannick; Lacoue, Jocelyne

2013-01-01

A fire safety analysis (FSA) is requested to justify the adequacy of fire protection measures set by the operator. A recent document written by IRSN outlines a global process for such a comprehensive fire safety analysis. Thanks to the French nuclear fire safety regulation evolutions, from prescriptive requirements to objective requirements, the proposed fire safety justification process focuses on compliance with performance criteria for fire protection measures. These performance criteria are related to the vulnerability of targets to effects of fire, and not only based upon radiological consequences out side the installation caused by a fire. In his FSA, the operator has to define the safety functions that should continue to ensure its mission even in the case of fire in order to be in compliance with nuclear safety objectives. Then, in order to maintain these safety functions, the operator has to justify the adequacy of fire protection measures, defined according to defence in depth principles. To reach the objective, the analysis process is based on the identification of targets to be protected in order to maintain safety functions, taken into account facility characteristics. These targets include structures, systems, components and personal important to safety. Facility characteristics include, for all operating conditions, potential ignition sources and fire protections systems. One of the key points of the fire analysis is the assessment of possible fire scenarios in the facility. Given the large number of possible fire scenarios, it is then necessary to evaluate 'reference fires' which are the worst case scenarios of all possible fire scenarios and which are used by the operator for the design of fire protection measures. (authors)

Reliability and safety engineering

CERN Document Server

Verma, Ajit Kumar; Karanki, Durga Rao

2016-01-01

Reliability and safety are core issues that must be addressed throughout the life cycle of engineering systems. Reliability and Safety Engineering presents an overview of the basic concepts, together with simple and practical illustrations. The authors present reliability terminology in various engineering fields, viz.,electronics engineering, software engineering, mechanical engineering, structural engineering and power systems engineering. The book describes the latest applications in the area of probabilistic safety assessment, such as technical specification optimization, risk monitoring and risk informed in-service inspection. Reliability and safety studies must, inevitably, deal with uncertainty, so the book includes uncertainty propagation methods: Monte Carlo simulation, fuzzy arithmetic, Dempster-Shafer theory and probability bounds. Reliability and Safety Engineering also highlights advances in system reliability and safety assessment including dynamic system modeling and uncertainty management. Cas...

Evaluation of fire safety measures at local universities in Kenya with ...

African Journals Online (AJOL)

This study establishes fire safety measures in place in local universities in Kenya, and ... fire suppression systems, fire detection and alarm systems and fire Hydrants. ... response backed by university management endorsement and support. The Directorate of occupational safety and health services should also make the ...

Evaluation of an accident management strategy of emergency water injection using fire engines in a typical pressurized water reactor

Directory of Open Access Journals (Sweden)

Soo-Yong Park

2015-10-01

Full Text Available Following the Fukushima accident, a special safety inspection was conducted in Korea. The inspection results show that Korean nuclear power plants have no imminent risk for expected maximum potential earthquake or coastal flooding. However long- and short-term safety improvements do need to be implemented. One of the measures to increase the mitigation capability during a prolonged station blackout (SBO accident is installing injection flow paths to provide emergency cooling water of external sources using fire engines to the steam generators or reactor cooling systems. This paper illustrates an evaluation of the effectiveness of external cooling water injection strategies using fire trucks during a potential extended SBO accident in a 1,000 MWe pressurized water reactor. With regard to the effectiveness of external cooling water injection strategies using fire engines, the strategies are judged to be very feasible for a long-term SBO, but are not likely to be effective for a short-term SBO.

Evaluation of an accident management strategy of emergency water injection using fire engines in a typical pressurized water reactor

International Nuclear Information System (INIS)

Park, Soo Yong; Ahn, Kwang Il

2015-01-01

Following the Fukushima accident, a special safety inspection was conducted in Korea. The inspection results show that Korean nuclear power plants have no imminent risk for expected maximum potential earthquake or coastal flooding. However long- and short-term safety improvements do need to be implemented. One of the measures to increase the mitigation capability during a prolonged station blackout (SBO) accident is installing injection flow paths to provide emergency cooling water of external sources using fire engines to the steam generators or reactor cooling systems. This paper illustrates an evaluation of the effectiveness of external cooling water injection strategies using fire trucks during a potential extended SBO accident in a 1,000 MWe pressurized water reactor. With regard to the effectiveness of external cooling water injection strategies using fire engines, the strategies are judged to be very feasible for a long-term SBO, but are not likely to be effective for a short-term SBO

Evaluation of an accident management strategy of emergency water injection using fire engines in a typical pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Park, Soo Yong; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Following the Fukushima accident, a special safety inspection was conducted in Korea. The inspection results show that Korean nuclear power plants have no imminent risk for expected maximum potential earthquake or coastal flooding. However long- and short-term safety improvements do need to be implemented. One of the measures to increase the mitigation capability during a prolonged station blackout (SBO) accident is installing injection flow paths to provide emergency cooling water of external sources using fire engines to the steam generators or reactor cooling systems. This paper illustrates an evaluation of the effectiveness of external cooling water injection strategies using fire trucks during a potential extended SBO accident in a 1,000 MWe pressurized water reactor. With regard to the effectiveness of external cooling water injection strategies using fire engines, the strategies are judged to be very feasible for a long-term SBO, but are not likely to be effective for a short-term SBO.

The Italian National Guidelines for the fire safety of facades

Directory of Open Access Journals (Sweden)

Lamberto Mazziotti

2013-11-01

Full Text Available Traditionally, the facades' design buildings where once only focused on architectural or aesthetic purposes (in addition, of course, of whether protective issues. Nowadays, thanks to the technological development of the construction works and the use of new types of materials, the facades' design should also address fire safety related aspects. In Europe and especially in Italy – where the types of building façades are built with windows of small surface and natural stone coverings – the green building/sustainability movement has resulted in the development of new concepts in facade or curtain wall design that intended to enhance the energy efficiency of building façades. These new building surfaces are covered by extensive panelling fitted with insulating materials or by wide glass surfaces, capable of carry out the most diverse purposes including, just to name a few: energy reduction, climate comfort, recovery of electricity through photovoltaic panels that convert sunlight into electricity, large space for advertising purpose. One of the main fire safety goal for a building design is to restrict the vertical fire spread so that the smoke and flames are limited to the fire origin floor. The new building façade and curtain wall topologies could overwhelms concerns for fire safety, therefore the Italian National fire service has released a Fire Code Guideline in order to address the fire safety design for an high rise building façade. This paper aims to show the guideline contents and the related fire safety façades concerns.

Sodium fires and its extinguishment

International Nuclear Information System (INIS)

Mikhedov, V.G.

1979-01-01

The fire safety problems of NPP with sodium coolants in USSR are presented. The design of sodium reactors is made with premises with sodium coolants being hermetic and filled with nitrogen. Some engineering solutions of fire safety including design, elaboration and choice of construction and protection materials are presented. Some theoretical aspects of sodium burning are presented as well as methods of sodium fire extinguishing methods including the use of powder

Fire protection and safety in working with sodium. Pt. 2

International Nuclear Information System (INIS)

Foerster, K.; Kremer, K.H.; Wolf, J.

1978-01-01

The use of sodium as a heat transfer medium in nuclear plant and the associated development of sodium technology caused the requirement for adapting fire and safety precautions to new conditions of dealing with this liquid. The comparison in the first part of this article of the properties of sodium with those of petrol clarified the different fire characteristics of sodium compared to many other combustible materials and the effects of fires which differ from conventional fires. Based on this, measures for fire precautions and for safety of personnel are introduced. (orig.) [de

Fire safety in dental clinics: Basics for dentists and dental students

Directory of Open Access Journals (Sweden)

Kalyana Chakravarthy Pentapati

2015-01-01

Full Text Available Fire safety is essential component and requirement in health care sector. It includes components like emergency exits, manual call outs, different types of fire extinguishers, safe assembly area, fire hydrant system with water sprinkler systems etc. We attempt to provide some basics about fire and fire safety that are prerequisite for safe working environment in dental clinics along with some recommendations that can be incorporated in the curriculum.

Industrial safety and fire protection during the construction phase

International Nuclear Information System (INIS)

Zimmer, K.

1977-01-01

The questions and problems of industrial safety and fire prevention have to be treated like the activities planning, developing, assembly, etc. This statement is illustrated by statistics of the fire insurance companies, from which it can be seen that the number of fire accidents has decreased but that the damage caused has greatly increased. The sooner the fire prevention and industrial safety measures are integrated in the planning phase, the better for the total costs. Preventive measures that possibly have to be introduced at a later stage are not only generally much more expensive but are also seldom as effective. (orig./HK) [de

Evaluation Of Fire Safety And Protection At PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Ahmad Nabil Ab Rahim; Alfred Sanggau Ligam; Nurhayati Ramli; Mohd Fazli Zakaria; Naim Syauqi Hamzah; Phongsakorn Prak; Mohammad Suhaimi Kassim; Zarina Masood

2014-01-01

Fire hazard is one of many risks that can affect the safety operation of PUSPATI TRIGA Reactor. Reactor building in Malaysian Nuclear Agency was built in 1980s and the fire system has been introduced since then. The evaluation of the fire safety system at this time is important to ensure the efficiency of fire prevention, fighting and mitigation task that probably occurs. This evaluation involves with the fire fighting system and equipment, integrity of the system from the perspective of management and equipment, fire fighting procedure and fire fighting response team. (author)

Getting fire risk assessment right.

Science.gov (United States)

Charters, David

2012-06-01

The NHS has one of the world's largest and most varied estates, which at any time accommodates many of the most dependent people in society. With around 6,000 fires occurring in NHS premises each year, its duty of care--and that of other healthcare providers--demands very close attention to fire safety. Here Dr David Charters BSc, PhD, CEng, FIFireE, MIMechE, MSFPE, director of Fire Engineering at BRE Global, an independent third party approvals body offering certification of fire, security, and sustainability products and services, examines the critical role of fire risk assessment, and explains why the process should provide the 'foundation' for effective fire safety measures.

41 CFR 102-80.135 - Who is a qualified fire protection engineer?

Science.gov (United States)

2010-07-01

... protection engineer? 102-80.135 Section 102-80.135 Public Contracts and Property Management Federal Property... qualified fire protection engineer? A qualified fire protection engineer is defined as an individual with a thorough knowledge and understanding of the principles of physics and chemistry governing fire growth...

48 CFR 245.7311-2 - Safety, security, and fire regulations.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Safety, security, and fire regulations. 245.7311-2 Section 245.7311-2 Federal Acquisition Regulations System DEFENSE ACQUISITION... Inventory 245.7311-2 Safety, security, and fire regulations. ...

Large-Scale Spacecraft Fire Safety Experiments in ISS Resupply Vehicles

Science.gov (United States)

Ruff, Gary A.; Urban, David

2013-01-01

Our understanding of the fire safety risk in manned spacecraft has been limited by the small scale of the testing we have been able to conduct in low-gravity. Fire growth and spread cannot be expected to scale linearly with sample size so we cannot make accurate predictions of the behavior of realistic scale fires in spacecraft based on the limited low-g testing to date. As a result, spacecraft fire safety protocols are necessarily very conservative and costly. Future crewed missions are expected to be longer in duration than previous exploration missions outside of low-earth orbit and accordingly, more complex in terms of operations, logistics, and safety. This will increase the challenge of ensuring a fire-safe environment for the crew throughout the mission. Based on our fundamental uncertainty of the behavior of fires in low-gravity, the need for realistic scale testing at reduced gravity has been demonstrated. To address this concern, a spacecraft fire safety research project is underway to reduce the uncertainty and risk in the design of spacecraft fire safety systems by testing at nearly full scale in low-gravity. This project is supported by the NASA Advanced Exploration Systems Program Office in the Human Exploration and Operations Mission Directorate. The activity of this project is supported by an international topical team of fire experts from other space agencies to maximize the utility of the data and to ensure the widest possible scrutiny of the concept. The large-scale space flight experiment will be conducted on three missions; each in an Orbital Sciences Corporation Cygnus vehicle after it has deberthed from the ISS. Although the experiment will need to meet rigorous safety requirements to ensure the carrier vehicle does not sustain damage, the absence of a crew allows the fire products to be released into the cabin. The tests will be fully automated with the data downlinked at the conclusion of the test before the Cygnus vehicle reenters the

Overview of IAEA guidelines for fire safety inspection and operation in nuclear power plants

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

In 1992, the International Atomic Energy Agency began an ambitious project on fire safety in nuclear power plants. The purpose of this ongoing project is to provide specific guidance on compliance with the requirements set forth through the IAEA Nuclear Safety Standards program established in 1974. The scope of the Fire Safety project encompasses several tasks, including the development of new standards and guidelines to assist Member States in assessing the level of fire safety in existing plants. Five new Safety Practices, one new Safety Guide and a Technical Document have been developed for use by the fire safety community. The primary intent of these new documents is to provide detailed guidance and a consistent format for the assessment of the overall level of fire safety being provided in existing nuclear power plants around the world and especially in developing countries. Sufficient detail is provided in the Safety Guide and Safety Practices to allow technically knowledgeable plant personnel, outside consultants or other technical experts to assess the adequacy of fire safety within the plant facilities. This paper describes topics addressed by each of the IAEA Fire Safety documents and discussed the relationship of each document to others in the series. (author)

The practical implementation of integrated safety management for nuclear safety analysis and fire hazards analysis documentation

International Nuclear Information System (INIS)

COLLOPY, M.T.

1999-01-01

In 1995 Mr. Joseph DiNunno of the Defense Nuclear Facilities Safety Board issued an approach to describe the concept of an integrated safety management program which incorporates hazard and safety analysis to address a multitude of hazards affecting the public, worker, property, and the environment. Since then the U S . Department of Energy (DOE) has adopted a policy to systematically integrate safety into management and work practices at all levels so that missions can be completed while protecting the public, worker, and the environment. While the DOE and its contractors possessed a variety of processes for analyzing fire hazards at a facility, activity, and job; the outcome and assumptions of these processes have not always been consistent for similar types of hazards within the safety analysis and the fire hazard analysis. Although the safety analysis and the fire hazard analysis are driven by different DOE Orders and requirements, these analyses should not be entirely independent and their preparation should be integrated to ensure consistency of assumptions, consequences, design considerations, and other controls. Under the DOE policy to implement an integrated safety management system, identification of hazards must be evaluated and agreed upon to ensure that the public. the workers. and the environment are protected from adverse consequences. The DOE program and contractor management need a uniform, up-to-date reference with which to plan. budget, and manage nuclear programs. It is crucial that DOE understand the hazards and risks necessarily to authorize the work needed to be performed. If integrated safety management is not incorporated into the preparation of the safety analysis and the fire hazard analysis, inconsistencies between assumptions, consequences, design considerations, and controls may occur that affect safety. Furthermore, confusion created by inconsistencies may occur in the DOE process to grant authorization of the work. In accordance with

Probabilistic safety analysis for fire events for the NPP Isar 2

International Nuclear Information System (INIS)

Schmaltz, H.; Hristodulidis, A.

2007-01-01

The 'Probabilistic Safety Analysis for Fire Events' (Fire-PSA KKI2) for the NPP Isar 2 was performed in addition to the PSA for full power operation and considers all possible events which can be initiated due to a fire. The aim of the plant specific Fire-PSA was to perform a quantitative assessment of fire events during full power operation, which is state of the art. Based on simplistic assumptions referring to the fire induced failures, the influence of system- and component-failures on the frequency of the core damage states was analysed. The Fire-PSA considers events, which will result due to fire-induced failures of equipment on the one hand in a SCRAM and on the other hand in events, which will not have direct operational effects but because of the fire-induced failure of safety related installations the plant will be shut down as a precautionary measure. These events are considered because they may have a not negligible influence on the frequency of core damage states in case of failures during the plant shut down because of the reduced redundancy of safety related systems. (orig.)

Fire safety assessment for the fire areas of the nuclear power plant using fire model CFAST

International Nuclear Information System (INIS)

Lee, Yoon Hwan; Yang, Joon Eon; Kim, Jong Hoon

2005-03-01

Now the deterministic analysis results for the cable integrity is not given in case of performing the fire PSA. So it is necessary to develop the assessment methodology for the fire growth and propagation. This document is intended to analyze the peak temperature of the upper gas layer using the fire modeling code, CFAST, to evaluate the integrity of the cable located on the dominant pump rooms, and to assess the CCDP(Conditional Core Damage Probability) using the results of the cable integrity. According to the analysis results, the cable integrity of the pump rooms is maintained and CCDP is reduced about two times than the old one. Accordingly, the fire safety assessment for the dominant fire areas using the fire modeling code will capable to reduce the uncertainty and to develop a more realistic model

Influence of safeguards and fire protection on criticality safety

International Nuclear Information System (INIS)

Six, D.E.

1980-01-01

There are several positive influences of safeguards and fire protection on criticality safety. Experts in each discipline must be aware of regulations and requirements of the others and work together to ensure a fault-tree design. EG and G Idaho, Inc., routinely uses an Occupancy-Use Readiness Manual to consider all aspects of criticality safety, fire protection, and safeguards. The use of the analytical tree is described

Large Scale Experiments on Spacecraft Fire Safety

DEFF Research Database (Denmark)

Urban, David L.; Ruff, Gary A.; Minster, Olivier

2012-01-01

-based microgravity facilities or has been limited to very small fuel samples. Still, the work conducted to date has shown that fire behaviour in low-gravity is very different from that in normal-gravity, with differences observed for flammability limits, ignition delay, flame spread behaviour, flame colour and flame......Full scale fire testing complemented by computer modelling has provided significant knowhow about the risk, prevention and suppression of fire in terrestrial systems (cars, ships, planes, buildings, mines, and tunnels). In comparison, no such testing has been carried out for manned spacecraft due...... to the complexity, cost and risk associ-ated with operating a long duration fire safety experiment of a relevant size in microgravity. Therefore, there is currently a gap in knowledge of fire behaviour in spacecraft. The entire body of low-gravity fire research has either been conducted in short duration ground...

Instrumentation for mine safety: fire and smoke problems and solutions

International Nuclear Information System (INIS)

Stevens, R.B.

1982-01-01

Underground fires continue to be one of the most serious hazards to life and property in the mining industry. Although underground mines are analogous to high-rise buildings where persons are isolated from immediate escape or rescue, application of technology to locate and control fire hazards while still in their controllable state is slow to be implemented in underground mines. This paper describes several USBM (Bureau of Mines) safety programs which included in-mine testing with mine fire and smoke sensors, telemetry and instrumentation to develop recommendations for improving mine fire safety. It is hoped that the technology developed during these programs can be added to other programs to provide the mining industry with the necessary fire safety facts. By recognizing fire potentials and being provided with cost-effective, proven components that will perform reliably under the poor environmental conditions of mining, mine operators can provide protection for their working life and property equal to that which they provide for themselves and their families at home. The basis of this report is two USBM programs for fire protection in metal and nonmetal mines and one coal program. The data was collected beginning in May 1974 and continuing through the present with underground tests of a South African fire system installed at Magma Mine in Superior, Arizona, and a computer-assisted, experimental system at Peabody Coal Mine in Pawnee, Illinois

Nuclear hazard/fire hazard: an elusive and important linkage

International Nuclear Information System (INIS)

Mariani, L.P.

1977-01-01

The Brown's Ferry Fire signaled a yellow alert for nuclear safety related fire protection and showed that fire protection engineering must be regarded as a bona fide nuclear discipline. A single-failure design criteria violation resulted in fire damage to plant systems and plant instrumentation. Localized damage lead to significant consequences. Although the linkage between fire and nuclear hazard is termed subtle, effective standards and criteria development must be aimed to future plants. Combined fire protection and nuclear engineering inspections are planned

A study on fire spreading model for the safety distance between the neighborhood occupancies and historical buildings in Taiwan

Science.gov (United States)

Chen, C. H.; Chien, S. W.; Ho, M. C.

2015-08-01

Cultural heritages and historical buildings are vulnerable against severe threats from fire. Since the 1970s, ten fire-spread events involving historic buildings have occurred in Taiwan, affecting a total of 132 nearby buildings. Developed under the influence of traditional Taiwanese culture, historic buildings in Taiwan are often built using non-fire resistant brick-wood structure and located in proximity to residential occupancies. Fire outbreak in these types of neighborhood will lead to severe damage of antiquities, leaving only unrecoverable historical imagery. This study is aimed to investigate the minimal safety distance required between a historical building and its surroundings in order to reduce the risk of external fire. This study is based on literature analysis and the fire spread model using a Fire Dynamics Simulator. The selected target is Jingmei Temple in Taipei City. This study explored local geography to identify patterns behind historical buildings distribution. In the past, risk reduction engineering for cultural heritages and historical buildings focused mainly on fire equipment and the available personnel with emergency response ability, and little attention was given to external fire risks and the affected damage. Through discussions on the required safety distance, this research provides guidelines for the following items: management of neighborhoods with historical buildings and consultation between the protection of cultural heritages and disaster prevention, reducing the frequency and extent of fire damages, and preserving cultural resource.

EFFICIENCY OF FIRE-FIGHTING PROTECTION OBJECTS IN PROVISION OF FIRE SAFETY AT INDUSTRIAL ENTERPRISES

Directory of Open Access Journals (Sweden)

A. V. Zhovna

2008-01-01

Full Text Available The paper gives an analysis of economic results pertaining to organization of a system for fire-fighting protection of industrial enterprises in theRepublicofBelarus. Statistical data on operational conditions of technical means of fire-fighting protection, particularly, automatic systems for detection and extinguishing of fires, systems of internal fire-fighting water-supply.  Requirements and provisions  of normative and technical documents are thoroughly studied. Observance of these documents is to ensure the required level of  fire safety. On the basis of the obtained results concerning  economic analysis of efficiency optimization directions are defined for selection of technical means of fire-fighting protection at objects of industrial purpose.

Fire safety improvement of para-aramid fiber in thermoplastic polyurethane elastomer

International Nuclear Information System (INIS)

Chen, Xilei; Wang, Wenduo; Li, Shaoxiang; Jiao, Chuanmei

2017-01-01

Highlights: • Fire safety of para-aramid fiber on TPU has been investigated. • Para-aramid fiber has excellent flame retardant abilities and smoke suppression properties on TPU. • A new technique to improve the fire safety polymer is provided in this article. - Abstract: This article mainly studied fire safety effects of para-aramid fiber (AF) in thermoplastic polyurethane (TPU). The TPU/AF composites were prepared by molten blending method, and then the fire safety effects of all TPU composites were tested using cone calorimeter test (CCT), microscale combustion colorimeter test (MCC), smoke density test (SDT), and thermogravimetric/fourier transform infrared spectroscopy (TG-IR). The CCT test showed that AF could improve the fire safety of TPU. Remarkably, the peak value of heat release rate (pHRR) and the peak value of smoke production rate (pSPR) for the sample with 1.0 wt% content of AF were decreased by 52.0% and 40.5% compared with pure TPU, respectively. The MCC test showed that the HRR value of AF-2 decreased by 27.6% compared with pure TPU. TG test showed that AF promoted the char formation in the degradation process of TPU; as a result the residual carbon was increased. The TG-IR test revealed that AF had increased the thermal stability of TPU at the beginning and reduced the release of CO_2 with the decomposition going on. Through the analysis of the results of this experiment, it will make a great influence on the study of the para-aramid fiber in the aspect of fire safety of polymer.

Fire safety improvement of para-aramid fiber in thermoplastic polyurethane elastomer

Energy Technology Data Exchange (ETDEWEB)

Chen, Xilei; Wang, Wenduo; Li, Shaoxiang; Jiao, Chuanmei, E-mail: jiaochm@qust.edu.cn

2017-02-15

Highlights: • Fire safety of para-aramid fiber on TPU has been investigated. • Para-aramid fiber has excellent flame retardant abilities and smoke suppression properties on TPU. • A new technique to improve the fire safety polymer is provided in this article. - Abstract: This article mainly studied fire safety effects of para-aramid fiber (AF) in thermoplastic polyurethane (TPU). The TPU/AF composites were prepared by molten blending method, and then the fire safety effects of all TPU composites were tested using cone calorimeter test (CCT), microscale combustion colorimeter test (MCC), smoke density test (SDT), and thermogravimetric/fourier transform infrared spectroscopy (TG-IR). The CCT test showed that AF could improve the fire safety of TPU. Remarkably, the peak value of heat release rate (pHRR) and the peak value of smoke production rate (pSPR) for the sample with 1.0 wt% content of AF were decreased by 52.0% and 40.5% compared with pure TPU, respectively. The MCC test showed that the HRR value of AF-2 decreased by 27.6% compared with pure TPU. TG test showed that AF promoted the char formation in the degradation process of TPU; as a result the residual carbon was increased. The TG-IR test revealed that AF had increased the thermal stability of TPU at the beginning and reduced the release of CO{sub 2} with the decomposition going on. Through the analysis of the results of this experiment, it will make a great influence on the study of the para-aramid fiber in the aspect of fire safety of polymer.

Archer Fire and Safety - reducing risk in the offshore

Energy Technology Data Exchange (ETDEWEB)

Todd, K

2000-06-01

Protecting the lives and safety of offshore oil and gas workers is the business of Newfoundland-based Archer Fire and Safety. Originally established as a supplier of industrial materials focusing on the oil and gas industry, the company narrowed its focus in 1996 to fire and safety protection, introduced more specialized fire and safety equipment, and began to explore service opportunities to the industry in addition to the usual consumables. After some anxious few years, the company now operates two SCBA service centres in Newfoundland, in addition to sales and servicing a wide range of fire and safety equipment such as gas, flame and heat detection.The company is constantly on the lookout for new opportunities and has developed a computer-based pricing system which enables them to provide quick response to pricing inquiries, a big advantage in an industry with relatively unsophisticated business practices. The company's emphasis on research and quick response capability enabled the company to anticipate future requirements and to land major contracts first at Bull Arm, and later on the Terra Nova Project. Its reputation for best-in-class products, high quality service and a business-like approach helped to attract other clients such as Terra Nova Alliance, Canship and Schlumberger, and offshore drilling companies like Glomar International and TransOcean Sedco-Forex, with further opportunities in the offing with upcoming projects such as the White Rose and Hebron.Today about 60 per cent of the business is offshore related.

Archer Fire and Safety - reducing risk in the offshore

Energy Technology Data Exchange (ETDEWEB)

Todd, K.

2000-06-01

Protecting the lives and safety of offshore oil and gas workers is the business of Newfoundland-based Archer Fire and Safety. Originally established as a supplier of industrial materials focusing on the oil and gas industry, the company narrowed its focus in 1996 to fire and safety protection, introduced more specialized fire and safety equipment, and began to explore service opportunities to the industry in addition to the usual consumables. After some anxious few years, the company now operates two SCBA service centres in Newfoundland, in addition to sales and servicing a wide range of fire and safety equipment such as gas, flame and heat detection.The company is constantly on the lookout for new opportunities and has developed a computer-based pricing system which enables them to provide quick response to pricing inquiries, a big advantage in an industry with relatively unsophisticated business practices. The company's emphasis on research and quick response capability enabled the company to anticipate future requirements and to land major contracts first at Bull Arm, and later on the Terra Nova Project. Its reputation for best-in-class products, high quality service and a business-like approach helped to attract other clients such as Terra Nova Alliance, Canship and Schlumberger, and offshore drilling companies like Glomar International and TransOcean Sedco-Forex, with further opportunities in the offing with upcoming projects such as the White Rose and Hebron.Today about 60 per cent of the business is offshore related.

Building Fire Safety Audit at Faculty X, University of Indonesia, Year 2006

Directory of Open Access Journals (Sweden)

Fatma Lestari

2010-10-01

Full Text Available Fire may cause loss of life, material and valuable assets. The objective of this study is to conduct audit for fire safety and emergency response in the building at Faculty X, University of Indonesia, Depok. The audit results on the building fire safety facilities including emergency response and preparedness are then compared to the Building Code Australia (BCA and Indonesian regulation on the building fire safety (Kep.MenPU.No 10 and 11/KPTS/2000. The building selected are Building A, B, C, D, F and G. Building classification for A, B, D, F and G are classified as Class 5, while Building C is classified as Class 9b. Variable which are evaluated including emergency exit, building structure, fire alarm and detector, communication and fire warning system, evacuation procedure, portable fire extinguishers, hydrant, sprinkler, and emergency response preparedness. Results suggested that emergency exit is locked, and this is not comply to the regulation. Building structure has been complied to the regulation since it was made of concrete. Fire detector and alarm only provided in Building G, while other building is not available. There is no evacuation procedure available. Portable fire extinguisher has been available in all the building. Hydrant an sprinkler only available in building G. There is no emergency response preparedness in this faculty. In conclusion, the fire safety facilities in this faculty need to be improved.

78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

Science.gov (United States)

2013-03-20

... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

Fire Protection Program Manual

Energy Technology Data Exchange (ETDEWEB)

Sharry, J A

2012-05-18

This manual documents the Lawrence Livermore National Laboratory (LLNL) Fire Protection Program. Department of Energy (DOE) Orders 420.1B, Facility Safety, requires LLNL to have a comprehensive and effective fire protection program that protects LLNL personnel and property, the public and the environment. The manual provides LLNL and its facilities with general information and guidance for meeting DOE 420.1B requirements. The recommended readers for this manual are: fire protection officers, fire protection engineers, fire fighters, facility managers, directorage assurance managers, facility coordinators, and ES and H team members.

Performance Assessment and analysis of national building codes with fire safety in all wards of a hospital

Directory of Open Access Journals (Sweden)

M. Mahdinia

2009-04-01

Full Text Available Background and aimsAIDS as a re-emergent disease and Viral hepatitis (B and C as one of thBackground and objective: Fire safety is an important problem in hospitals. Movement less, lack of awareness and special situation of residents are the reasons of this subject. In more countries such as Iran, fire protection regulations have compiled within the framework of national building codes. Current building codes don't create sufficient safety for patient in the hospitals in different situations and more of the advanced countries in the world effort to establish building code, base  on performance. This study to be accomplished with this goal that determination of fire risk level in the wards of a hospital and survey the efficiency of the national building codes. Methodsfire risk assesses is done, using "engineering fire risk assessment method" with the checklist for Data gathering. In this manner, risk calculate in all compartments and in the next  stage for survey the effect of building codes, with this supposition that all compartment is  conforming to building code requirement, risk level calculate in two situation.Resultsthe results of present study reveals that, risk level in all wards is more than one and even though risk less than one is acceptable, consequently minimum of safely situations didn't  produce in most wards. The results show the national building code in the different conditions  don't have appropriate efficient for creation of suitable safety. Conclusionin order to access to a fire safety design with sufficient efficiency, suitable selection is use of risk assessment based on, design methods.

Inspection of fire protection measures and fire fighting capability at nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire protection of nuclear power plants. The publication outlines practices for inspecting the fire protection measures at nuclear power plants in accordance with Safety Series No.50-SG-D2(Rev.1), Fire Protection in Nuclear Power Plants, and includes a comprehensive fire safety inspection checklist of the specific elements to be addressed when evaluating the adequacy and effectiveness of the fire protection measures and manual fire fighting capability available at operating nuclear power plants. The publication will be useful not only to regulators and safety assessors but also to operators and designers. The book addresses a specialized topic and it is recommended that it be used in conjunction with Safety Guide No.50-SG-D2(Rev.1)

Probability based high temperature engineering creep and structural fire resistance

CERN Document Server

Razdolsky, Leo

2017-01-01

This volume on structural fire resistance is for aerospace, structural, and fire prevention engineers; architects, and educators. It bridges the gap between prescriptive- and performance-based methods and simplifies very complex and comprehensive computer analyses to the point that the structural fire resistance and high temperature creep deformations will have a simple, approximate analytical expression that can be used in structural analysis and design. The book emphasizes methods of the theory of engineering creep (stress-strain diagrams) and mathematical operations quite distinct from those of solid mechanics absent high-temperature creep deformations, in particular the classical theory of elasticity and structural engineering. Dr. Razdolsky’s previous books focused on methods of computing the ultimate structural design load to the different fire scenarios. The current work is devoted to the computing of the estimated ultimate resistance of the structure taking into account the effect of high temperatur...

OMS engine firing

Science.gov (United States)

1983-01-01

An Orbital maneuvering system (OMS) engine firing caused this bright glow at the aft end of the shuttle Challenger during STS-7. Also visible in the open payload bay are parts of the Shuttle pallet satellite (SPAS-01), the experiment package for NASA's Office of Space and Terrestrial Applications (OSTA-2), the protective cradles for the Indonesian Palapa-B and Telesat Canada Anik C2 satellites, some getaway special (GAS) canisters and the Canadian built remote manipulator system (RMS). Only a small portion of the earth's horizon can be seen above the orbiter's vertical stabilizer.

Development of IFC based fire safety assesment tools

DEFF Research Database (Denmark)

Taciuc, Anca; Karlshøj, Jan; Dederichs, Anne

2016-01-01

Due to the impact that the fire safety design has on the building's layout and on other complementary systems, as installations, it is important during the conceptual design stage to evaluate continuously the safety level in the building. In case that the task is carried out too late, additional...... changes need to be implemented, involving supplementary work and costs with negative impact on the client. The aim of this project is to create a set of automatic compliance checking rules for prescriptive design and to develop a web application tool for performance based design that retrieves data from...... Building Information Models (BIM) to evacuate the safety level in the building during the conceptual design stage. The findings show that the developed tools can be useful in AEC industry. Integrating BIM from conceptual design stage for analyzing the fire safety level can ensure precision in further...

Root cause analysis for fire events at nuclear power plants

International Nuclear Information System (INIS)

1999-09-01

Fire hazard has been identified as a major contributor to a plant' operational safety risk. The International nuclear power community (regulators, operators, designers) has been studying and developing tools for defending against this hazed. Considerable advances have been achieved during past two decades in design and regulatory requirements for fire safety, fire protection technology and related analytical techniques. The IAEA endeavours to provide assistance to Member States in improving fire safety in nuclear power plants. A task was launched by IAEA in 1993 with the purpose to develop guidelines and good practices, to promote advanced fire safety assessment techniques, to exchange state of the art information, and to provide engineering safety advisory services and training in the implementation of internationally accepted practices. This TECDOC addresses a systematic assessment of fire events using the root cause analysis methodology, which is recognized as an important element of fire safety assessment

Safety during sea transport of radioactive materials. Probabilistic safety analysis of package fro sea surface fire accident

International Nuclear Information System (INIS)

Matsuoka, Takeshi; Obara, Isonori; Akutsu, Yukio; Aritomi, Masanori

2000-01-01

The ships carrying irradiated nuclear fuel, plutonium and high level radioactive wastes(INF materials) are designed to keep integrity of packaging based on the various safety and fireproof measures, even if the ship encounters a maritime fire accident. However, granted that the frequency is very low, realistic severe accidents should be evaluated. In this paper, probabilistic safety assessment method is applied to evaluate safety margin for severe sea fire accidents using event tree analysis. Based on our separate studies, the severest scenario was estimated as follows; an INF transport ship collides with oil tanker and induces a sea surface fire. Probability data such as ship's collision, oil leakage, ignition, escape from fire region, operations of cask cooling system and water flooding systems were also introduced from above mentioned studies. The results indicate that the probability of which packages cannot keep their integrity during the sea surface fire accident is very low and sea transport of INF materials is carried out very safely. (author)

Propulsion and Energetics Panel Working Group 11 on Aircraft Fire Safety. Volume 2. Main Report

Science.gov (United States)

1979-11-01

which make burning metal particles a potent igni- tion source and extinguishment of bulk metal fires a difficult task. In the latter case, the difficulty...aircraft to fires induced by uncon- tained engine failures and internal engine metal fires . With respect to the uncontained engine failure current engine

FIRE-PRAN

International Nuclear Information System (INIS)

Waterfall, K.W.

1991-01-01

Shell Internationale Petroleum Maatschappij B.V. (SIPM), is a service company in the Royal Dutch/Shell Group of Companies who provides services worldwide (outside of the USA) to Shell Operating Companies. It has defined and recommended for implementation by Shell Companies a policy on safety (Enhanced Safety Management policy) to manage the total safety aspects of all they do, including the design, engineering, installation and operation of their facilities worldwide. This policy affects all activities in such a way as to avoid harm to health of, or injury to employees and others as well as avoiding damage to property. This in turn reflects through specific policies and standards for investment strategy, engineering and operations of facilities. With average Group losses due to major fires and explosion (for each incident over Brit-pounds 100,000) between 1988 and 1990 being of the order of Brit-pounds 28 million, there is an obvious potential to effectively employ fire protection criteria in design. However, Shell need to ensure the cost-effective application of protective measures, but first and foremost it is essential not to jeopardize life or risk damage to the environment. FIRE-PRAN has the possibility to do this efficiently as it is A systematic team approach for identification of all potential fire and explosion hazards and consequences, and a means for developing optimal means of protection for all types of facilities. It should thus be considered as an auditing technique, but one that fits into the overall safe management of activities. This paper discusses the status of development of the FIRE-PRAN technique following its successful application over a number of years to a variety of equipment and installations

Operating room fire prevention: creating an electrosurgical unit fire safety device.

Science.gov (United States)

Culp, William C; Kimbrough, Bradly A; Luna, Sarah; Maguddayao, Aris J

2014-08-01

To reduce the incidence of surgical fires. Operating room fires represent a potentially life-threatening hazard and are triggered by the electrosurgical unit (ESU) pencil. Carbon dioxide is a fire suppressant and is a routinely used medical gas. We hypothesize that a shroud of protective carbon dioxide covering the tip of the ESU pencil displaces oxygen, thereby preventing fire ignition. Using 3-dimensional modeling techniques, a polymer sleeve was created and attached to an ESU pencil. This sleeve was connected to a carbon dioxide source and directed the gas through multiple precisely angled ports, generating a cone of fire-suppressive carbon dioxide surrounding the active pencil tip. This device was evaluated in a flammability test chamber containing 21%, 50%, and 100% oxygen with sustained ESU activation. The sleeve was tested with and without carbon dioxide (control) until a fuel was ignited or 30 seconds elapsed. Time to ignition was measured by high-speed videography. Fires were ignited with each control trial (15/15 trials). The control group median ± SD ignition time in 21% oxygen was 3.0 ± 2.4 seconds, in 50% oxygen was 0.1 ± 1.8 seconds, and in 100% oxygen was 0.03 ± 0.1 seconds. No fire was observed when the fire safety device was used in all concentrations of oxygen (0/15 trials; P fire ignition was 76% to 100%. A sleeve creating a cone of protective carbon dioxide gas enshrouding the sparks from an ESU pencil effectively prevents fire in a high-flammability model. Clinical application of this device may reduce the incidence of operating room fires.

Safety engineering with COTS components

International Nuclear Information System (INIS)

O'Halloran, Mark; Hall, Jon G.; Rapanotti, Lucia

2017-01-01

Safety-critical systems are becoming more widespread, complex and reliant on software. Increasingly they are engineered through (COTS) (Commercial Off The Shelf) components to alleviate the spiralling costs and development time, often in the context of complex supply chains. A parallel increased concern for safety has resulted in a variety of safety standards, with a growing consensus that a safety life cycle is needed which is fully integrated with the design and development life cycle, to ensure that safety has appropriate influence on the design decisions as system development progresses. In this article we explore the application of an integrated approach to safety engineering in which assurance drives the engineering process. The paper reports on the outcome of a case study on a live industrial project with a view to evaluate: its suitability for application in a real-world safety engineering setting; its benefits and limitations in counteracting some of the difficulties of safety engineering with (COTS) components across supply chains; and, its effectiveness in generating evidence which can contribute directly to the construction of safety cases. - Highlights: • Assurance as effective driver for COTS-based safety-critical system development. • Engages stakeholders, captures requirements and provides rich traceability. • Shares appropriate safety requirements across the supply chain.

An assessment of the impact of home safety assessments on fires and fire-related injuries: a case study of Cheshire Fire and Rescue Service.

Science.gov (United States)

Arch, B N; Thurston, M N

2013-06-01

Deaths and injuries related to fires are largely preventable events. In the UK, a plethora of community-based fire safety initiatives have been introduced over the last 25 years, often led by fire and rescue services, to address this issue. This paper focuses on one such initiative--home safety assessments (HSAs). Cheshire Fire and Rescue Service (in England) implemented a uniquely large-scale HSA intervention. This paper assesses its effectiveness. The impact of HSAs was assessed in relation to three outcomes: accidental dwelling fires (ADFs), ADFs contained and injuries arising from ADFs. A two-period comparison in fire-related rates of incidences in Cheshire between 2002 and 2011 was implemented, using Poisson regression and adjusting for the national temporal trend using a control group comprising the 37 other English non-metropolitan fire-services. Significant reductions were observed in rates of ADFs [incidence rate ratios (IRR): 0.79, 95% confidence interval (CI): 0.74-0.83, P fires contained to room of origin. There is strong evidence to suggest that the intervention was successful in reducing domestic fires and related injuries.

A study on fire design accidental loads for aluminum safety helidecks

Directory of Open Access Journals (Sweden)

Sang Jin Kim

2016-11-01

Full Text Available The helideck structure must satisfy the safety requirements associated with various environmental and accidental loads. Especially, there have been a number of fire accidents offshore due to helicopter collision (take-off and/or landing in recent decades. To prevent further accidents, a substantial amount of effort has been directed toward the management of fire in the safety design of offshore helidecks. The aims of this study are to introduce and apply a procedure for quantitative risk assessment and management of fires by defining the fire loads with an applied example. The frequency of helicopter accidents are considered, and design accidental levels are applied. The proposed procedures for determining design fire loads can be efficiently applied in offshore helideck development projects.

Hotel and Motel Fire Safety Project - USFA

Data.gov (United States)

Department of Homeland Security — Provides a listing of properties compliant with the requirements of the Hotel and Motel Fire Safety Act of 1990. Users may search for compliant properties and submit...

Safety study of fire protection for nuclear fuel cycle facility

International Nuclear Information System (INIS)

2013-01-01

Insufficiencies in the fire protection system of the nuclear reactor facilities were pointed out when the fire occurred due to the Niigata prefecture-Chuetsu-oki Earthquake in July, 2007. This prompted the revision of the fire protection safety examination guideline for nuclear reactors as well as commercial guidelines. The commercial guidelines have been endorsed by the regulatory body. Now commercial fire protection standards for nuclear facilities such as the design guideline and the management guideline for protecting fire in the Light Water Reactors (LWRs) are available, however, those to apply to the nuclear fuel cycle facilities such as mixed oxide fuel fabrication facility (MFFF) have not been established. For the improvement of fire protection system of the nuclear fuel cycle facilities, the development of a standard for the fire protection, corresponding to the commercial standard for LWRs were required. Thus, Japan Nuclear Energy Safety Organization (JNES) formulated a fire protection guidelines for nuclear fuel cycle facilities as a standard relevant to the fire protection of the nuclear fuel cycle facilities considering functions specific to the nuclear fuel cycle facilities. In formulating the guidelines, investigation has been conduced on the commercial guidelines for nuclear reactors in Japan and the standards relevant to the fire protection of nuclear facilities in USA and other countries as well as non-nuclear industrial fire protection standards. The guideline consists of two parts; Equipments and Management, as the commercial guidances of the nuclear reactor. In addition, the acquisition of fire evaluation data for a components (an electric cabinet, cable, oil etc.) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

Fire safety in the atomic age

International Nuclear Information System (INIS)

Whitman, L.E.

1980-01-01

This nontechnical review of radiation hazards acquaints those faced with radiation fire-safety problems (firemen, plant safety personnel, technicians, and others) with what the hazards are, where they may be found, and how to deal with them. It removes unnecessary fears and misconceptions by giving a picture of radiation as something that is neither to be feared nor ignored, but rather something that can be lived with safely. Since all radioactive materials emit energy that has the power to damage living tissue, those involved with fire protection who might come into contact with such materials must understand both the real dangers from a variety of radiation exposures, and the safest, most-effective ways to avert danger to themselves and others. Whitman discusses in detail the potential hazards, from contamination from radioactive waste to transportation of radioactive materials, from nuclear power plants to radiation machinery and nuclear weapons. He presents the basic facts and includes practical problems to be solved. 14 references, 65 figures

Fire Safety Tests for Spherical Resorcinol Formaldehyde Resin: Data Summary Report

Energy Technology Data Exchange (ETDEWEB)

Kim, Dong-Sang; Peterson, Reid A.; Schweiger, Michael J.

2012-07-30

A draft safety evaluation of the scenario for spherical resorcinol-formaldehyde (SRF) resin fire inside the ion exchange column was performed by the Hanford Tank Waste Treatment and Immobilization Plant (WTP) Fire Safety organization. The result of this draft evaluation suggested a potential change of the fire safety classification for the Cesium Ion Exchange Process System (CXP) emergency elution vessels, equipment, and piping, which may be overly bounding based on the fire performance data from the manufacturer of the ion exchange resin selected for use at the WTP. To resolve this question, the fire properties of the SRF resin were measured by Southwest Research Institute (SwRI), following the American Society for Testing and Materials (ASTM) standard procedures, through a subcontract managed by Pacific Northwest National Laboratory (PNNL). For some tests, the ASTM standard procedures were not entirely appropriate or practical for the SRF resin material, so the procedures were modified and deviations from the ASTM standard procedures were noted. This report summarizes the results of fire safety tests performed and reported by SwRI. The efforts by PNNL were limited to summarizing the test results provided by SwRI into one consolidated data report. All as-received SwRI reports are attached to this report in the Appendix. Where applicable, the precision and bias of each test method, as given by each ASTM standard procedure, are included and compared with the SwRI test results of the SRF resin.

Repository Subsurface Preliminary Fire Hazard Analysis

International Nuclear Information System (INIS)

Logan, Richard C.

2001-01-01

This fire hazard analysis identifies preliminary design and operations features, fire, and explosion hazards, and provides a reasonable basis to establish the design requirements of fire protection systems during development and emplacement phases of the subsurface repository. This document follows the Technical Work Plan (TWP) (CRWMS M and O 2001c) which was prepared in accordance with AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''; Attachment 4 of AP-ESH-008, ''Hazards Analysis System''; and AP-3.11Q, ''Technical Reports''. The objective of this report is to establish the requirements that provide for facility nuclear safety and a proper level of personnel safety and property protection from the effects of fire and the adverse effects of fire-extinguishing agents

Fire protection system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor

Fire protection system operating experience review for fusion applications

Energy Technology Data Exchange (ETDEWEB)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor.

Systems Safety and Engineering Division

Data.gov (United States)

Federal Laboratory Consortium — Volpe's Systems Safety and Engineering Division conducts engineering, research, and analysis to improve transportation safety, capacity, and resiliency. We provide...

14 CFR 25.865 - Fire protection of flight controls, engine mounts, and other flight structure.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fire protection of flight controls, engine... Design and Construction Fire Protection § 25.865 Fire protection of flight controls, engine mounts, and other flight structure. Essential flight controls, engine mounts, and other flight structures located in...

The study on safety facility criteria for radioactive waste repository

International Nuclear Information System (INIS)

Lee, S. H.; Choi, M. H.; Han, S. H. and others

1992-12-01

The radioactive waste repository are necessary to install the engineered safety systems to secure the safety for operation of the repository in the event of fire and earthquake. Since the development of safety facility criteria requires a thorough understanding about the characteristics of the engineered safety systems, we should investigate by means of literature survey and visit SKB. In particular, definition, composition of the systems, functional requirement of the systems, engineered safety systems of foreign countries, system design, operation and maintenance requirement should be investigated : fire protection system, ventilation system, drainage system, I and C system, electric system, radiation monitoring system. This proposed criteria consist of purpose, scope of application, ventilation system, fire protection system, drainage system, electric system and this proposed criteria can be applied as a basic reference for the final criteria

Focus on the studies in support of fire safety analysis. IRSN modelling approach for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Espargilliere, Julien; Meyrand, Raphael; Vinot, Thierry [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France)

2015-12-15

For a fire safety analysis, in order to comply with nuclear safety goals, a nuclear fuel facility operator has to define the elements important for safety to be maintained, even in the case of a fire. One of the key points of this fire analysis is the assessment of possible fire scenarios in the facility. This paper presents the IRSN method applied to a case study to assess fire scenarios which have the most harmful effects on safety targets. The layout consists in a central room (fire cell) containing three glove boxes with radioactive material and three electrical cabinets. This room is linked to two connecting compartments (the fire cell and these two compartments define the containment cell) and then to two corridors. Each room is equipped with a mechanical ventilation system, and a pressure cascade is established from the corridors to the central room. A fire scenario was studied with fire ignition occurring in an electrical cabinet. This scenario has a set of safety goals (prevention of fire cell and containment device failure, propagation of the fire). This case study was conducted with the IRSN code SYLVIA based on two zones modelling. Safety goals were associated with key parameters and performance criteria to be fulfilled. Modelling assumptions were defined in order to maximize physical effects of the fire. Sensitivity studies were also conducted on key parameters such as oxygen limitation, equivalent-fuel definition. Eventually, a critical analysis of the code models was carried out.

Chemical research projects office functions accomplishments programs. [applied research in the fields of polymer chemistry and polymeric composites with emphasis on fire safety

Science.gov (United States)

Heimbuch, A. H.; Parker, J. A.

1975-01-01

Basic and applied research in the fields of polymer chemistry, polymeric composites, chemical engineering, and biophysical chemistry is summarized. Emphasis is placed on fire safety and human survivability as they relate to commercial and military aircraft, high-rise buildings, mines and rapid transit transportation. Materials systems and other fire control systems developed for aerospace applications and applied to national domestic needs are described along with bench-scale and full-scale tests conducted to demonstrate the improvements in performance obtained through the utilization of these materials and fire control measures.

Topology optimization for simplified structural fire safety

DEFF Research Database (Denmark)

Madsen, Søren; Lange, Nis P.; Giuliani, Luisa

2016-01-01

Topology optimization is applied in an idealized structural fire safety model, where the minimum compliance problem is constrained by temperature-controlled structural degradation. The constraint ensures a certain structural stiffness after a prescribed time. As this time period is extended......, resulting optimized topologies tend to become thicker or introduce redundant members that can take over when structural parts near the origin of the fire lose their load carrying capability. Hence, the structural degradation model acts as an erosion operator on the topology and indirectly enforces a minimum...

Different design approaches to structural fire safety

DEFF Research Database (Denmark)

Giuliani, Luisa; Budny, I.

2013-01-01

-priori evaluate which design is the safest or the most economical one: a punctual analysis of the different aspects and a comparison of the resulting designs is therefore of interest and is presented in this paper with reference to the case study considered.The third approach refers instead to a performance......-based fire design of the structure(PBFD), where safety goals are explicitly defined and a deeper knowledge of the structural response to fire effects can be achieved, for example with the avail of finite element analyses (FEA). On the other hand, designers can’t follow established procedures when undertaking...... such advanced investigations, which are generally quite complex ones, due to the presence of material degradation and large displacements induced by fire, as well as the possible triggering of local mechanism in the system. An example of advanced investigations for fire design is given in the paper...

Modeling of compartment fire

International Nuclear Information System (INIS)

Sathiah, P.; Siccama, A.; Visser, D.; Komen, E.

2011-01-01

Fire accident in a containment is a serious threat to nuclear reactors. Fire can cause substantial loss to life and property. The risk posed by fire can also exceed the risk from internal events within a nuclear reactor. Numerous research efforts have been performed to understand and analyze the phenomenon of fire in nuclear reactor and its consequences. Modeling of fire is an important subject in the field of fire safety engineering. Two approaches which are commonly used in fire modeling are zonal modeling and field modeling. The objective of this work is to compare zonal and field modeling approach against a pool fired experiment performed in a well-confined compartment. Numerical simulations were performed against experiments, which were conducted within PRISME program under the framework of OECD. In these experiments, effects of ventilation flow rate on heat release rate in a confined and mechanically ventilated compartment is investigated. Time dependent changes in gas temperature and oxygen mass fraction were measured. The trends obtained by numerical simulation performed using zonal model and field model compares well with experiments. Further validation is needed before this code can be used for fire safety analyses. (author)

EFFECTS OF FIRE FUMES ON ALMOND SAFETY AND QUALITY

Directory of Open Access Journals (Sweden)

Amanda Ramírez-Gandolfo

2011-08-01

Full Text Available A fire originated and burnt two cold chambers; the present study focused on almonds stored in adjacent chambers (4, 5, 6 and 13 and evaluated both their food safety and quality. Testing for polycyclic aromatic hydrocarbons, polychlorinated dibenzo-p-dioxins and dibenzofurans was carried out in affected facilities, packaging and almonds. Experimental results proved that fire fumes did not reach chambers 4-6, but traces were found in bin packaging of chamber 13; thus, packaging from this chamber were changed. Concentrations of benzo(apyrene were low enough to prove that fire fumes did not get in contact with the stored almonds. Later, only volatile compounds typical of nuts were identified in both raw and toasted almonds. Finally, a trained panel concluded that no sensory signal of fumes reaching almonds was found. This manuscript could be taken as a model protocol to establish whether fire fumes have reached and affected the safety and/or quality of foods. This information will be especially useful for insurance companies.

Idaho National Engineering and Environmental Laboratory Wildland Fire Management Environmental Assessment

Energy Technology Data Exchange (ETDEWEB)

Irving, John S

2003-04-01

DOE prepared an environmental assessment (EA)for wildland fire management activities on the Idaho National Engineering and Environmental Laboratory (INEEL) (DOE/EA-1372). The EA was developed to evaluate wildland fire management options for pre-fire, fire suppression, and post fire activities. Those activities have an important role in minimizing the conversion of the native sagebrush steppe ecosystem found on the INEEL to non-native weeds. Four alternative management approaches were analyzed: Alternative 1 - maximum fire protection; Alternative 2 - balanced fire protection; Alternative 2 - balanced fire protection; Alternative 3 - protect infrastructure and personnel; and Alternative 4 - no action/traditional fire protection.

Using Modeling and Rehearsal to Teach Fire Safety to Children with Autism

Science.gov (United States)

Garcia, David; Dukes, Charles; Brady, Michael P.; Scott, Jack; Wilson, Cynthia L.

2016-01-01

We evaluated the efficacy of an instructional procedure to teach young children with autism to evacuate settings and notify an adult during a fire alarm. A multiple baseline design across children showed that an intervention that included modeling, rehearsal, and praise was effective in teaching fire safety skills. Safety skills generalized to…

10th Asia-Oceania Symposium on Fire Science and Technology

CERN Document Server

Matsuyama, Ken; Himoto, Keisuke; Nakamura, Yuji; Wakatsuki, Kaoru

2017-01-01

This book focuses on topics in the entire spectrum of fire safety science, targeting research in fires, explosions, combustion science, heat transfer, fluid dynamics, risk analysis, structural engineering, and other subjects. The book contributes to a gain in advanced scientific knowledge and presents or advances new ideas in all topics in fire safety science. Two decades ago, the 1st Asia-Oceania Symposium on Fire Science and Technology was held in Hefei, China. Since then, the Asia-Oceania Symposia have grown in size and quality. This book, reflecting that growth, helps readers to understand fire safety technology, design, and methodology in diverse areas including historical buildings, photovoltaic panels, batteries, and electric vehicles.

Quantitative assessment of safety barrier performance in the prevention of domino scenarios triggered by fire

International Nuclear Information System (INIS)

Landucci, Gabriele; Argenti, Francesca; Tugnoli, Alessandro; Cozzani, Valerio

2015-01-01

The evolution of domino scenarios triggered by fire critically depends on the presence and the performance of safety barriers that may have the potential to prevent escalation, delaying or avoiding the heat-up of secondary targets. The aim of the present study is the quantitative assessment of safety barrier performance in preventing the escalation of fired domino scenarios. A LOPA (layer of protection analysis) based methodology, aimed at the definition and quantification of safety barrier performance in the prevention of escalation was developed. Data on the more common types of safety barriers were obtained in order to characterize the effectiveness and probability of failure on demand of relevant safety barriers. The methodology was exemplified with a case study. The results obtained define a procedure for the estimation of safety barrier performance in the prevention of fire escalation in domino scenarios. - Highlights: • We developed a methodology for the quantitative assessment of safety barriers. • We focused on safety barriers aimed at preventing domino effect triggered by fire. • We obtained data on effectiveness and availability of the safety barriers. • The methodology was exemplified with a case study of industrial interest. • The results showed the role of safety barriers in preventing fired domino escalation

Evaluating a smartphone application to improve child passenger safety and fire safety knowledge and behaviour.

Science.gov (United States)

Omaki, Elise; Shields, Wendy C; McDonald, Eileen; Aitken, Mary E; Bishai, David; Case, James; Gielen, Andrea

2017-02-01

Although proven measures for reducing injury due to motor vehicle collision and residential fires exist, the number of families properly and consistently using child passenger restraints and smoke alarms remains low. This paper describes the design of the Safety In Seconds (SIS) 2.0 study, which aims to evaluate the impact of a smartphone app on parents' use of child restraints and smoke alarms. SIS is a multisite randomised controlled trial. Participants are parents of children aged 4-7 years who are visiting the Pediatric Emergency Department or Pediatric Trauma Service. Parents are randomised to receive tailored education about child passenger safety or about fire safety via the SIS smartphone app. A baseline and two follow-up surveys at 3 months and 6 months are conducted. Primary outcomes are: (1) having the correct child restraint for the child's age and size; (2) restraining the child in the back seat of the car; (3) buckling the child up for every ride; (4) having the restraint inspected by a child passenger safety technician; (5) having a working smoke alarm on every level of the home; (6) having hard-wired or lithium battery smoke alarms; (7) having and (8) practising a fire escape plan. Finding ways to communicate with parents about child passenger and fire safety continues to be a research priority. This study will contribute to the evidence about how to promote benefits of proper and consistent child restraint and smoke alarm use. NCT02345941; Pre-results. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

Sodium fires and its extinguishment; Gorenie, sredstva i sposoby tusheniya natriya

Energy Technology Data Exchange (ETDEWEB)

Mikhedov, V G

1979-03-01

The fire safety problems of NPP with sodium coolants in USSR are presented. The design of sodium reactors is made with premises with sodium coolants being hermetic and filled with nitrogen. Some engineering solutions of fire safety including design, elaboration and choice of construction and protection materials are presented. Some theoretical aspects of sodium burning are presented as well as methods of sodium fire extinguishing methods including the use of powder.

An Assessment of the Fire Safety Hazard Associated with External Fire Spread in Tall Buildings with Combustible Façade Material

DEFF Research Database (Denmark)

Lavard Brogaard, Nicholas; Torero, Jose L.; Jomaas, Grunde

2014-01-01

in order to obtain a conclusive assessment of the fire safety hazards associated with combustible facades. Prescriptive fire safety codes are typically not allowing any type of combustible façade in buildings that are taller than 2-3 stories. However, a performance based approach does not contain height...

Evaluation of fire probabilistic safety assessment for a PWR plant

International Nuclear Information System (INIS)

Wu, C.H.; Lin, T.J.; Kao, T.M.

2001-01-01

The internal fire analysis of the level 1 power operation probability safety assessment (PSA) for Maanshan (PWR) Nuclear Power Plant (MNPP) was updated. The fire analysis adopted a scenario-based PSA approach to systematically evaluate fire and smoke hazards and their associated risk impact to MNPP. The result shows that the core damage frequency (CDF) due to fire is about six times lower than the previous one analyzed by the Atomic Energy Council (AEC), Republic of China in 1987. The plant model was modified to reflect the impact of human events and recovery actions during fire. Many tabulated EXCEL spread-sheets were used for evaluation of the fire risk. The fire-induced CDF for MNPP is found to be 2.1 E-6 per year in this study. The relative results of the fire analysis will provide the bases for further risk-informed fire protection evaluation in the near future. (author)

14 CFR 23.865 - Fire protection of flight controls, engine mounts, and other flight structure.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fire protection of flight controls, engine... controls, engine mounts, and other flight structure. Flight controls, engine mounts, and other flight... they are capable of withstanding the effects of a fire. Engine vibration isolators must incorporate...

Safety demonstration test on solvent fire in fuel reprocessing plant

International Nuclear Information System (INIS)

Nishio, Gunji; Hashimoto, Kazuichiro

1989-03-01

This report summarizes a fundamental of results obtained in the Reprocessing Plant Safety Demonstration Test Program which was performed under the contract between the Science and Technology Agency of Japan and the Japan Atomic Energy Research Institute. In this test program, a solvent fire was hypothesized, and such data were obtained as fire behavior, smoke behavior and integrity of exhaust filters in the ventilation system. Through the test results, it was confirmed that under the fire condition in hypothetical accident, the integrity of the cell and the cell ventilation system were maintained, and the safety function of the exhaust filters was maintained against the smoke loading. Analytical results by EVENT code agreed well with the present test data on the thermofluid flow in a cell ventilation system. (author)

Action taken by the french safety authorities for fire protection and fire fighting in basic nuclear plants

International Nuclear Information System (INIS)

Savornin, J.; Gibault, M.; Berger, R.; Kaluzny, Y.; Wallard, H.E.; Winter, D.

1989-03-01

The safety goal for nuclear installations is to prevent the dispersal of radioactive substances, both in the work area and outside the buildings into the environment. It is therefore at the design stage, then during construction and subsequent operation that it is necessary to take preventive measures against the outbreak of fire, and to take precautions to ensure that the consequences will always be limited. The paper describes the arrangements made by the French safety authorities to provide protection against fire in both nuclear plants and nuclear fuel cycle installations at all these stages

Preliminary fire hazards analysis for W-211, Initial Tank Retrieval Systems

International Nuclear Information System (INIS)

Huckfeldt, R.A.

1995-01-01

A fire hazards analysis (FHA) was performed for Project W-211, Initial Tank Retrieval System (ITRS), at the Department of Energy (DOE) Hanford site. The objectives of this FHA was to determine (1) the fire hazards that expose the Initial Tank Retrieval System or are inherent in the process, (2) the adequacy of the fire-safety features planned, and (3) the degree of compliance of the project with specific fire safety provisions in DOE orders and related engineering codes and standards. The scope included the construction, the process hazards, building fire protection, and site wide fire protection. The results are presented in terms of the fire hazards present, the potential extent of fire damage, and the impact on employees and public safety. This study evaluated the ITRS with respect to its use at Tank 241-SY-101 only

Protection against internal fires and explosions in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. This Safety Guide supplements the requirements established in Safety of Nuclear Power Plants: Design. It supersedes Safety Series No. 50-SG-D2 (Rev. 1), Fire Protection in Nuclear Power Plants: A Safety Guide, issued in 1992.The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice

Evaluation of the Cable Types for Safety Requirements during Fire Conditions in Nuclear Facility

International Nuclear Information System (INIS)

Al-kattan, W.A.

2015-01-01

In Nuclear Power Plants (NPPs), the fire in cables causes many dangerous events in electrical or mechanical operations causing a nuclear reactor melt down. Main Control Room (MCR) in nuclear power plants have therefore, special concern in the fire protection systems. The Nuclear International Atomic Energy Agency (IAEA) has promoted the use of risk-informed and performance based methods for fire protection. These methods affirm the relevant needs to develop realistic methods to quantify the risk of fire to NPPs safety. The recent electrical cable testing has been carried out to provide empirical data on the failure modes and likelihood of fire-induced damage. In this thesis, will use fire modeling to develop fire probabilistic safety assessment to estimate the likelihood of fire induced cable damage given a specified fire profile. The objective of this work is to provide a comprehensive evaluation of the most recent fire-induced circuit failure due to different cables type that used inside the NPPs by simulation using fire modeling. One of this work scope is to suggest a suitable cable insulation material especially in case of the thermal failure thresholds, for developing the electrical cable thermal fragility distributions and evaluate parameters that influence fire-induced circuit failure modes. The main control room is implementing using the CFAST (fire simulation package). The simulation results represent the full development fire temperature and heat flux as well as the output gases. The results can be used as the basic parameters of the cables comparison and then evaluation.The importance of these results are not only for evaluating the cables but one can efficiently use them to improve the whole NPPs safety levels. The gases results of the fire simulation inside the room are oxygen, carbon monoxide, carbon dioxide, and hydrogen chloride. These gases are being used lot achieving the healthy protection of NPPs. Finally, one can measure the healthy environment

20 CFR 654.417 - Fire, safety, and first aid.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Fire, safety, and first aid. 654.417 Section..., safety, and first aid. (a) All buildings in which people sleep or eat shall be constructed and maintained...-type water extinguisher. (g) First aid facilities shall be provided and readily accessible for use at...

System safety engineering analysis handbook

Science.gov (United States)

Ijams, T. E.

1972-01-01

The basic requirements and guidelines for the preparation of System Safety Engineering Analysis are presented. The philosophy of System Safety and the various analytic methods available to the engineering profession are discussed. A text-book description of each of the methods is included.

Probabilistic assessment of fire hazard: a contribution of power industry to the development of fire protection engineering

International Nuclear Information System (INIS)

Kandrac, J.; Skvarka, P.

1990-01-01

Draft methodology was developed for assessment of fire hazard in nuclear power plants. Named DIMEHORP, the methodology is based on fire hazard analyses and on the analyses of the possible ways of fire propagation and of the power plant systems. The former includes determining the spaces of the power plant in which a fire can arise. Fire propagation analysis deals with the probability that within a given section the fire will propagate and cause damage to the equipment before it is localized. The mathematical model used is based on probability theory in conjunction with expert estimates. The methodology was applied to the assessment of the effect of fire in the cable rooms of the Dukovany nuclear power plant on the safety and reliability of its operation. (Z.M.). 3 tabs., 6 refs

Lessons learned from IAEA fire safety missions

International Nuclear Information System (INIS)

Lee, S.P.

1998-01-01

The IAEA has conducted expert missions to evaluate fire safety at the following nuclear power plants: the Zaporozhe plant in the Ukraine, the Borselle plant in the Netherlands, the Medzamor plant in Armenia, the Karachi plant in Pakistan, the Temelin plant in the Czech Republic, and the Laguna Verde plant in Mexico. The scope of these missions varied in subject and depth. The teams sent from the IAEA consisted of external fire experts and IAEA staff. All the missions were of great use to the host countries. The participating experts also benefited significantly. A summary of the missions and their findings is given. (author)

Fire Safety During the Holiday Season | Poster

Science.gov (United States)

Winter is here, and that means holiday decorations, a warm hearth, and (hopefully) plenty of homecooked meals. Unfortunately, winter also brings numerous fire hazards both at work and around the house. This year, as you shop, decorate, and celebrate, keep these safety tips in mind to ensure a safe and enjoyable holiday season.

Fire safety case study of a railway tunnel: Smoke evacuation

Directory of Open Access Journals (Sweden)

van Maele Karim

2007-01-01

Full Text Available When a fire occurs in a tunnel, it is of great importance to assure the safety of the occupants of the tunnel. This is achieved by creating smoke-free spaces in the tunnel through control of the smoke gases. In this paper, results are presented of a study concerning the fire safety in a real scale railway tunnel test case. Numerical simulations are performed in order to examine the possibility of natural ventilation of smoke in inclined tunnels. Several aspects are taken into account: the length of the simulated tunnel section, the slope of the tunnel and the possible effects of external wind at one portal of the tunnel. The Fire Dynamics Simulator of the National Institute of Standards and Technology, USA, is applied to perform the simulations. The simulations show that for the local behavior of the smoke during the early stages of the fire, the slope of the tunnel is of little importance. Secondly, the results show that external wind and/or pressure conditions have a large effect on the smoke gases inside the tunnel. Finally, some idea for the value of the critical ventilation velocity is given. The study also shows that computational fluid dynamics calculations are a valuable tool for large scale, real life complex fire cases. .

Development and validation of a physics-based urban fire spread model

OpenAIRE

HIMOTO, Keisuke; TANAKA, Takeyoshi

2008-01-01

A computational model for fire spread in a densely built urban area is developed. The model is distinct from existing models in that it explicitly describes fire spread phenomena with physics-based knowledge achieved in the field of fire safety engineering. In the model, urban fire is interpreted as an ensemble of multiple building fires; that is, the fire spread is simulated by predicting behaviors of individual building fires under the thermal influence of neighboring building fires. Adopte...

Fire hazard analysis for fusion energy experiments

International Nuclear Information System (INIS)

Alvares, N.J.; Hasegawa, H.K.

1979-01-01

The 2XIIB mirror fusion facility at Lawrence Livermore Laboratory (LLL) was used to evaluate the fire safety of state-of-the-art fusion energy experiments. The primary objective of this evaluation was to ensure the parallel development of fire safety and fusion energy technology. Through fault-tree analysis, we obtained a detailed engineering description of the 2XIIB fire protection system. This information helped us establish an optimum level of fire protection for experimental fusion energy facilities as well as evaluate the level of protection provided by various systems. Concurrently, we analyzed the fire hazard inherent to the facility using techniques that relate the probability of ignition to the flame spread and heat-release potential of construction materials, electrical and thermal insulations, and dielectric fluids. A comparison of the results of both analyses revealed that the existing fire protection system should be modified to accommodate the range of fire hazards inherent to the 2XIIB facility

Nuclear insurance fire risk

International Nuclear Information System (INIS)

Dressler, E.G.

2001-01-01

Nuclear facilities operate under the constant risk that radioactive materials could be accidentally released off-site and cause injuries to people or damages to the property of others. Management of this nuclear risk, therefore, is very important to nuclear operators, financial stakeholders and the general public. Operators of these facilities normally retain a portion of this risk and transfer the remainder to others through an insurance mechanism. Since the nuclear loss exposure could be very high, insurers usually assess their risk first-hand by sending insurance engineers to conduct a nuclear insurance inspection. Because a serious fire can greatly increase the probability of an off-site release of radiation, fire safety should be included in the nuclear insurance inspection. This paper reviews essential elements of a facility's fire safety program as a key factor in underwriting nuclear third-party liability insurance. (author)

Numerical simulation methods of fires in nuclear power plants

International Nuclear Information System (INIS)

Keski-Rahkonen, O.; Bjoerkman, J.; Heikkilae, L.

1992-01-01

Fire is a significant hazard to the safety of nuclear power plants (NPP). Fire may be serious accident as such, but even small fire at a critical point in a NPP may cause an accident much more serious than fire itself. According to risk assessments a fire may be an initial cause or a contributing factor in a large part of reactor accidents. At the Fire Technology and the the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) fire safety research for NPPs has been carried out in a large extent since 1985. During years 1988-92 a project Advanced Numerical Modelling in Nuclear Power Plants (PALOME) was carried out. In the project the level of numerical modelling for fire research in Finland was improved by acquiring, preparing for use and developing numerical fire simulation programs. Large scale test data of the German experimental program (PHDR Sicherheitsprogramm in Kernforschungscentral Karlsruhe) has been as reference. The large scale tests were simulated by numerical codes and results were compared to calculations carried out by others. Scientific interaction with outstanding foreign laboratories and scientists has been an important part of the project. This report describes the work of PALOME-project carried out at the Fire Technology Laboratory only. A report on the work at the Nuclear Engineering Laboratory will be published separatively. (au)

Fire hazards evaluation for light duty utility arm system

International Nuclear Information System (INIS)

HUCKFELDT, R.A.

1999-01-01

In accordance with DOE Order 5480.7A, Fire Protection, a Fire Hazards Analysis must be performed for all new facilities. LMHC Fire Protection has reviewed and approved the significant documentation leading up to the LDUA operation. This includes, but is not limited to, development criteria and drawings, Engineering Task Plan, Quality Assurance Program Plan, and Safety Program Plan. LMHC has provided an appropriate level of fire protection for this activity as documented

Fire probability safety analysis in France for 900 MWe nuclear power plants

International Nuclear Information System (INIS)

Bertrand, R.; Bonneval, F.; Mattei, J.M.

2000-01-01

This paper describes the methodology implemented by the Institute for Nuclear Safety and Protection (IPSN) to carry out the Fire Probabilistic Safety Assessment (Fire PSA) for French 900 MWe pressurised water reactors. The initial results obtained are presented. Additional research and development activities are indicated which IPSN carried out or decided to perform in order to reduce the amount of uncertainty associated with the data or to confirm hypotheses that can impact significantly the study results. (orig.) [de

Failure modes of safety-related components at fires on nuclear power plants

International Nuclear Information System (INIS)

Aaslund, A.

2000-03-01

Probabilistic assessment methods can be used to identify specific plant vulnerabilities. Application of such methods can also facilitate selection among system design alternatives available for safety enhancements. The quality of assessment results is however strongly dependent on realistic and accurate input data for modelling of system component behaviour and failure modes during conditions to be assessed. Use of conservative input data may not lead to results providing guidance on safety upgrades. Adequate input data for probabilistic assessments seems to be lacking for at least failure modes of some electrical components when exposed to a fire. This report presents an attempt to improve the situation with respect to such input data. In order to take advantage of information in existing documentation of fire incident occurrences some of the lessons learned from the fire at Browns Ferry Nuclear Power Plant on March 22, 1975 are discussed in this report. Also a summary of results from different fire tests of electrical cables presented in a fire risk analysis report is a part of the references. The failure modes used to describe fire-induced damage are 'open circuit' and 'hot short' which seems to be commonly accepted terms within the branch. Definitions of the terms are included in the report. Effects of the failure modes when occurring in some of the channels of the reactor protection system are discussed with respect to the existing design of the reactor protection system at Ringhals 2 nuclear power unit. Experiences from the Browns Ferry fire and results from fire tests of electrical cables indicate that the dominating failure mode for electrical cables is 'open circuit'. An 'open circuit' failure leads to circuit disjunction and loss of continuity. The circuit can no longer transmit its signal or power. When affecting channels of the reactor protection system an 'open circuit' failure can cause extensive inadvertent actions of safety related equipment

Idaho National Engineering and Environmental Laboratory Wildland Fire Management Environmental Assessment - April 2003

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

2003-04-30

DOE prepared an environmental assessment (EA)for wildland fire management activities on the Idaho National Engineering and Environmental Laboratory (INEEL) (DOE/EA-1372). The EA was developed to evaluate wildland fire management options for pre-fire, fire suppression, and post fire activities. Those activities have an important role in minimizing the conversion of the native sagebrush steppe ecosystem found on the INEEL to non-native weeds. Four alternative management approaches were analyzed: Alternative 1 - maximum fire protection; Alternative 2 - balanced fire protection; Alternative 2 - balanced fire protection; Alternative 3 - protect infrastructure and personnel; and Alternative 4 - no action/traditional fire protection.

FIRE

International Nuclear Information System (INIS)

Brtis, J.S.; Hausheer, T.G.

1990-01-01

FIRE, a microcomputer based program to assist engineers in reviewing and documenting the fire protection impact of design changes has been developed. Acting as an electronic consultant, FIRE is designed to work with an experienced nuclear system engineer, who may not have any detailed fire protection expertise. FIRE helps the engineer to decide if a modification might adversely affect the fire protection design of the station. Since its first development, FIRE has been customized to reflect the fire protection philosophy of the Commonwealth Edison Company. That program is in early production use. This paper discusses the FIRE program in light of its being a useful application of expert system technologies in the power industry

Statistical assessment of fire safety in multi-residential buildings in Slovenia

Directory of Open Access Journals (Sweden)

Domen Kušar

2009-01-01

Full Text Available Nearly a third of residential units in Slovenia are located in multi-residential buildings. The majority of such buildings were built after WW2, when the need for suitable accommodation buildings was at its peak. They were built using the construction possibilities and requirements of the time. Every year there are over 200 fires in these buildings, resulting in fatalities and vast material damage. Due to the great efforts over the past centuries, which were all mainly aimed at replacing combustible construction materials with non-combustible ones, and with advancements in fire service equipment and techniques, the number of fires and their scope has decreased significantly but they were not entirely put out. New and greater advances in the field of fire safety of multi-residential buildings became obvious within the last few years, when stricter regulations regarding the construction of such objects came into force. Developments in science and within the industry itself brought about several new solutions in improving the situation in this field, which has been confirmed by experiences from abroad. Unfortunately in Slovenia, the establishment of safety principles still depends mainly on an occupants’ perception, financial means, and at the same time, certain implementation procedures that are much more complicated due to new property ownership. With the aid of the statistical results from the 2002 Census and contemporary fire safety requirements, this article attempts to show the present-day situation of the problem at both the state and municipality level and will propose solutions to improve this situation. The authors established that not even one single older, multi-residential building meets complies with modern requirements. Fortunately, the situation is improved by the fact that most buildings in Slovenia are built from non-combustible materials (concrete, brick, which limit the spread of fire.

48 CFR 2052.235-71 - Safety, health, and fire protection.

Science.gov (United States)

2010-10-01

... extension of time or for compensation or damages by reason of, or in connection with, this type of work... performance of the work under this contract to protect the health and safety of its employees and of members... hazards to life and property. The contractor shall comply with all applicable health, safety, and fire...

Firefighters United for Safety, Ethics, and Ecology (FUSEE): Torchbearers for a new fire management paradigm

Science.gov (United States)

Timothy Ingalsbee; Joseph Fox; Patrick Withen

2007-01-01

Firefighters United for Safety, Ethics, and Ecology (FUSEE) is a nonprofit organization promoting safe, ethical, ecological wildland fire management. FUSEE believes firefighter and community safety are ultimately interdependent with ethical public service, wildlands protection, and ecological restoration of fire-adapted ecosystems. Our members include current, former,...

Study of methodology for low power/shutdown fire PSA

International Nuclear Information System (INIS)

Yan Zhen; Li Zhaohua; Li Lin; Song Lei

2014-01-01

As a risk assessment technology based on probability, the fire PSA is accepted abroad by nuclear industry in its application in the risk assessment for nuclear power plants. Based on the industry experience, the fire-induced impact on the plant safety during low power and shutdown operation cannot be neglected, therefore fire PSA can be used to assess the corresponding fire risk. However, there is no corresponding domestic guidance/standard as well as accepted analysis methodology up to date. Through investigating the latest evolvement on fire PSA during low power and shutdown operation, and integrating its characteristic with the corresponding engineering experience, an engineering methodology to evaluate the fire risk during low power and shutdown operation for nuclear power plant is established in this paper. In addition, an analysis demonstration as an example is given. (authors)

Tech assist/fire safety assessment of 100K area facilities

International Nuclear Information System (INIS)

Johnson, B.H.

1994-01-01

This Tech Assist/Fire Safety Assessment provides a comprehensive assessment of the 100K Area Facilities at the U.S. Department of Energy's Hanford Site for fire protection upgrades that may be needed given the limited remaining service life of these facilities. This assessment considers the relative nature of observed fire risks and whether the installed fire protection systems adequately control this risk. The analysis is based on compliance with DOE Orders, NFPA Codes and Standards, and recognized industry practice. Limited remaining service life (i.e., 6 to 12 years), current value of each facility, comparison to the best protected class of industrial risk, and the potential for exemptions from DOE requirements are key factors for recommendations presented in this report

Construction products performances and basic requirements for fire safety of facades in energy rehabilitation of buildings

Directory of Open Access Journals (Sweden)

Laban Mirjana Đ.

2015-01-01

Full Text Available Construction product means any product or kit which is produced and placed on the market for incorporation in a permanent manner in construction works, or parts thereof, and the performance of which has an effect on the performance of the construction works with respect to the basic requirements for construction works. Safety in case of fire and Energy economy and heat retention represent two among seven basic requirements which building has to meet according to contemporary technical rules on planning and construction. Performances of external walls building materials (particularly reaction to fire could significantly affect to fire spread on the façade and other building parts. Therefore, façade shaping and materialization in building renewal process, has to meet the fire safety requirement, as well as the energy requirement. Brief survey of fire protection regulations development in Serbia is presented in the paper. Preventive measures for fire risk reduction in building façade energy renewal are proposed according to contemporary fire safety requirements.

Reported fire safety and first-aid amenities in Airbnb venues in 16 American cities.

Science.gov (United States)

Kennedy, Hudson R; Jones, Vanya C; Gielen, Andrea

2018-05-07

Airbnb helps hosts rent all or part of their home to guests as an alternative to traditional hospitality settings. Airbnb venues are not uniformly regulated across the USA. This study quantified the reported prevalence of fire safety and first-aid amenities in Airbnb venues in the USA. The sample includes 120 691 venues in 16 US cities. Proportions of host-reported smoke and carbon monoxide (CO) detectors, fire extinguishers and first-aid kits were calculated. The proportion of venues that reportedly contained amenities are as follows: smoke detectors 80% (n=96 087), CO detectors 57.5% (n=69 346), fire extinguishers 42% (n=50 884) and first-aid kits 36% (n=43 497). Among this sample of Airbnb venues, safety deficiencies were noted. While most venues had smoke alarms, approximately 1/2 had CO alarms and less than 1/2 reported having a fire extinguishers or first-aid kits. Local and state governments or Airbnb must implement regulations compliant with current National Fire Protection Association fire safety standards. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

A safety evaluation of fire and explosion in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Nishio, Gunji; Takada, Junichi; Tukamoto, Michio; Watanabe, Kouji; Miyata, Teijirou

1996-01-01

The demonstration test was performed in JAERI to prove the adequacy of a safety evaluation for an air-ventilation system in the case of solvent fire and red-oil explosion in a nuclear fuel reprocessing plant. The test objectives were to obtain data of the safety evaluation on a thermofluid behavior and a confinement effect of radioactive materials during fire and explosion while the system is operating in a cell. The computer code was developed to evaluate the safety of associated network in the ventilation system and to estimate the confinement of radioactive materials in the system. The code was verified by comparison of code calculations with results of the demonstration test. (author)

Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

International Nuclear Information System (INIS)

Lambright, J.A.; Cerjak, J.; Spiler, J.; Ioannidi, J.

1998-01-01

Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

Liquid metals fire control engineering handbook

International Nuclear Information System (INIS)

Ballif, J.L.

1979-02-01

This handbook reviews the basic requirements of the use of liquid metals with emphasis on sodium which has the greatest current usage. It delineates the concepts necessary to design facilities both radioactive and nonradioactive for use with liquid metals. It further reviews the state-of-the-art in fire extinguishers and leak detection equipment and comments on their application and sensitivity. It also provides details on some engineering features of value to the designer of liquid metal facilities

An evaluation of The Great Escape: can an interactive computer game improve young children's fire safety knowledge and behaviors?

Science.gov (United States)

Morrongiello, Barbara A; Schwebel, David C; Bell, Melissa; Stewart, Julia; Davis, Aaron L

2012-07-01

Fire is a leading cause of unintentional injury and, although young children are at particularly increased risk, there are very few evidence-based resources available to teach them fire safety knowledge and behaviors. Using a pre-post randomized design, the current study evaluated the effectiveness of a computer game (The Great Escape) for teaching fire safety information to young children (3.5-6 years). Using behavioral enactment procedures, children's knowledge and behaviors related to fire safety were compared to a control group of children before and after receiving the intervention. The results indicated significant improvements in knowledge and fire safety behaviors in the intervention group but not the control. Using computer games can be an effective way to promote young children's understanding of safety and how to react in different hazardous situations.

Wildland fire management. Volume 1: Prevention methods and analysis. [systems engineering approach to California fire problems

Science.gov (United States)

Weissenberger, S. (Editor)

1973-01-01

A systems engineering approach is reported for the problem of reducing the number and severity of California's wildlife fires. Prevention methodologies are reviewed and cost benefit models are developed for making preignition decisions.

Nuclear electric power safety, operation, and control aspects

CERN Document Server

Knowles, J Brian

2013-01-01

Assesses the engineering of renewable sources for commercial power generation and discusses the safety, operation, and control aspects of nuclear electric power From an expert who advised the European Commission and UK government in the aftermath of Three Mile Island and Chernobyl comes a book that contains experienced engineering assessments of the options for replacing the existing, aged, fossil-fired power stations with renewable, gas-fired, or nuclear plants. From geothermal, solar, and wind to tidal and hydro generation, Nuclear Electric Power: Safety, Operation, and Control Aspects ass

Sodium fire studies in France. Safety experiments applied to fast reactors

International Nuclear Information System (INIS)

Fruchard, Y.; Colome, J.; Malet, J.C.; Berlin, M.; Duverger de Cuy, G.; Justin, J.; Duco, J.

1976-01-01

In fast reactors, the risk of sodium fires must be analyzed in detail and the consequences of an accidental fire must be known precisely. Beyond the search for prevention and detection means, techniques must be developed to set up a limit to damages created by an accidental fire: extinguishing, aerosol confinement, protection of the reactor structures. The program developed by the Nuclear Safety Department of the Commissariat a l'Energie Atomique to solve these various problems is described. The main results and their applications to the Super-Phenix reactor are presented [fr

Can fire safety in hotels be improved? Results from the survey of a panel of experts in Spain.

Science.gov (United States)

Rubio-Romero, Juan Carlos; Márquez-Sierra, Francisco; Suárez-Cebador, Manuel

2016-06-08

The hotel industry is an important driver of the European labour market with over 250,000 hotels employing some 2 million people. In Spain, 240 workers were injured by fires in hotels from 2004 to 2008. Fire is considered to be the most important risk in the hotel industry, but the lack of an EU-wide data recording system for hotels makes it difficult to give exact figures for fire events. We analysed the state of fire prevention systems in hotels in Spain with the aim of proposing strategies to improve fire safety. A 10-item questionnaire was administered from 2007 to 2009 to 15 Spanish experts in fire safety. The questions were measured using a Likert scale and classified into 4 sections: current state of installations, influence of establishment characteristics, application of regulations and priority ranking of actions. Descriptive statistics summarized the data and t-tests evaluated the agreement foreach statement in the questionnaire. The statistical analysis showed homogeneity in the responses by the experts in all four categories: current state of fire safety installations, influence of establishment characteristics, application of regulations, and priority of actions. There was consensus among the experts over the necessity to improve the enforcement of regulations and also regarding the existence of an association between the hotel category (in Spain they are ranked using a 1 to 5 "star" rating system) and the level of fire safety; hotels with a higher category had higher levels of safety. There is a need to identify ways to apply fire safety standards to older hotels so that they comply with new regulations, to standardize regulations for different regions and countries, to improve the maintenance of installations and equipment, to increase the effectiveness of inspections conducted by government bodies, and to raise the general awareness of stakeholders involved in hotel fire prevention.

Evaluation of safety margin of packaging for radioactive materials transport during a severe fire

International Nuclear Information System (INIS)

Gilles, P.; Ringot, C.; Warniez, P.; Grall, L.; Perrot, J.

1986-06-01

A high safety is obtained by International regulations on radioactive materials transport. It is obtained by packaging design adapted to the potential risk. An important accident to consider is fire for two reasons: the probability of fire occuring for time and temperature higher than conditions applied to type B packaging (800 deg C, 1/2 hr) is not negligible, particularly for air or maritime transport. Safety margins are studied by computation and experimental tests. This report presents results obtained for different types of packagings. Results show a large safety margin [fr

46. The goals of safety engineering department of the plant

International Nuclear Information System (INIS)

Ivanov, A.V.

1993-01-01

The goals of safety engineering department of the plant, including elaboration of instructions on safety engineering on all specialities, safety engineering training of all labours working on the plant and control for abidance by the instructions on safety engineering were discussed.

Fire safety requirements for electric cables and lines in deep coal mines

Energy Technology Data Exchange (ETDEWEB)

Herms, C D

1982-01-07

In the case of a mine fire, an additional hazard from combustible cable material is likely to arise only in those few areas of the mine where special circumstances might help the fire to spread along the cables. It is more important to preserve the functional integrity of cables in the outbye roads which are affected by fire gases then at the actual seat of the fire. Mine cables with better fire-resistant properties should be made from materials which do not propagate fires, do not release burning drops, develop the lowest possible fume density and/or will permanently resist gas temperatures of 200 to 300/sup 0/C. Fire test specifications should be defined for such special cables, based on corresponding draft VDE directives. In proposing these measures the proviso is made then improvement in safety can be clearly demonstrated.

Parametric study for the fire safety design of steel structures

DEFF Research Database (Denmark)

Aiuti, Riccardo; Giuliani, Luisa

2013-01-01

the considered time of fire exposure. A deeper knowledge on the failure mode of steel structure is however important in order to ensure the safety of the people and properties outside the building. Aim of this paper is to analyze the behaviour of single elements, sub-assemblies and frames exposed to fire...... or hindered thermal expansion induced on the element by the rest of the structure. Nevertheless, restrained thermal expansion is known to significantly affect the behaviour of steel structures in fire, and the compliance with a prescribed resistance class doesn’t ensure the integrity of the building after...... and find out the basic collapse mechanisms of structural elements in fire conditions, considering the rest of the construction with appropriate constraints. The analysis is carried out taking into account material and geometrical nonlinearities as well as the degradation of steel properties at high...

Engineering Status of the Fusion Ignition Research Experiment (FIRE)

International Nuclear Information System (INIS)

Heitzenroeder, Philip J.; Meade, Dale; Thome, Richard J.

2000-01-01

FIRE is a compact, high field tokamak being studied as an option for the next step in the US magnetic fusion energy program. FIRE's programmatic mission is to attain, explore, understand, and optimize alpha-dominated plasmas to provide the knowledge necessary for the design of attractive magnetic fusion energy systems. This study began in 1999 with broad participation of the US fusion community, including several industrial participants. The design under development has a major radius of 2 m, a minor radius of 0.525 m, a field on axis of 10T and capability to operate at 12T with upgrades to power supplies. Toroidal and poloidal field magnets are inertially cooled with liquid nitrogen. An important goal for FIRE is a total project cost in the $1B range. This paper presents an overview of the engineering details which were developed during the FIRE preconceptual design study in FY99 and 00

Space transportation main engine reliability and safety

Science.gov (United States)

Monk, Jan C.

1991-01-01

Viewgraphs are used to illustrate the reliability engineering and aerospace safety of the Space Transportation Main Engine (STME). A technology developed is called Total Quality Management (TQM). The goal is to develop a robust design. Reducing process variability produces a product with improved reliability and safety. Some engine system design characteristics are identified which improves reliability.

Forum for fire protection and safety in power plants[Norway

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The conference contains 16 presentations on topics in the fields of fire protection and safety in plants in Western Norway, reorganization and reconstruction of power systems and plants in Norway, various aspects of risk and vulnerability analysis, technological aspects of plant management and construction and problems and risks with particularly transformers. Some views on challenges of the fire departments and the new Norwegian regulations for electrical power supply systems are included. One presentation deals with challenges for Icelandic power production plants.

The assessment of fire safety of cast iron structures in historical buildings: Theory and practice

NARCIS (Netherlands)

Twilt, L.; Hunen, M. van

2000-01-01

The assessment of structural fire safety of cast iron structures in historical buildings is difficult because the available information on the fire behaviour is limited, whilst the fire design assumptions (if any) often are not well docu-mented. A complicating factor with regard to protective

Reference to the Safety Engineering Undergraduate Courses to Improve the Subjects and Contents of the Certified Safety Engineer Qualification and Examination System of China

OpenAIRE

Haibin Qiu; Shanghong Shi; Tingdi Zhao; Yiwei Qiao; Jiangshi Zhang

2013-01-01

The aim of this paper is to recommend that the subjects and contents of certified safety engineers use safety engineering undergraduate curriculum system for reference. Human resources play an important role in accident prevention and loss control. Education on safety engineering develops quickly in China. Moreover, the State Administration of Work Safety and the National Human Resources and Social Security Ministry have implemented a certified safety engineer qualification and examination sy...

Fire Safety Aspects of Polymeric Materials. Volume 2. Test Methods, Specifications and Standards

Science.gov (United States)

1979-01-01

Chairman: Dr. Seymour L. Blum Vice President Northern Energy Corporation 70 Memorial Drive Cambridge, MA 02142 Dr. George S. Ansell Dean, School...limitations, is perhaps the most firmly grounded and thoroughly docu- mented of any in the fire safety field (Benjamin and Adams , 1976). Having established...of the largest fire experiments ever undertaken. Operation Euroka, a 50 acre wildland fuel fire in Australia ( Adams et al., 1973). Scaling and

Evaluation of Generic Issue 57: Effects of fire protection system actuation on safety-related equipment

International Nuclear Information System (INIS)

Lambright, J.; Bohn, M.; Lynch, J.; Ross, S.; Brosseau, D.

1992-12-01

Nuclear power plants have experienced actuations of fire protection systems (FPSs) under conditions for which these systems were not intended to actuate and also have experienced advertent actuations with the presence of a fire. These actuations have often damaged safety-related equipment. A review of the impact of past occurrences of both types of such events and their impact on plant safety systems, an analysis of the risk impacts of such events on nuclear power plant safety, and a cost-benefit analysis of potential corrective measures have been performed. Thirteen different scenarios leading to actuation of fire protection systems due to a variety of causes were identified. These scenarios ranged from inadvertent actuation caused by human error to hardware failure, and include seismic root causes and seismic/fire interactions. A quantification of these thirteen root causes, where applicable, was performed on generically applicable scenarios. This document, Volume 4, contains appendices E and F of this report

View of the firing of a single engine OMS

Science.gov (United States)

1985-01-01

View of a single engine orbital maneuvering system (OMS) firing on the Discovery. The payload bay is open and the protective canisters for the AUSSAT communications satellite (open) and the ASC-1 are visible. A cloudy Earth's horizon can be seen above the orbiter.

Report of the international fire safety mission to Temelin, unit 1 nuclear power plant Czech Republic 4 to 14 February 1996

International Nuclear Information System (INIS)

1996-01-01

This report presents the results of an IAEA Fire Safety Mission conducted within the scope of Technical Co-operation Project CZR/9/005 to assess the licensing process, design, analysis and operational management of the Temelin Nuclear Power Plant with regards to fire safety of the plant. The Temelin Nuclear Power Plant currently has two units under construction. Each unit is equipped with a pressurized water reactor of the WWER design with a net electrical output of about MWe. The plant has already made significant upgrading in fire protection from the original design. The Team's evaluation is based on the IAEA Safety Series No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, and other fire protection guidelines currently produced by the IAEA. The evaluation, conclusions and recommendations presented in this report reflect the views of the Fire Safety Mission experts. The recommendations are provided for consideration by the responsible authorities in the Czech Republic towards enhancing fire safety at the Temelin plant

Health and safety manual

International Nuclear Information System (INIS)

1980-02-01

The manual consists of the following chapters: general policies and administration; the Environmental Health and Safety Department; the Medical Services Department: biological hazards; chemical safety; confined space entry; cryogenic safety; electrical safety; emergency plans; engineering and construction; evacuations, trenching, and shoring; fire safety; gases, flammable and compressed; guarding, mechanical; ladders and scaffolds, work surfaces; laser safety; materials handling and storage; noise; personal protective equipment; pressure safety; radiation safety, ionizing and non-ionizing; sanitation; seismic safety; training, environmental health and safety; tools, power and hand-operated; traffic and transportation; and warning signs and devices

Sodium fire studies in France safety tests and applications on an LMFBR

International Nuclear Information System (INIS)

Fruchard, Y.; Colome, J.; Malet, J.C.; Berlin, M.; de Cuy, G.D.; Justin, J.; Duco, J.; Fourest, B.

1976-01-01

The risk of sodium fires in an LMFBR requires thorough analysis, and the possible consequences of an accidental fire must be accurately determined. Not only must means of prevention and detection be perfected, but techniques must be developed to limit the damage caused by a fire: extinguishment, aerosol containment, protection of reactor structures. The program currently undertaken by the CEA's Nuclear Safety Department covering these problems is described. The major results obtained as well as their application to the SUPER-PHENIX reactor are included

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Neupauer, R.M.; Thurmond, S.M.

1992-09-01

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Neupauer, R.M.; Thurmond, S.M.

1992-09-01

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

Fire barrier penetration seals in nuclear power plants

International Nuclear Information System (INIS)

Bajwa, C.S.; West, K.S.

1996-07-01

NNPs are divided into separated fire areas by fire-rated structural barriers. Fire-rated penetration seals are installed to seal certain openings in these barriers, in order to provide reasonable assurance that a fire will be confined to the area where it started. The staff of the Fire Protection Engineering Section, Office of Nuclear Reactor Regulation, US NRC, conducted a comprehensive technical assessment of penetration seals to address reports of potential problems, to determine if there were any problems of safety significance, and to determine if NRC requirements, review guidance, and inspection procedures are adequate. It was concluded that the general condition of penetration seal programs in industry is satisfactory, and that the actions taken in 1988 and 1994 had increased industry awareness of potential problems and resulted in more thorough surveillances, maintenance, and corrective actions. These previous staff actions, together with continued licensee upkeep of existing penetration seal programs and continued NRC inspections, are adequate to maintain public health and safety. Several minor revisions to the NRC fire protection regulation and review guidance are recommended

Spacecraft Fire Safety 1956 to 1999: An Annotated Bibliography

Science.gov (United States)

Friedman, Robert; Ruff, Gary A.

2013-01-01

Knowledge of fire safety in spacecraft has resulted from over 50 years of investigation and experience in space flight. Current practices and procedures for the operation of the Space Transportation System (STS) shuttle and the International Space Station (ISS) have been developed from this expertise, much of which has been documented in various reports. Extending manned space exploration from low Earth orbit to lunar or Martian habitats and beyond will require continued research in microgravity combustion and fire protection in low gravity. This descriptive bibliography has been produced to document and summarize significant work in the area of spacecraft fire safety that was published between 1956 and July 1999. Although some important work published in the late 1990s may be missing, these citations as well as work since 2000 can generally be found in Web-based resources that are easily accessed and searched. In addition to the citation, each reference includes a short description of the contents and conclusions of the article. The bibliography contains over 800 citations that are cross-referenced both by topic and the authors and editors. There is a DVD that accompanies this bibliography (available by request from the Center for Aerospace Information) containing the full-text articles of selected citations as well as an electronic version of this report that has these citations as active links to their corresponding full-text article.

Curriculum: Integrating Health and Safety Into Engineering Curricula.

Science.gov (United States)

Talty, John T.

1985-01-01

National Institute for Occupational Safety and Health instituted a project in 1980 to encourage engineering educators to focus on occupational safety and health issues in engineering curricula. Progress to date is outlined, considering specific results in curriculum development, engineering society interaction, and formation of a teaching…

75 FR 44720 - Safety Zone; Live-Fire Gun Exercise, M/V Del Monte, James River, VA

Science.gov (United States)

2010-07-29

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Part 165 [Docket No. USCG-2010-0585] RIN 1625-AA00 Safety Zone; Live-Fire Gun Exercise, M/V Del Monte, James River, VA AGENCY: Coast Guard, DHS... follows: Sec. 165.T05-0585 Safety Zone; Live-Fire Gun Exercise, M/V Del Monte, James River, VA (a...

Fire safety at home

Science.gov (United States)

... over the smoke alarm as needed. Using a fire extinguisher can put out a small fire to keep it from getting out of control. Tips for use include: Keep fire extinguishers in handy locations, at least one on ...

Evaluation of Fire Hazard and Safety Management of Heritage Buildings in Georgetown, Penang

Directory of Open Access Journals (Sweden)

Othuman Mydin M.A.

2014-03-01

Full Text Available Fire is a subject that is always neglected and ignored as far as heritage buildings are concerned. Unlike newly-built buildings, which are required under UBBL to undergo certain fire protection system tests, people are less likely to carry out such tests and detailed assessments for heritage buildings. Thus, this research is significant as it is aimed at accomplishing several objectives including studying the current fire emergency plan, besides identifying and assessing the possible fire hazards in heritage buildings in Penang. Several case studies were carried out at a few premises such as the Khoo Kongsi, Cheah Kongsi, Hock Teik Chen Shin Temple and the Teochew Temple with the aid of the Fire Rescue Department Malaysia (FRDM. The results obtained from this study will be discussed according to several aspects focusing on general health and safety management at the site, the fire-fighting system, fire exit routes and signage at the temples, fire hazards, and fire detection and alarm.

Fire hazard analysis for Plutonium Finishing Plant complex

International Nuclear Information System (INIS)

MCKINNIS, D.L.

1999-01-01

A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements are addressed in terms of the fire protection objectives stated in paragraph 4 of DOE 5480.7A. In addition, the FHA also complies with WHC-CM-4-41, Fire Protection Program Manual, Section 3.4 [1994] and WHC-SD-GN-FHA-30001, Rev. 0 [WHC, 1994]. Objectives of the FHA are to determine: (1) the fire hazards that expose the PFP facilities, or that are inherent in the building operations, (2) the adequacy of the fire safety features currently located in the PFP Complex, and (3) the degree of compliance of the facility with specific fire safety provisions in DOE orders, related engineering codes, and standards

Safety assessment of indoor live fire range, May 1989

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-05-01

The following Safety Assessment (SA) pertains to the indoor live fire range (LFR) at EG&G Mound Applied Technology plant. The purpose of the indoor LFR is to conduct training with live ammunition for all designated personnel. The SA examines the risks that are attendant to the operation of an indoor LFR for this purpose.

Unified Facilities Criteria (UFC) Design: Fire Protection Engineering for Facilities

Science.gov (United States)

2003-08-20

following provisions: • Ceiling sprinkler design area must be increased by 10 percent. ESFR sprinklers must increase the required number to be...Control System ESFR Early Suppression Fast-Response Sprinklers ETL Engineering Technical Letters FAAA Fire Administration Authorization Act FM

Course in fire protection training for nuclear power plant personnel

International Nuclear Information System (INIS)

Walker, K.L.; Bates, E.F.; Randall, J.D.

1979-01-01

Proposed Regulatory Guide 1.120, entitled ''Fire Protection Guidelines for Nuclear Power Plants,'' provides detailed requirements for the overall fire protection programs at nuclear power plant sites in the United States. An essential element in such a program in the training of plant fire brigade personnel is the use of proper firefighting techniques and equipment. The Texas A and M University Nuclear Science Center (NSC) in conjunction with the Fire Protection Training Division of the Texas Engineering Extension Service has developed a one-week course to meet this training need. The program emphasizes hands-on exercises. The course is designed for up to 18 students with all protective clothing provided. Fire instructors are certified by the State of Texas, and registered nuclear engineers and certified health physicists supervise the radiological safety exercises. The first course was conducted during the week of January 8--12, 1979

Fire safety analysis: methodology

International Nuclear Information System (INIS)

Kazarians, M.

1998-01-01

From a review of the fires that have occurred in nuclear power plants and the results of fire risk studies that have been completed over the last 17 years, we can conclude that internal fires in nuclear power plants can be an important contributor to plant risk. Methods and data are available to quantify the fire risk. These methods and data have been subjected to a series of reviews and detailed scrutiny and have been applied to a large number of plants. There is no doubt that we do not know everything about fire and its impact on a nuclear power plants. However, this lack of knowledge or uncertainty can be quantified and can be used in the decision making process. In other words, the methods entail uncertainties and limitations that are not insurmountable and there is little or no basis for the results of a fire risk analysis fail to support a decision process

40 CFR Table 6 to Subpart IIIi of... - Optional 3-Mode Test Cycle for Stationary Fire Pump Engines

Science.gov (United States)

2010-07-01

... Engines [As stated in § 60.4210(g), manufacturers of fire pump engines may use the following test cycle... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Optional 3-Mode Test Cycle for Stationary Fire Pump Engines 6 Table 6 to Subpart IIII of Part 60 Protection of Environment ENVIRONMENTAL...

Safety and maintenance engineering: A compilation

Science.gov (United States)

1974-01-01

A compilation is presented for the dissemination of information on technological developments which have potential utility outside the aerospace and nuclear communities. Safety of personnel engaged in the handling of hazardous materials and equipment, protection of equipment from fire, high wind, or careless handling by personnel, and techniques for the maintenance of operating equipment are reported.

Fire protection for nuclear power plants. Part 1. Fundamental approaches. Version 6/99

International Nuclear Information System (INIS)

1999-06-01

The KTA nuclear safety code sets out the fundamental approaches and principles for the prevention of fires in nuclear power plants, addressing aspects such as initiation, spreading, and effects of a fire: (a) Fire load and ignition sources, (b) structural and plant engineering conditions, (c) ways and means relating to fire call and fire fighting. Relevant technical and organisational measures are defined. Scope and quality of fire prevention measures to be taken, as well the relevant in-service inspection activities are determined according to the protective goals pursued in each case. (orig./CB) [de

Safety analysis of the existing 850 Firing Facility

International Nuclear Information System (INIS)

Odell, B.N.

1986-01-01

A safety analysis was performed to determine if normal operations and/or potential accidents at the 850 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exception was explosives, which was classified as a moderate hazard per the requirements given in DOE Order 5481.1A. This safety analysis concluded that the operation at this facility will present no undue risk to the health and safety of LLNL employees or the public

Safety analysis of the existing 851 Firing Facility

International Nuclear Information System (INIS)

Odell, B.N.

1986-01-01

A safety analysis was performed to determine if normal operations and/or potential accidents at the 851 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but two of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exceptions were the linear accelerator and explosives, which were classified as moderate hazards per the requirements given in DOE Order 5481.1A. This safety analysis concluded that the operation at this facility will present no undue risk to the health and safety of LLNL employees or the public

30 CFR 77.1105 - Internal combustion engines; fueling.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Internal combustion engines; fueling. 77.1105 Section 77.1105 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE... COAL MINES Fire Protection § 77.1105 Internal combustion engines; fueling. Internal combustion engines...

Safety considerations and countermeasures against fire and explosion at an HTGR-hydrogen production system. Proposal of safety design concept

International Nuclear Information System (INIS)

Nishihara, T.; Hada, K.; Shibata, T.; Shiozawa, S.

1996-01-01

Establishment of safety design concept and countermeasures against fire and explosion accidents is among key safety-related issues in an HTGR-hydrogen production system. We propose the different safety design concepts depending upon the origin of fire and explosion which may happen in the HTGR-hydrogen production plant. Against fire and explosion originated outside the reactor building (R/B), namely in the area of hydrogen production plant, the safety design concept is primarily to take a safe distance for preventing the damage on safety-related items or a proof wall if necessary. Because the hydrogen production plant is designed in the same safety level as a conventional chemical plant. The safe distance is proposed to limit an incident overpressure to 10 kPa so as not to suffer any damage on the items and to limit a wall-averaged temperature of concrete structures of the R/B to 175degC according to the current regulation. On the other hand, against a potential possibility of explosion originated inside the R/B, the safety design concept is to minimize the possibility of explosion low enough to assume no occurrence inside the R/B. That is, the measure is to exclude a simultaneous failure of a secondary helium piping and an endothermic chemical reactor. Furthermore, in severe accident condition in which the explosion may be postulated a priori, an incidental overpressure of explosion inside the reactor containment vessel (C/V) should be limited so as not to fail the C/V through restricting the amount of combustible gas ingress into the C/V by means of a combination of C/V isolation valve installed in the helium piping and emergency shut off valve in the process feed gas line. (author)

Fire safety of LPG in marine transportation. Final report

Energy Technology Data Exchange (ETDEWEB)

Martinsen, W.E.; Johnson, D.W.; Welker, J.R.

1980-06-01

This report contains an analytical examination of cargo spill and fire hazard potential associated with the marine handling of liquefied petroleum gas (LPG) as cargo. Principal emphasis was on cargo transfer operations for ships unloading at receiving terminals, and barges loading or unloading at a terminal. Major safety systems, including emergency shutdown systems, hazard detection systems, and fire extinguishment and control systems were included in the analysis. Spill probabilities were obtained from fault tree analyses utilizing composite LPG tank ship and barge designs. Failure rates for hardware in the analyses were generally taken from historical data on similar generic classes of hardware, there being very little historical data on the specific items involved. Potential consequences of cargo spills of various sizes are discussed and compared to actual LPG vapor cloud incidents. The usefulness of hazard mitigation systems (particularly dry chemical fire extinguishers and water spray systems) in controlling the hazards posed by LPG spills and spill fires is also discussed. The analysis estimates the probability of fatality for a terminal operator is about 10/sup -6/ to 10/sup -5/ per cargo transfer operation. The probability of fatality for the general public is substantially less.

Safety assessment of outdoor live fire range

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-05-01

The following Safety Assessment (SA) pertains to the outdoor live fire range facility (LFR). The purpose of this facility is to supplement the indoor LFR. In particular it provides capacity for exercises that would be inappropriate on the indoor range. This SA examines the risks that are attendant to the training on the outdoor LFR. The outdoor LFR used by EG&G Mound is privately owned. It is identified as the Miami Valley Shooting Grounds. Mondays are leased for the exclusive use of EG&G Mound.

77 FR 4897 - Safety Zone; M/V Del Monte Live-Fire Gun Exercise, James River, Isle of Wight, VA

Science.gov (United States)

2012-02-01

...-AA00 Safety Zone; M/V Del Monte Live-Fire Gun Exercise, James River, Isle of Wight, VA AGENCY: Coast... provide for the safety of life on navigable waters during the live-fire gun exercises on the M/V Del Monte... associated with the live-fire gun exercise. DATES: This rule is effective in the CFR on February 1, 2012...

76 FR 31848 - Safety Zone; M/V Del Monte Live-Fire Gun Exercise, James River, Isle of Wight, Virginia

Science.gov (United States)

2011-06-02

...-AA00 Safety Zone; M/V Del Monte Live-Fire Gun Exercise, James River, Isle of Wight, Virginia AGENCY... provide for the safety of life on navigable waters during the live-fire gun exercises on the M/V Del Monte... associated with the live-fire gun exercise. DATES: This rule will be effective from 11 a.m. June 6, 2011...

Reactor engineering and engineered reactor safety in France

International Nuclear Information System (INIS)

1987-01-01

The proceedings give the full text of the lectures held by acknowledged French experts at the KTG Seminar in Mainz on March 10, 1987, all dealing with the leading topic of the current status of reactor engineering and development in France. Although the basic engineering principles and construction lines as well as the safety philosophy are the same in France as in West Germany, there have been distinctive developments over many years in the two countries that by now are not well known even among experts in this field, and hence cannot be properly assessed. Non-availability of relevant surveys or other type of literature in the German language reviewing the French developments is another factor that hitherto was a handicap to mutual exchange of information. The seminar was intended to close this gap. The proceedings should be read by all those in West Germany who wish to be informed about the developments in reactor engineering and reactor safety in France. (orig./DG) [de

Safety demonstration tests of postulated solvent fire accidents in extraction process of a fuel reprocessing plant, (2)

International Nuclear Information System (INIS)

Tukamoto, Michio; Takada, Junichi; Koike, Tadao; Nishio, Gunji; Uno, Seiichiro; Kamoshida, Atsusi; Watanabe, Hironori; Hashimoto, Kazuichiro; Kitani, Susumu.

1992-03-01

Demonstration tests of hypothetical solvent fire in an extraction process of the reprocessing plant were carried out from 1984 to 1985 in JAERI, focusing on the confinement of radioactive materials during the fire by a large-scale fire facility (FFF) to evaluate the safety of air-ventilation system in the plant. Fire data from the demonstration test were obtained by focusing on fire behavior at cells and ducts in the ventilation system, smoke generation during the fire, transport and deposition of smoke containing simulated radioactive species in the ventilation system, confinement of radioactive materials, and integrity of HEPA filters by using the FFF simulating an air-ventilation system of the reference reprocessing plant in Japan. The present report is published in a series of the report Phase I (JAERI-M 91-145) of the demonstration test. Test results in the report will be used for the verification of a computer code FACE to evaluate the safety of postulated fire accidents in the reprocessing plant. (author)

WIPP fire hazards and risk analysis

International Nuclear Information System (INIS)

1991-05-01

The purpose of this analysis was to conduct a fire hazards risk analysis of the Transuranic (TRU) contact-handled waste receipt, emplacement, and disposal activities at the Waste Isolation Pilot Plant (WIPP). The technical bases and safety envelope for these operations are defined in the approved WIPP Final Safety Analysis Report (FSAR). Although the safety documentation for the initial phase of the Test Program, the dry bin scale tests, has not yet been approved by the Department of Energy (DOE), reviews of the draft to date, including those by the Advisory Committee on Nuclear Facility Safety (ACNFS), have concluded that the dry bin scale tests present no significant risks in excess of those estimated in the approved WIPP FSAR. It is the opinion of the authors and reviewers of this analysis, based on sound engineering judgment and knowledge of the WIPP operations, that a Fire Hazards and Risk Analysis specific to the dry bin scale test program is not warranted prior to first waste receipt. This conclusion is further supported by the risk analysis presented in this document which demonstrates the level of risk to WIPP operations posed by fire to be extremely low. 15 refs., 41 figs., 48 tabs

FDS Modeling of the Sensitivity of the Smoke Potential Values used in Fire Safety Strategies

DEFF Research Database (Denmark)

Corches, Andrei-Mircea; Ulriksen, Lene; Jomaas, Grunde

2014-01-01

To investigate the sensitivity of Fire Dynamics Simulator (FDS) with respect to the input parameters that are used to define the optical properties of the smoke, a parametric study was performed for relevant fire scenarios in an open plan office building. The parametric study mainly focuses on th...... to defining the design fires will reduce the sensitivity of the numerical fire simulation and further reduce the risk of overestimating the evacuation safety level (ESL) of the building....

Integrating system safety into the basic systems engineering process

Science.gov (United States)

Griswold, J. W.

1971-01-01

The basic elements of a systems engineering process are given along with a detailed description of what the safety system requires from the systems engineering process. Also discussed is the safety that the system provides to other subfunctions of systems engineering.

Fire safety of historical buildings traditional versus innovative “behavioural design” solutions by using wayfinding systems

CERN Document Server

Bernardini, Gabriele

2017-01-01

This book applies a behavioral point of view to individuals’ fire safety in historic buildings. It outlines theoretical and operative issues, based on recent studies and international guidelines. Firstly, critical issues for Building Heritage fire safety are widely discussed, by including the modelling of human factor and man-environment-fire interference in these architectural spaces. A significant part of the book includes a discussion on emergency modeling and simulation. A source code for representing the fire evacuation process (including man-evacuation facilities interactions) is offered to the reader. Methods for effectiveness assessment of risk-reducing solutions are provided and tested in a case-study. Being a structured approach to occupants-related problems during a fire in heritage buildings, it offers an innovative methodology and practical examples that researchers and designers can use as a guide when proposing and testing solutions. Evaluation indexes for effectiveness assessment (also usefu...

10. colloquium on aspects of chemical and physical safety engineering. Current trends in safety engineering - research findings and legal boundary conditions - new options for large-scale experiments; 10. Kolloquium zu Fragen der chemischen und physikalischen Sicherheitstechnik. Aktuelle Entwicklungen in der Sicherheitstechnik - Forschungsergebnisse und gesetzliches Umfeld - neue Moeglichkeiten fuer Grossversuche

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

Since 1981, BAM and PTB have been hosting of this series of colloquia, at which attendants were informed on current news and trends in chemical and physical safety engineering. This volume informs on explosion protection to prevent formation of explosive solvent/vapour/air mixtures in dryers, ignition source safety of ga/air, dust/air, and dust layers, sudden ignition processes in hydrogen/air mixtures, test methods, influencing parameters of the hazardous properties of ammonium nitrate and materials containing it, fire behaviour and fire hazards of bulk goods and specific materials, problems in the application of new technical rules and directives on a national and European level, and new approaches to probabilistic risk assessment for safe design of gas stores. At this anniversary meeting, the attendants were also given the opportunity to visit the BAM test facilities at Horstwalde, about 50 km south of Berlin. This test site, with an area of 12 km{sup 2}, has an explosion test area with a diameter of 400 m for fire and explosion tests up to 150 kg TNT. (orig.)

TIS General Safety Group Annual Report 2000

CERN Document Server

Weingarten, W

2001-01-01

This report summarises the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division (TIS) during the year 2000, and the results obtained. The different topics in which the Group is active are covered: general safety inspections and ergonomy, electrical, chemistry and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

Ongoing enhancements in the German nuclear regulatory framework with respect to fire safety

Energy Technology Data Exchange (ETDEWEB)

Elsche, Bjoern [e.on Kernkraft, Hannover (Germany); Roewekamp, Marina [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany); Neugebauer, Wilfried [AREVA NP, Erlangen (Germany); Gersinska, Rainer [Bundesamt fuer Strahlenschutz (BfS), Salzgitter (Germany). KTA-Geschaeftsstelle

2015-12-15

In the recent past, the regulatory framework for nuclear power plants (NPP) in Germany has been updated and enhanced comprising on the one hand comprehensive high level regulatory documents such as the 'Safety Requirements for Nuclear Power Plants' and, on the other hand, revised state-of-the-art nuclear safety standards and rules being incorporated in a corresponding legal structure. A major enhancement concerns the nuclear fire and explosion protection standards being already available as so-called green print for final comments which are expected to be officially published end of 2015. The update became necessary after approx. ten years for better addressing some lessons learnt form the operating experience, the consideration of post- Fukushima insights, such as more systematically addressing event combinations with fires and taking into account deviations from non-nuclear standards for escape and rescue routes. Moreover, fire protections remains an important issue for nuclear power plants in Germany during the longer term post-commercial safe shutdown period before decommissioning during which the spent fuel elements remain either in the containment or in the spent fuel pool for further years requiring suitable fire protection means being in place.

Gypsum plasterboards enhanced with phase change materials: A fire safety assessment using experimental and computational techniques

Directory of Open Access Journals (Sweden)

Kolaitis Dionysios I.

2013-11-01

Full Text Available Phase Change Materials (PCM can be used for thermal energy storage, aiming to enhance building energy efficiency. Recently, gypsum plasterboards with incorporated paraffin-based PCM blends have become commercially available. In the high temperature environment developed during a fire, the paraffins, which exhibit relatively low boiling points, may evaporate and, escaping through the gypsum plasterboard's porous structure, emerge to the fire region, where they may ignite, thus adversely affecting the fire resistance characteristics of the building. Aiming to assess the fire safety behaviour of such building materials, an extensive experimental and computational analysis is performed. The fire behaviour and the main thermo-physical physical properties of PCM-enhanced gypsum plasterboards are investigated, using a variety of standard tests and devices (Scanning Electron Microscopy, Thermo Gravimetric Analysis, Cone Calorimeter. The obtained results are used to develop a dedicated numerical model, which is implemented in a CFD code. CFD simulations are validated using measurements obtained in a cone calorimeter. In addition, the CFD code is used to simulate an ISO 9705 room exposed to fire conditions, demonstrating that PCM addition may indeed adversely affect the fire safety of a gypsum plasterboard clad building.

Fire hazard analysis for Plutonium Finishing Plant complex

Energy Technology Data Exchange (ETDEWEB)

MCKINNIS, D.L.

1999-02-23

A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements are addressed in terms of the fire protection objectives stated in paragraph 4 of DOE 5480.7A. In addition, the FHA also complies with WHC-CM-4-41, Fire Protection Program Manual, Section 3.4 [1994] and WHC-SD-GN-FHA-30001, Rev. 0 [WHC, 1994]. Objectives of the FHA are to determine: (1) the fire hazards that expose the PFP facilities, or that are inherent in the building operations, (2) the adequacy of the fire safety features currently located in the PFP Complex, and (3) the degree of compliance of the facility with specific fire safety provisions in DOE orders, related engineering codes, and standards.

Methods for the sodium cooled fast reactor fire safety provisions

International Nuclear Information System (INIS)

Gryaznov, B.V.; Dergachev, N.P.

1983-01-01

Problems of fire safety provision on NPPs with sodium cooled fast reactor are under discussion. Methods of sodium leak localization, measures eliminating sodium flaring up during leaks and main means of sodium fire extinguishing are considered. An extinguishing of sodium flaring up is performed by means of sodium temperatUre decrease and by limitation of hydrogen access to the flaring up surface. A conclusion is made that the most effective methods of extinguishing are the following: self-extinguishing (due to hydrogen burning out in a limiting volume); extinguishing by a gas mixture of nitrogen and carbonic acid (initial filling and blowing of rooms during sodium flaring up); extinguishing by special powders

Evaluation of fire hazard analyses for nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1995-01-01

The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire safety of nuclear power plants. The publication supplements the broad concepts of Safety Series No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, by providing a detailed list of the issues, and some of the limitations, to be considered when evaluating the adequacy and effectiveness of the fire hazard analysis of a nuclear power plant. The publication is intended for assessors of fire hazard analyses, including regulators, independent assessors or plant assessors, and gives a broad description of the methodology to be used by operators in preparing a fire hazard analysis for their own plant. 1 fig

Fire Safety Aspects of Polymeric Materials. Volume 7. Buildings

Science.gov (United States)

1979-01-01

Custodial Buildings 136 4.5.5 Retail Stores, Malls, etc. 138 l’ 4.5.6 Restaurants and Nightclubs 4.5.7 Public Assembly Occupancies - Auditoria , Theaters... auditoria , theaters, exhibition halls, arenas, transportation terminals; educational buildings and indus- trial buildings. Many of the fire safety...usage are developed. 4.5.7 Public Assembly Occupancies - Auditoria , Theaters, Exhibition Halls, Arenas, Transportation Terminals, Etc. The factors

Advanced methods for a probabilistic safety analysis of fires. Development of advanced methods for performing as far as possible realistic plant specific fire risk analysis (fire PSA)

International Nuclear Information System (INIS)

Hofer, E.; Roewekamp, M.; Tuerschmann, M.

2003-07-01

In the frame of the research project RS 1112 'Development of Methods for a Recent Probabilistic Safety Analysis, Particularly Level 2' funded by the German Federal Ministry of Economics and Technology (BMWi), advanced methods, in particular for performing as far as possible realistic plant specific fire risk analyses (fire PSA), should be developed. The present Technical Report gives an overview on the methodologies developed in this context for assessing the fire hazard. In the context of developing advanced methodologies for fire PSA, a probabilistic dynamics analysis with a fire simulation code including an uncertainty and sensitivity study has been performed for an exemplary scenario of a cable fire induced by an electric cabinet inside the containment of a modern Konvoi type German nuclear power plant taking into consideration the effects of fire detection and fire extinguishing means. With the present study, it was possible for the first time to determine the probabilities of specified fire effects from a class of fire events by means of probabilistic dynamics supplemented by uncertainty and sensitivity analyses. The analysis applies a deterministic dynamics model, consisting of a dynamic fire simulation code and a model of countermeasures, considering effects of the stochastics (so-called aleatory uncertainties) as well as uncertainties in the state of knowledge (so-called epistemic uncertainties). By this means, probability assessments including uncertainties are provided to be used within the PSA. (orig.) [de

Determination of engineering safety factor -routine in Hungary (a methodology for the normal operation local power engineering safety factors)

International Nuclear Information System (INIS)

Szecsenyi, Z.; Korpas, L.; Bona, G.; Kereszturi, A.

2010-01-01

From the late nineties Paks Nuclear Power Plant-in collaboration with KFKI Atomic Energy Research Institute (KFKI AEKI)- is developing a system for determining the normal operation local power engineering safety factors. The system is based on a Monte Carlo sampling of the uncertain model input parameters. Additionally, the comparison of the calculation to the in-core measurements plays essential role for determining some important input parameters. By using new fuel types and the corresponding more recent detailed technological data, the applied method is being improved from time to time. Presently, the actually used and authorized engineering safety factors at Paks NPP are determined by using this method. In the paper, the system.s main properties are described (not going beyond the possible extent). The main points are as follows:-Mathematical definition of the engineering safety factor;-Sources of the uncertainties;-Input error propagation method constituting the basis of the system;-Flow-chart of the subsequent steps of the determination Finally, in the paper the engineering safety factors values of some selected parameters are presented as examples for demonstration of the capability of the method. (Authors)

Fire and evacuation drills make the CERN safety plans work

CERN Multimedia

Antonella Del Rosso

2013-01-01

Regular drills are a way of making sure that we are ready and able to react in the event of a fire or other adverse event. They are also a demanding test of all the technical and organisational measures in place to allow the quick and safe evacuation of buildings. Recently, large-scale drills took place in Building 40 and at Point 5 underground.   Group photo at Point 5, after the common evacuation drill. The ability to react to unexpected, adverse events relies in particular on training. This is why CERN’s safety teams organise regular drills. One of the most recent exercises took place on 26 March in Building 40. “Building 40 is a modern building fully equipped against fire, with two emergency exits in the central atrium. We also have 29 emergency guides distributed on each floor to guide people out of their offices,” says Kate Richardson, Territorial Safety Officer of the building. “The drills are very useful for testing the building's insta...

Fire risk analysis for nuclear power plants: Methodological developments and applications

International Nuclear Information System (INIS)

Kazarians, M.; Apostolakis, G.; Siv, N.O.

1985-01-01

A methodology to quantify the risk from fires in nuclear power plants is described. This methodology combines engineering judgment, statistical evidence, fire phenomenology, and plant system analysis. It can be divided into two major parts: (1) fire scenario identification and quantification, and (2) analysis of the impact on plant safety. This article primarily concentrates on the first part. Statistical analysis of fire occurrence data is used to establish the likelihood of ignition. The temporal behaviors of the two competing phenomena, fire propagation and fire detection and suppression, are studied and their characteristic times are compared. Severity measures are used to further specialize the frequency of the fire scenario. The methodology is applied to a switchgear room of a nuclear power plant

The General Safety Group Annual Report 2001/2002

CERN Document Server

Weingarten, W

2003-01-01

This report summarizes the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division during 2001 and 2002, and the results obtained. The different topics in which the group is active are covered: general safety inspections and ergonomics, electrical, chemical and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

Patient safety trilogy: perspectives from clinical engineering.

Science.gov (United States)

Gieras, Izabella; Sherman, Paul; Minsent, Dennis

2013-01-01

This article examines the role a clinical engineering or healthcare technology management (HTM) department can play in promoting patient safety from three different perspectives: a community hospital, a national government health system, and an academic medical center. After a general overview, Izabella Gieras from Huntington Hospital in Pasadena, CA, leads off by examining the growing role of human factors in healthcare technology, and describing how her facility uses clinical simulations in medical equipment evaluations. A section by Paul Sherman follows, examining patient safety initiatives from the perspective of the Veterans Health Administration with a focus on hazard alerts and recalls. Dennis Minsent from Oregon Health & Science University writes about patient safety from an academic healthcare perspective, and details how clinical engineers can engage in multidisciplinary safety opportunities.

Engineering design guidelines for nuclear criticality safety

International Nuclear Information System (INIS)

Waltz, W.R.

1988-08-01

This document provides general engineering design guidelines specific to nuclear criticality safety for a facility where the potential for a criticality accident exists. The guide is applicable to the design of new SRP/SRL facilities and to major modifications Of existing facilities. The document is intended an: A guide for persons actively engaged in the design process. A resource document for persons charged with design review for adequacy relative to criticality safety. A resource document for facility operating personnel. The guide defines six basic criticality safety design objectives and provides information to assist in accomplishing each objective. The guide in intended to supplement the design requirements relating to criticality safety contained in applicable Department of Energy (DOE) documents. The scope of the guide is limited to engineering design guidelines associated with criticality safety and does not include other areas of the design process, such as: criticality safety analytical methods and modeling, nor requirements for control of the design process

Experience with performance based training of nuclear criticality safety engineers

International Nuclear Information System (INIS)

Taylor, R.G.

1993-01-01

For non-reactor nuclear facilities, the U.S. Department of Energy (DOE) does not require that nuclear criticality safety engineers demonstrate qualification for their job. It is likely, however, that more formalism will be required in the future. Current DOE requirements for those positions which do have to demonstrate qualification indicate that qualification should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis is incompletely developed in some areas

Bridging the divide between fire safety research and fighting fire safely: How do we convey research innovation to contribute more effectively to wildland firefighter safety?

Science.gov (United States)

Theodore Ted Adams; Bret W. Butler; Sara Brown; Vita Wright; Anne Black

2017-01-01

Creating a safe workplace for wildland firefighters has long been at the centre of discussion for researchers and practitioners. The goal of wildland fire safety research has been to protect operational firefighters, yet its contributions often fall short of potential because much is getting lost in the translation of peer-reviewed results to potential and intended...

Operation of Browns Ferry, Units 1 and 2 following the March 22, 1975 fire. Safety evaluation report

International Nuclear Information System (INIS)

1976-03-01

The Safety Evaluation Report issued February 23, 1976, presents the NRC evaluation regarding the acceptability of the restoration and modifications at the Browns Ferry Plant Units 1 and 2, following the March 22, 1975 fire, to establish that the facility may be operated in the restored and modified condition without endangering the health and safety of the public. The modifications involved enhancing separation of redundant safeguards equipment by some rerouting of cable and by the application of a fire-retardant coating to the cable; enhancing fire extinguishing capability by the addition of fixed spray and sprinkler systems and expanded smoke and heat detection systems; and enhancing the overall fire protection program by changes in procedures, training, and organization. The NRC staff indicated some items that remained to be resolved prior to operation and concluded that subject to their satisfactory resolution the restoration of Browns Ferry Nuclear Plants Units 1 and 2 including the modifications is acceptable and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the facility as restored and modified

Safety assessment of VHTR hydrogen production system against fire, explosion and acute toxicity

International Nuclear Information System (INIS)

Murakami, Tomoyuki; Nishihara, Tetsuo; Kunitomi, Kazuhiko

2008-01-01

The Japan Atomic Energy Agency has been developing a nuclear hydrogen production system by using heat from the Very High Temperature Reactor (VHTR). This system will handle a large amount of combustible gas and toxic gas. The risk from fire, explosion and acute toxic exposure caused by an accident involving chemical material release in a hydrogen production system is assessed. It is important to ensure the safety of the nuclear plant, and the risks for public health should be sufficiently small. This report provides the basic policy for the safety evaluation in cases of accident involving fire, explosion and toxic material release in a hydrogen production system. Preliminary safety analysis of a commercial-sized VHTR hydrogen production system, GTHTR300C, is performed. This analysis provides us with useful information on the separation distance between a nuclear plant and a hydrogen production system and a prospect that an accident in a hydrogen production system does not significantly increase the risks of the public. (author)

Workshop on explosions, BLEVEs, fires, etc.

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

The purpose of this workshop will be to provide a bridge between engineering practices, modeling, and measurement of fires and explosions, and use this information in a practical manner to improve the fire safety of the process facility. New techniques and information are available on the means to prevent, predict and mitigate fires and explosions. A review of BLEVEs and methods for preventing and protecting against the effects of BLEVES in large petrochemical facilities. Observations and the use of models that have been successful in predicting the effects of vapor explosions for the prevention of collapse of structures and mitigation of the effects of vapor explosions in process facilities are presented. Recent work involving the measurement of radiation from large jet fires at the Kuwaiti oil fields and fire tests of crude oil spills on the sea is discussed. Fire radiation measurement can be used to predict effects on structures, facilities, and the complexity of fire fighting operations required for control of spill and pool fires. Practical applications of techniques for prevention and control of explosions within building, resulting from failures of autoclaves or release of flammable gas to the atmosphere of the building are discussed.

Applying Open Source Game Engine for Building Visual Simulation Training System of Fire Fighting

Science.gov (United States)

Yuan, Diping; Jin, Xuesheng; Zhang, Jin; Han, Dong

There's a growing need for fire departments to adopt a safe and fair method of training to ensure that the firefighting commander is in a position to manage a fire incident. Visual simulation training systems, with their ability to replicate and interact with virtual fire scenarios through the use of computer graphics or VR, become an effective and efficient method for fire ground education. This paper describes the system architecture and functions of a visual simulated training system of fire fighting on oil storage, which adopting Delat3D, a open source game and simulation engine, to provide realistic 3D views. It presents that using open source technology provides not only the commercial-level 3D effects but also a great reduction of cost.

Assessment of Application Example for a Sodium Fire Extinguishing Facility using Safety Control of Dangerous Substances Act

International Nuclear Information System (INIS)

Jung, Minhwan; Jeong, Ji-Young; Kim, Jongman

2014-01-01

Sodium is under regulation of four kinds of laws including the Safety Control of Dangerous Substances Act and it is under categorized as Class 3(pyrophoric material, water-prohibiting substance). To obtain a license for a sodium experiment facility, the codes and regulations must be satisfied in the Safety Control of Dangerous Substance Act. However, there are some parts that need to be discussed in related regulations in the Safety Control of Dangerous Substance Act because there are differences with the actual features of sodium. To apply for an actual sodium facility, it is necessary to give a supplementary explanation regarding the regulations. The objective of this study is to assess the application example of a sodium experiment facility using the above mentioned laws and to propose the necessity of an amendment for conventional laws in regard to fire extinguishing systems and agents. In this work, an application example of a sodium experiment facility using the Safety Control of Dangerous Substances Act, and the necessity of amending the existing laws in regard to fire extinguishing systems including the agent used, was assessed. The safest standard was applied for cases in which the consideration of a sodium fire is not mentioned in conventional regulations. For the construction of the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor), the described regulations in this work should be reviewed and improved carefully by the fire safety regulatory body

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies

Energy Technology Data Exchange (ETDEWEB)

Neupauer, R.M.; Thurmond, S.M.

1992-09-01

This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

Developing safety culture in nuclear power engineering

International Nuclear Information System (INIS)

Tevlin, S.A.

2000-01-01

The new issue (no. 11) of the IAEA publications series Safety Reports, devoted to the safety culture in nuclear engineering Safety culture development in the nuclear activities. Practical recommendations to achieve success, is analyzed. A number of recommendations of international experts is presented and basic general indicators of satisfactory and insufficient safety culture in the nuclear engineering are indicated. It is shown that the safety culture has two foundations: human behavior and high quality of the control system. The necessity of creating the confidence by the management at all levels of the enterprise, development of individual initiative and responsibility of the workers, which make it possible to realize the structural hierarchic system, including technical, human and organizational constituents, is noted. Three stages are traced in the process of introducing the safety culture. At the first stage the require,emts of scientific-technical documentation and provisions of the governmental, regional and control organs are fulfilled. At the second stage the management of the organization accepts the safety as an important direction in its activities. At the third stage the organization accomplishes its work, proceeding from the position of constant safety improvement. The general model of the safety culture development is considered [ru

Experience with performance based training of nuclear criticality safety engineers

International Nuclear Information System (INIS)

Taylor, R.G.

1993-01-01

Historically, new entrants to the practice of nuclear criticality safety have learned their job primarily by on-the-job training (OJT) often by association with an experienced nuclear criticality safety engineer who probably also learned their job by OJT. Typically, the new entrant learned what he/she needed to know to solve a particular problem and accumulated experience as more problems were solved. It is likely that more formalism will be required in the future. Current US Department of Energy requirements for those positions which have to demonstrate qualification indicate that it should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis i's incompletely developed in some areas. Details of this analysis are provided in this report

Investigation of potential fire-related damage to safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Wanless, J.

1985-11-01

Based on a review of vendor information, fire damage reports, equipment qualification and hydrogen burn test results, and material properties, thirty-three types of equipment found in nuclear power plants were ranked in terms of their potential sensitivity to fire environments. The ranking considered both the functional requirements and damage proneness of each component. A further review of the seven top-ranked components was performed, considering the relative prevalence and potential safety significance of each. From this, relays and hand switches dominate as first choices for fire damage testing with logic equipment, power supplies, transmitters, and motor control centers as future candidates

OASIS: An automotive analysis and safety engineering instrument

International Nuclear Information System (INIS)

Mader, Roland; Armengaud, Eric; Grießnig, Gerhard; Kreiner, Christian; Steger, Christian; Weiß, Reinhold

2013-01-01

In this paper, we describe a novel software tool named OASIS (AutOmotive Analysis and Safety EngIneering InStrument). OASIS supports automotive safety engineering with features allowing the creation of consistent and complete work products and to simplify and automate workflow steps from early analysis through system development to software development. More precisely, it provides support for (a) model creation and reuse, (b) analysis and documentation and (c) configuration and code generation. We present OASIS as a part of a tool chain supporting the application of a safety engineering workflow aligned with the automotive safety standard ISO 26262. In particular, we focus on OASIS' (1) support for property checking and model correction as well as its (2) support for fault tree generation and FMEA (Failure Modes and Effects Analysis) table generation. Finally, based on the case study of hybrid electric vehicle development, we demonstrate that (1) and (2) are able to strongly support FTA (Fault Tree Analysis) and FMEA

Safety - Multiple Languages

Science.gov (United States)

... bosanski (Bosnian) PDF Fire Safety at Home - English MP3 Fire Safety at Home - bosanski (Bosnian) MP3 Fire Safety at Home - English MP4 Fire Safety ... Burmese) PDF Home Safety Checklist - myanma bhasa (Burmese) MP3 Minnesota Department of Health Chinese, Simplified (Mandarin dialect) ( ...

Contributions of microgravity test results to the design of spacecraft fire-safety systems

Science.gov (United States)

Friedman, Robert; Urban, David L.

1993-01-01

Experiments conducted in spacecraft and drop towers show that thin-sheet materials have reduced flammability ranges and flame-spread rates under quiescent low-gravity environments (microgravity) compared to normal gravity. Furthermore, low-gravity flames may be suppressed more easily by atmospheric dilution or decreasing atmospheric total pressure than their normal-gravity counterparts. The addition of a ventilating air flow to the low-gravity flame zone, however, can greatly enhance the flammability range and flame spread. These results, along with observations of flame and smoke characteristics useful for microgravity fire-detection 'signatures', promise to be of considerable value to spacecraft fire-safety designs. The paper summarizes the fire detection and suppression techniques proposed for the Space Station Freedom and discusses both the application of low-gravity combustion knowledge to improve fire protection and the critical needs for further research.

Contributions of Microgravity Test Results to the Design of Spacecraft Fire Safety Systems

Science.gov (United States)

Friedman, Robert; Urban, David L.

1993-01-01

Experiments conducted in spacecraft and drop towers show that thin-sheet materials have reduced flammability ranges and flame-spread rates under quiescent low-gravity environments (microgravity) as compared to normal gravity. Furthermore, low-gravity flames may be suppressed more easily by atmospheric dilution or decreasing atmospheric total pressure than their normal-gravity counterparts. The addition of a ventilating air flow to the low-gravity flame zone, however, can greatly enhance the flammability range and flame spread. These results, along with observations of flame and smoke characteristics useful for microgravity fire-detection 'signatures', promise to be of considerable value to spacecraft fire-safety designs. The paper summarizes the fire detection and suppression techniques proposed for the Space Station Freedom and discusses both the application of low-gravity combustion knowledge to improve fire protection and the critical needs for further research.

Fire Situations and Prevention Measures of residential building

Directory of Open Access Journals (Sweden)

Zhou Baixia

2017-01-01

Full Text Available The proportion of residential building is the largest in all buildings. With the development of urbanization, residential building fires are at high momentum. The paper lists the residential building fires and the number of casualties’ proportion to total fires from 2011 to 2014, analyzing the high incidence causes of the fires and casualties and putting forward suggestions and countermeasures including carrying out fire safety education to improve the fire safety awareness of residents, fulfilling responsibility to enhancing fire safety management capabilities, perfecting fire apparatus to develop fire safety environment and enhancing public awareness of fire safety, equipping evacuation equipments to promote response ability to deal with disasters etc.

Safety test of an improved multihundred watt FSA: launch abort, solid propellant fire

International Nuclear Information System (INIS)

Seabourn, C.M.

1978-07-01

This safety test consisted of exposing a simulant-fueled Improved Multihundred Watt Fuel Sphere Assembly, containing a Pt-3008 sphere holding the fuel simulant, to a single proximity fire of UTP-3001 solid rocket propellant for 10.5 min. The graphite outside shell sustained only minor abrasion damage. It was covered on one side with a heavy deposit of alumina from the fire mixed with silica from the test bed. The Pt-3008 shell had small amounts of carbon, alumina, and silica deposited on its surface but sustained no other damage. The PT-3008 sphere was not breached, and therefore the fuel sphere assembly would not release fuel in a solid-propellant fire of a launch abort. 12 figures

Engineering systems reliability, safety, and maintenance an integrated approach

CERN Document Server

Dhillon, B S

2017-01-01

Today, engineering systems are an important element of the world economy and each year billions of dollars are spent to develop, manufacture, operate, and maintain various types of engineering systems around the globe. Many of these systems are highly sophisticated and contain millions of parts. For example, a Boeing jumbo 747 is made up of approximately 4.5 million parts including fasteners. Needless to say, reliability, safety, and maintenance of systems such as this have become more important than ever before.　 Global competition and other factors are forcing manufacturers to produce highly reliable, safe, and maintainable engineering products. Therefore, there is a definite need for the reliability, safety, and maintenance professionals to work closely during design and other phases. Engineering Systems Reliability, Safety, and Maintenance: An Integrated Approach eliminates the need to consult many different and diverse sources in the hunt for the information required to design better engineering syste...

Detection and Elimination of a Potential Fire in Engine and Battery Compartments of Hybrid Electric Vehicles

Directory of Open Access Journals (Sweden)

Macam S. Dattathreya

2012-01-01

Full Text Available This paper presents a novel fuzzy deterministic noncontroller type (FDNCT system and an FDNCT inference algorithm (FIA. The FDNCT uses fuzzy inputs and produces a deterministic non-fuzzy output. The FDNCT is an extension and alternative for the existing fuzzy singleton inference algorithm. The research described in this paper applies FDNCT to build an architecture for an intelligent system to detect and to eliminate potential fires in the engine and battery compartments of a hybrid electric vehicle. The fuzzy inputs consist of sensor data from the engine and battery compartments, namely, temperature, moisture, and voltage and current of the battery. The system synthesizes the data and detects potential fires, takes actions for eliminating the hazard, and notifies the passengers about the potential fire using an audible alarm. This paper also presents the computer simulation results of the comparison between the FIA and singleton inference algorithms for detecting potential fires and determining the actions for eliminating them.

Preparedness of fire safety in underground train station: Comparison between train operators in Malaysia with other operators from the developed countries

Science.gov (United States)

Tajedi, Noor Aqilah A.; Sukor, Nur Sabahiah A.; Ismail, Mohd Ashraf M.; Shamsudin, Shahrul A.

2017-10-01

The purpose of this paper is to compare the fire evacuation plan and preparation at the underground train stations in the different countries. The methodology for this study was using the extended questionnaire survey to investigate the Rapid Rail Sdn Bhd, Malaysia's fire safety plan and preparation at the underground train stations. There were four sections in the questionnaire which included (i) background of the respondents, (ii) the details on the train stations, safety instruction and fire evacuation exercises (iii) technical systems, installation and equipment at the underground stations and (iv) procedures and technical changes related to fire safety that had been applied by the operators. Previously, the respondents from the different train operator services in the developed countries had completed the questionnaires. This paper extends the response from the Rapid Rail Sdn Bhd to compare the emergency procedures and preparation for fire event with the developed countries. As a result, this study found that the equipment and facilities that provided at the underground train stations that operated by Rapid Rail are relevant for fire safety procedures and needs. The main advantage for Rapid Rail is the underground stations were designed with two or more entrances/exits that may perform better evacuation compare to one main entrance/exit train stations in the other developed countries.

The influence of engine speed and load on the heat transfer between gases and in-cylinder walls at fired and motored conditions of an IDI diesel engine

International Nuclear Information System (INIS)

Sanli, Ali; Ozsezen, Ahmet N.; Kilicaslan, Ibrahim; Canakci, Mustafa

2008-01-01

In this study, the heat transfer characteristics between gases and in-cylinder walls at fired and motored conditions in a diesel engine were investigated by using engine data obtained experimentally. For this investigation, a four-cylinder, indirect injection (IDI) diesel engine was tested under different engine speeds and loads. The heat transfer coefficient was calculated by using Woschni expression correlated for the IDI diesel engines, and also using Annand and Hohenberg expressions. The temperature of in-cylinder gases were determined from a basic model based on the first law of thermodynamics after measuring in-cylinder pressure experimentally. The results show that the heat transfer characteristics of the IDI diesel engine strongly depend on the engine speed and load as a function of crank angle at fired and motored conditions

The influence of engine speed and load on the heat transfer between gases and in-cylinder walls at fired and motored conditions of an IDI diesel engine

Energy Technology Data Exchange (ETDEWEB)

Sanli, Ali; Kilicaslan, Ibrahim [Department of Mechanical Education, Kocaeli University, 41380 Izmit (Turkey); Ozsezen, Ahmet N.; Canakci, Mustafa [Department of Mechanical Education, Kocaeli University, 41380 Izmit (Turkey); Alternative Fuels R and D Center, Kocaeli University, 41040 Izmit (Turkey)

2008-08-15

In this study, the heat transfer characteristics between gases and in-cylinder walls at fired and motored conditions in a diesel engine were investigated by using engine data obtained experimentally. For this investigation, a four-cylinder, indirect injection (IDI) diesel engine was tested under different engine speeds and loads. The heat transfer coefficient was calculated by using Woschni expression correlated for the IDI diesel engines, and also using Annand and Hohenberg expressions. The temperature of in-cylinder gases were determined from a basic model based on the first law of thermodynamics after measuring in-cylinder pressure experimentally. The results show that the heat transfer characteristics of the IDI diesel engine strongly depend on the engine speed and load as a function of crank angle at fired and motored conditions. (author)

Current Status of Fire Risk Assessment in Germany

International Nuclear Information System (INIS)

Berg, H. P.

2002-01-01

The approach for fire risk assessment to be applied within periodic safety reviews of nuclear power plants in Germany starts with a screening process providing critical fire zones in which a fully developed fire has the potential to both cause an initiating event and impair the function of at least one component or system critical to safety. The second step is to perform a quantitative analysis. For that purpose, a standard event tree has been developed with elements for fire initiation, ventilation of the room, fire detection, fire suppression, and fire propagation. This standard event tree has to be adapted to each critical fire zone or room. In a final step, the fire induced frequency of initiating events, the main contributors and the calculated hazard state frequency for the fire event are determined. In order to perform a quantitative fire risk assessment, a basic data base must be established which should, e.g., include initiating frequencies, reliability data for all fire protection measures, fire barriers, etc. Detailed plant-specific information is needed on ignition sources, detection and extinguishing systems, manual fire fighting, stationary fire suppression systems. As one contributor to fire specific PSA input data, reliability data for the active fire protection measures are required for the application in the fire specific event tree analysis. These data needed to be estimated are unavailabilities per demand or failure rates per hour of plant operation for those components or systems belonging to the active fire protection means. The data on potential failures or unavailabilities per demand of the respective fire protection measures were gained from the plant specific documentation of inspection and maintenance. The assessment whether the detected findings are estimated as failures or only as deficiencies or deteriorations requires a deep insight in the plant specific operating conditions for the fire protection means and needs careful engineering

2012 national state safety engineers and traffic engineers peer-to-peer workshop.

Science.gov (United States)

2013-11-01

The Illinois Department of Transportation (IDOT) and the Illinois Center for Transportation (ICT) sponsored and hosted the : 2012 National State Safety Engineers and Traffic Engineers Peer-to-Peer Workshop on November 14 and 15, 2012, at the : Hyatt ...

Environmental optimisation of natural gas fired engines. Measurement on four different engines. Project report

Energy Technology Data Exchange (ETDEWEB)

Kvist, T.

2010-10-15

The emissions of NO{sub x}, CO and UHC as well as the composition of the hydrocarbon emissions were measured for four different stationary lean burn natural gas fired engines installed at different combined heat and power (CHP) units in Denmark. The units have been chosen to be representative for the natural gas engine based on power production in Denmark. The NO{sub x} emissions were varied from around 200 to 500 mg/m3(n) by varying the ignition timing and the excess of air. For each of the examined engines measurements were conducted at different combinations of ignition timing and excess of air. The measurements showed the NO{sub x} emissions were relatively more sensitive to engine setting than UHC, CO and formaldehyde emissions. By reducing the NO{sub x} emissions to 40 % of the initial value (from 500 to 200 mg/m3(n)) the UHC emission were increased by 10 % to 50 % of the initial value. The electrical efficiency was reduced by 0,5 to 1,0 % point. (Author)

Criticality safety engineer training at WSRC

International Nuclear Information System (INIS)

Williamson, T.G.; Mincey, J.F.

1993-01-01

Two programs designed to prepare engineers for certification as criticality safety engineers are offered at Westinghouse Savannah River Company (WSRC). One program, Student On Loan Criticality Engineer Training (SOLCET), is an intensive 2-yr course involving lectures, rigorous problem assignments, and mentoring. The other program, In-Field Criticality Engineer Training (IN-FIELD), is a less intensive series of lectures and problem assignments. Both courses are conducted by members of the Applied Physics Group (APG) of the Savannah River Technical Center, the organization at WSRC responsible for the operation and maintenance of criticality codes and for training of code users

Utilization of the safety functional analysis techniques to optimize the separation requirements in case of fire

International Nuclear Information System (INIS)

Alvarez, L.M.

1983-01-01

The present philosophy for the fire protection of the safe shutdown capability in nuclear power plants is based on the separation of the safety-related systems in different fire areas in such a way that the redundant systems are not subject to damage from a single fire risk. The purpose ofthis paper is to show the experience gained in the application of a symmetric method of analysis to minimize the number of fire barriers being compatible with the regulatory requirements and with capability of achieving and maintaining the safe plant shutdown in the event of a fire. As a conclusion of the analysis, the separation criteria for the divisions involved in the safe plant shutdown are obtained

A computer code SPHINCS for sodium fire safety evaluation

International Nuclear Information System (INIS)

Yamaguchi, Akira

2000-01-01

A computer code SPHINCS solves coupled phenomena of thermal-hydraulics and sodium fire based on a multi-zone model. It deals with arbitrary number of rooms each of which is connected mutually by doorway and penetrations. With regard to the combustion phenomena, flame sheet model and liquid droplet combustion model are used for pool and spray fire, respectively, with the chemical equilibrium model using Gibbs free energy minimization method. The chemical reaction and mass and heat transfer are solved interactively. A specific feature of SPHINCS is detailed representation of thermal-hydraulics of a sodium pool and a steel liner, which is placed on the floor to prevent sodium-concrete contact. The author analyzed a series of pool combustion experiments, in which gas and liner temperatures are measured in detail. It has been found that good agreement is obtained and the SPHINCS has been validated with regard to the pool combustion phenomena. Further research needs are identified for the pool spreading modeling considering thermal deformation of liner and measurement of pool fluidity property of a mixture of liquid sodium and reaction products. SPHINCS code is to be used mainly in the safety evaluation of the consequence of sodium fire accident of liquid metal cooled fast reactor. (author)

Safety in offshore engineering an academic course covering safety in offshore wind

NARCIS (Netherlands)

Cerda Salzmann, D.J.

2011-01-01

Offshore projects are known for their challenging conditions, generally leading to high risks. Therefore no offshore project can go without a continuous and extensive assessment on safety issues. The Delft University of Technology is currently developing a course "Safety in Offshore Engineering"

Analyzing the Risk of Fire in a Hospital Complex by “Fire Risk Assessment Method for Engineering”(FRAME

Directory of Open Access Journals (Sweden)

Sarsangi V.* MSc,

2016-08-01

Full Text Available Aims The occurrence of fire in residential buildings, commercial complexes and large and small industries cause physical, environmental and financial damages to many different communities. Fire safety in hospitals is sensitive and it is believed that the society takes the responsibility to care sick people. The goal of this study was to use Fire Risk Assessment Method for Engineering (FRAME in a hospital complex environment and assess the level of fire risks. Materials & Methods This descriptive study was conducted in Kashan Shahid Beheshti hospital in 2013. The FRAME is designed based on the empirical and scientific knowledge and experiment and have acceptable reliability for assessing the building fire risk. Excel software was used to calculate the risk level and finally fire risk (R was calculated separately for different units. Findings Calculated Rs were less than 1for health, autoclave, office of nursing and infection control units. R1s were greater than 1 for all units. R2s were less than 1 for office of nursing and infection control units. Conclusion FRAME is an acceptable tool for assessing the risk of fire in buildings and the fire risk is high in Shahid Beheshti Hospital Complex of Kashan and damages can be intolerable in the case of fire.

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

1979-01-01

The Safety Guide gives design and some operational guidance for protection from fire and fire-related explosions in nuclear power plants (NPP). It confines itself to fire protection of items important to safety, leaving the aspects of fire protection not related to safety in NPP to be decided upon the basis of the national practices and regulations

A fire hazard analysis at the Ignalina nuclear power plant

International Nuclear Information System (INIS)

Joerud, F.; Magnusson, T.

1998-01-01

The fire hazard analysis (FHA) of the Ignalina Nuclear Power Plant (INPP) Unit no.1 was initiated during 1997 and is estimated to finalise in summer 1998. The reason for starting a FHA was a recommendation in the Safety Analysis Report and its review to prioritise a systematic FHA. Fire protection improvements had earlier been based on engineering assessments, but further improvements required a systematic FHA. It is also required by the regulator for licensing of unit no.1. In preparation of the analysis it was decided to perform a deterministic FHA to fulfil the requirements in the IAEA draft of a Safety Practice ''Preparation of Fire Hazard Analyses for Nuclear Power Plants''. As a supporting document the United States Department of Energy Reactor Core Protection Evaluation Methodology for Fires at RBMK and WWER Nuclear Power Plants (RCPEM) was agreed to be used. The assistance of the project is performed as a bilateral activity between Sweden and UK. The project management is the responsibility of the INPP. In order to transfer knowledge to the INPP project group, training activities are arranged by the western team. The project will be documented as a safety case. The project consists of parties from INPP, Sweden, UK and Russia which makes the project very dependent of good communication procedures. The most difficult problems is except from the problems with translation, the problems with different standards and lack of testing protocols of the fire protection installations and problems to set the right level of screening criteria. There is also the new dimension of making it possible to take credit for the fire brigade in the safety case, which can bring the project into difficulties. The most interesting challenges for the project are to set the most sensible safety levels in the screening phase, to handle the huge volume of rooms for survey and screening, to maintain the good exchange of fire- and nuclear safety information between all the parties involved

New engineering safety factors for Loviisa NPP core calculations

Energy Technology Data Exchange (ETDEWEB)

Kuopanportti, Jaakko; Saarinen, Simo; Lahtinen, Tuukka; Ekstroem, Karoliina [Fortum Power and Heat Ltd., Fortum (Finland)

2017-09-15

In Loviisa NPP, there are two limiting thermal margins called the enthalpy rise margin and the linear heat rate margin that are monitored during normal operation. Engineering safety factors are applied in determination of both of these factors. The factors take into account the effect of various manufacturing tolerances, impact of the irradiation and simulation uncertainties on the local heat rate and on the enthalpy of the coolant. The engineering factors were re-evaluated during 2015 and the factors were approved by the Finnish radiation and nuclear safety authority in 2016. The re-evaluation was performed by considering all of the identified phenomena that affect the local heat rate or the enthalpy of the coolant. This paper summarizes the work that was performed during the re-evaluation of the engineering safety factors and presents the results for each uncertainty component. The new engineering safety factors are 1.115 for the linear heat rate and 1.100 for the enthalpy rise margin when the old factors were 1.12 and 1.16, respectively. The new factors improve the fuel economy by about 1%.

The economics of fire protection

CERN Document Server

Ramachandran, Ganapathy

2003-01-01

This important new book, the first of its kind in the fire safety field, discusses the economic problems faced by decision-makers in the areas of fire safety and fire precautions. The author considers the theoretical aspects of cost-benefit analysis and other relevant economic problems with practical applications to fire protection systems. Clear examples are included to illustrate these techniques in action. The work covers: * the performance and effectiveness of passive fire protection measures such as structural fire resistance and means of escape facilities, and active systems such as sprinklers and detectors * the importance of educating for better understanding and implementation of fire prevention through publicity campaigns and fire brigade operations * cost-benefit analysis of fire protection measures and their combinations, taking into account trade-offs between these measures. The book is essential reading for consultants and academics in construction management, economics and fire safety, as well ...

FIRE HAZARDS ANALYSIS - BUSTED BUTTE

International Nuclear Information System (INIS)

Longwell, R.; Keifer, J.; Goodin, S.

2001-01-01

The purpose of this fire hazards analysis (FHA) is to assess the risk from fire within individual fire areas at the Busted Butte Test Facility and to ascertain whether the DOE fire safety objectives are met. The objective, identified in DOE Order 420.1, Section 4.2, is to establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: (1) The occurrence of a fire related event. (2) A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees. (3) Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards. (4) Property losses from a fire and related events exceeding limits established by DOE. Critical process controls and safety class systems being damaged as a result of a fire and related events

Fire Risk Assessment in Germany

International Nuclear Information System (INIS)

Berg, H. P.

2000-01-01

Quantitative fire risk assessment can serve as an additional tool to assess the safety level of a nuclear power plant (NPP) and to set priorities for fire protection improvement measures. The recommended approach to be applied within periodic safety reviews of NPPs in Germany starts with a screening process providing critical fire zones in which a fully developed fire has the potential to both cause an initiating event and impair the function of at least one component or system critical to safety. The second step is to perform a quantitative analysis using a standard event tree has been developed with elements for fire initiation, ventilation of the room, fire detection, fire suppression, and fire propagation. In a final step, the fire induced frequency of initiating events, the main contributors and the calculated hazard state frequency for the fire event are determined. Results of the first quantitative fire risk studies performed in Germany are reported. (author)

Definitions of engineered safety features and related features for nuclear power plants

International Nuclear Information System (INIS)

1986-01-01

In light water moderated, light water cooled nuclear power plants, definitions are given of engineered safety features which are designed to suppress or prevent dispersion of radioactive materials due to damage etc. of fuel at the times of power plant failures, and of related features which are designed to actuate or operate the engineered safety features. Contents are the following: scope of engineered safety features and of related features; classification of engineered safety features (direct systems and indirect systems) and of related features (auxiliaries, emergency power supply, and protective means). (Mori, K.)

Test Plan to Assess Fire Effects on the Function of an Engineered Surface Barrier

International Nuclear Information System (INIS)

Ward, Anderson L.; Berlin, Gregory T.; Cammann, Jerry W.; Leary, Kevin D.; Link, Steven O.

2008-01-01

Wildfire is a frequent perturbation in shrub steppe ecosystems, altering the flora, fauna, atmosphere, and soil of these systems. Research on the fire effects has focused mostly on natural ecosystems with essentially no attention on engineered systems like surface barriers. The scope of the project is to use a simulated wildfire to induce changes in an engineered surface barrier and document the effects on barrier performance. The main objective is to quantify the effects of burning and the resulting post-fire conditions on alterations in soil physical properties; hydrologic response, particularly the water balance; geochemical properties; and biological properties. A secondary objective is to use the lessons learned to maximize fire protection in the design of long-term monitoring systems based on electronic sensors. A simulated wildfire will be initiated, controlled and monitored at the 200-BP-1 barrier in collaboration with the Hanford Fire Department during the fall of 2008. The north half of the barrier will be divided into nine 12 x 12 m plots, each of which will be randomly assigned a fuel load of 2 kg m-2 or 4 kg m-2. Each plot will be ignited around the perimeter and flames allowed to carry to the centre. Any remaining unburned vegetation will be manually burned off using a drip torch. Progress of the fire and its effects will be monitored using point measurements of thermal, hydrologic, and biotic variables. Three measures of fire intensity will be used to characterize fire behavior: (1) flame height, (2) the maximum temperature at three vertical profile levels, and (3) total duration of elevated temperature at these levels. Pre-burn plant information, including species diversity, plant height, and canopy diameter will be measured on shrubs from the plots to be burned and from control plots at the McGee ranch. General assessments of shrub survival, recovery, and recruitment will be made after the fire. Near-surface soil samples will be collected pre- and

Test Plan to Assess Fire Effects on the Function of an Engineered Surface Barrier

Energy Technology Data Exchange (ETDEWEB)

Ward, Anderson L.; Berlin, Gregory T.; Cammann, Jerry W.; Leary, Kevin D.; Link, Steven O.

2008-09-29

Wildfire is a frequent perturbation in shrub steppe ecosystems, altering the flora, fauna, atmosphere, and soil of these systems. Research on the fire effects has focused mostly on natural ecosystems with essentially no attention on engineered systems like surface barriers. The scope of the project is to use a simulated wildfire to induce changes in an engineered surface barrier and document the effects on barrier performance. The main objective is to quantify the effects of burning and the resulting post-fire conditions on alterations in soil physical properties; hydrologic response, particularly the water balance; geochemical properties; and biological properties. A secondary objective is to use the lessons learned to maximize fire protection in the design of long-term monitoring systems based on electronic sensors. A simulated wildfire will be initiated, controlled and monitored at the 200-BP-1 barrier in collaboration with the Hanford Fire Department during the fall of 2008. The north half of the barrier will be divided into nine 12 x 12 m plots, each of which will be randomly assigned a fuel load of 2 kg m-2 or 4 kg m-2. Each plot will be ignited around the perimeter and flames allowed to carry to the centre. Any remaining unburned vegetation will be manually burned off using a drip torch. Progress of the fire and its effects will be monitored using point measurements of thermal, hydrologic, and biotic variables. Three measures of fire intensity will be used to characterize fire behavior: (1) flame height, (2) the maximum temperature at three vertical profile levels, and (3) total duration of elevated temperature at these levels. Pre-burn plant information, including species diversity, plant height, and canopy diameter will be measured on shrubs from the plots to be burned and from control plots at the McGee ranch. General assessments of shrub survival, recovery, and recruitment will be made after the fire. Near-surface soil samples will be collected pre- and

Systems engineered health and safety criteria for safety analysis reports

International Nuclear Information System (INIS)

Beitel, G.A.; Morcos, N.

1993-01-01

The world of safety analysis is filled with ambiguous words: codes and standards, consequences and risks, hazard and accident, and health and safety. These words have been subject to disparate interpretations by safety analysis report (SAR) writers, readers, and users. open-quotes Principal health and safety criteriaclose quotes has been one of the most frequently misused phrases; rarely is it used consistently or effectively. This paper offers an easily understood definition for open-quotes principal health and safety criteriaclose quotes and uses systems engineering to convert an otherwise mysterious topic into the primary means of producing an integrated SAR. This paper is based on SARs being written for environmental restoration and waste management activities for the U.S. Department of Energy (DOE). Requirements for these SARs are prescribed in DOE Order 5480-23, open-quotes Nuclear Safety Analysis Reports.close quotes

Fire fighting. Measures to guarantee the safety of the radioactive installations

International Nuclear Information System (INIS)

Orta Aguilera, R.

1993-01-01

The work relates the incidence of the aspects related to the fire prevention and fighting as well as the activities of rescue and saving in the radioactive facilities, with the objective of guaranteeing a strict safety regime of all installations along the country so as to reduce to the minimum the risk for the personnel, the population and the environment

Combining engineering and data-driven approaches: Development of a generic fire risk model facilitating calibration

DEFF Research Database (Denmark)

De Sanctis, G.; Fischer, K.; Kohler, J.

2014-01-01

Fire risk models support decision making for engineering problems under the consistent consideration of the associated uncertainties. Empirical approaches can be used for cost-benefit studies when enough data about the decision problem are available. But often the empirical approaches...... a generic risk model that is calibrated to observed fire loss data. Generic risk models assess the risk of buildings based on specific risk indicators and support risk assessment at a portfolio level. After an introduction to the principles of generic risk assessment, the focus of the present paper...... are not detailed enough. Engineering risk models, on the other hand, may be detailed but typically involve assumptions that may result in a biased risk assessment and make a cost-benefit study problematic. In two related papers it is shown how engineering and data-driven modeling can be combined by developing...

Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

International Nuclear Information System (INIS)

Dey, M.K.

1998-01-01

This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

International Nuclear Information System (INIS)

Dey, M.K.

2000-01-01

This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

Passive fire protection role and evolutions

Energy Technology Data Exchange (ETDEWEB)

Cerosky, Tristan [NUVIA (France); Perdrix, Johan [NUVIA Protection (France)

2015-12-15

Major incidents associated with nuclear power plants often invoke a re-examination of key safety barriers. Fire hazard, in particular, is a key concern for safe operation of nuclear power plants given its propensity to damage safety systems which could ultimately lead to radioactive release into the atmosphere. In the recent past, events such as the Fukushima disaster have led to an industry-wide push to improve nuclear safety arrangements. As part of these measures, upgrading of fire safety systems has received significant attention. In addition to the inherent intricacies associated with such a complex undertaking, factors such as frequent changes in the national and European fire regulations also require due attention while formulating a fire protection strategy. This paper will highlight some salient aspects underpinning an effective fire protection strategy. This will involve: A) A comprehensive introduction to the different aspects of fire safety (namely prevention, containment and mitigation) supported by a review of the development of the RCC-I from 1993 to 1997 editions and the ETC-F (AFCEN codes used by EDF in France). B) Development of the fire risk analysis methodology and the different functions of passive fire protection within this method involving confinement and protection of safety-related equipment. C) A review of the benefits of an effective passive fire protection strategy, alongside other arrangements (such as active fire protection) to a nuclear operator in term of safety and cost savings. It is expected that the paper will provide nuclear operators useful guidelines for strengthening existing fire protection systems.

A deterministric and probabilistric model for oilspill fires in nuclear power plants

International Nuclear Information System (INIS)

Karlsson, B.

1988-03-01

A deterministic and probabilistic model for oilspill fires in nuclear power plant compartments has been developed. It's objective is to predict whether certain components in the compartment will cease to function as a result of the fire and to give the probability of failure. Results are presented for several scenarios in two compartments. The model has been implimented in the computer code OSFIC, a tool for safety engineers to compare various component configurations in different compartments. (author)

Structural fire resistance experimental research priority needs of U.S. industry

CERN Document Server

Almand, Kathleen H

2012-01-01

Structural Fire Resistance Experimental Research – Priority Needs of U.S. Industry provides a synthesis of stakeholder input to a prioritized agenda for research at the National Fire Research Laboratory (NFRL) at the National Institute of Standards and Technology (NIST) designed to accelerate the implementation of performance-based fire engineering for structures. The NFRL presents a broad range of unanswered questions regarding the performance of real structures in fire conditions, and informs performance-based design methods and standards in this field. The authors conducted a comprehensive literature review of large-scale structural fire testing and compiled research needs from a variety of sources. The book addresses major issues of broad concern in the fire community, such as real fire exposure and structural response, composite floor system performance, enhancing modeling performance, and understanding the embedded safety features in design methods. It concludes with a prioritized set of research reco...

Validation study of computer code SPHINCS for sodium fire safety evaluation of fast reactor

International Nuclear Information System (INIS)

Yamaguchi, Akira; Tajima, Yuji

2003-01-01

A computer code SPHINCS solves coupled phenomena of thermal hydraulics and sodium fire based on a multi-zone model. It deals with an arbitrary number of rooms, each of which is connected mutually by doorways and penetrations. With regard to the combustion phenomena, a flame sheet model and a liquid droplet combustion model are used for pool and spray fires, respectively, with the chemical equilibrium model based on the Gibbs free energy minimization method. The chemical reaction and mass and heat transfer are solved interactively. A specific feature of SPHINCS is detailed representation of thermalhydraulics of a sodium pool and a steel liner, which is placed on the floor to prevent sodium-concrete contact. The authors analyzed a series of pool combustion experiments, in which gas and liner temperatures are measured in detail. It has been found that good agreement is obtained and the SPHINCS code has been validated with regard to pool combustion phenomena. Further research needs are identified for pool spreading modeling considering thermal deformation of steel liner and measurement of pool fluidity property as a mixture of liquid sodium and reaction products. The SPHINCS code is to be used mainly in the safety evaluation of the consequence of a sodium fire accident in a liquid metal cooled fast reactor as well as fire safety analysis in general

Fire Safety Consideration in the Pre-conceptual Design State of Pyro-Facillity

Energy Technology Data Exchange (ETDEWEB)

Jeon, Hong Rae; Seo, Seok Jun; Lee, Hyo Jik [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The government, in order to solve this problem, has organized a public engagement committee and is searching for a solution. To use sustainable nuclear energy, our country is also pursuing research and development of fast breeder reactor and pyroprocessing technology in accordance with the international movement of spent fuel recycling and efforts towards nuclear non-proliferation which is centered on the development and demonstration of recycling spent fuel and fast breeder reactors. Pyro-facility has different features with nuclear power plant. In the pyroprocess, chemical and electrochemical separation were took place in the hot cells and material at risk (MAR) is distributed in many working areas. In this paper, we conducted the fire modeling of hot cells to see the stability of pyrophoric materials which is considered as one of the potential hazardous materials in the main process cell. Based on modeling results, consideration of fire safety pyrofacility will be discussed. We performed preliminary hazard analysis for pyrofacility and summarized potential fire hazard. Pyrophoric material fire is the dominant hazard in the main process hot cell and fire modeling of cable tray in the cell was analyzed to see the stability of pyrophoric materials. Analysis results clearly shows that pyrophoric materials are prone to be affected.

Analysis Evacuation Route for KM Zahro Express on Fire Condition using Agent Based Modeling and Fire Dynamics Simulatior

Directory of Open Access Journals (Sweden)

Trika Pitana

2017-09-01

Full Text Available Safety is the thing that needs to be preferred by users of transport, passengers should also understand about safety procedures and evacuation procedures in the means of transport. There have been many accidents that happen in the world of transport, particularly in the shipping world, from 2010 to 2016 is no more than 50 accidents of ships in accordance with the cause recorded by KNKT (Komisi Nasional Keselamatan Transportasi. On this research was discussed the evacuation time on the ship KM Zahro express that occurred earlier in the year 2017 in the Kepulauan Seribu, DKI Jakarta. Almost all passenger dead caused by fire from power source in engine room. This thesis will explaine about evacuation time and dangers from fire that interfere the process of evacuation. The methods used are Agent Based Modeling and Simulation (ABMS and Fire Dynamics Simulator (FDS for modeling fire simulation. Agent-Based Modeling software (pathfinder and Fire Dynamics Simulator software (pyrosim are used to calculate time evacuation in normal condition and fire condition of KM Zahro Express. Agent-Based Modeling and Simulator (ABMS is a modeling method that aims to model complex problems based on real cases. Agent-Based Modeling and Simulator (ABMS is designed to model a place that has a seat, path, exit door, humans, and others. Pyrosim is a graphical user interface for the Fire Dynamics Simulator (FDS. FDS models can predict smoke, temperature, carbon monoxide, and other substances during fires.  In this case the existing models can be used to plan and prepare an emergency if unwanted things happen. As well as using basic rules which refer to the Safety Of Life At Sea (SOLAS and International Maritime Organization (IMO. Result of Evacuation simulation calculation on emergency conditions (two rear exit doors will be closed that match at actually condition is 29,783 minutes (respon is not taken in this simulation, calculation results obtained from simulation of

Fire Engine Support and On-scene Time in Prehospital Stroke Care - A Prospective Observational Study.

Science.gov (United States)

Puolakka, Tuukka; Väyrynen, Taneli; Erkkilä, Elja-Pekka; Kuisma, Markku

2016-06-01

Introduction On-scene time (OST) previously has been shown to be a significant component of Emergency Medical Services' (EMS') operational delay in acute stroke. Since stroke patients are managed routinely by two-person ambulance crews, increasing the number of personnel available on the scene is a possible method to improve their performance. Hypothesis Using fire engine crews to support ambulances on the scene in acute stroke is hypothesized to be associated with a shorter OST. All patients transported to hospital as thrombolysis candidates during a one-year study period were registered by the ambulance crews using a case report form that included patient characteristics and operational EMS data. Seventy-seven patients (41 [53%] male; mean age of 68.9 years [SD=15]; mean Glasgow Coma Score [GCS] of 15 points [IQR=14-15]) were eligible for the study. Forty-five cases were managed by ambulance and fire engine crews together and 32 by the ambulance crews alone. The median ambulance response time was seven minutes (IQR=5-10) and the fire engine response time was six minutes (IQR=5-8). The number of EMS personnel on the scene was six (IQR=5-7) and two (IQR=2-2), and the OST was 21 minutes (IQR=18-26) and 24 minutes (IQR=20-32; P =.073) for the groups, respectively. In a following regression analysis, using stroke as the dispatch code was the only variable associated with short (engine crews to support ambulances in acute stroke care was not associated with a shorter on-scene stay when compared to standard management by two-person ambulance crews alone. Using stroke as the dispatch code was the only variable that was associated independently with a short OST. Puolakka T , Väyrynen T , Erkkilä E-P , Kuisma M . Fire engine support and on-scene time in prehospital stroke care - a prospective observational study. Prehosp Disaster Med. 2016;31(3):278-281.

Specialists' meeting on sodium fires

International Nuclear Information System (INIS)

Kozlov, F.A.; Kuznetsova, R.I.

1989-01-01

The four sessions of the meeting covered the following topics: 1. general approach to fast reactor safety, standards of fire safety, maximum design basis accidents for sodium leaks and fires, status of sodium fires in different countries; 2. physical and chemical processes during combustion of sodium and its interaction with structural and technological materials and methods for structural protection; 3. methods of sodium fires extinguishing and measures for localizing aerosol combustion products, organization of fire fighting procedures, instruction and training of fire personnel; 4. elimination of the consequences of sodium fires

Specialists' meeting on sodium fires

Energy Technology Data Exchange (ETDEWEB)

Kozlov, F A; Kuznetsova, R I [eds.

1989-07-01

The four sessions of the meeting covered the following topics: 1. general approach to fast reactor safety, standards of fire safety, maximum design basis accidents for sodium leaks and fires, status of sodium fires in different countries; 2. physical and chemical processes during combustion of sodium and its interaction with structural and technological materials and methods for structural protection; 3. methods of sodium fires extinguishing and measures for localizing aerosol combustion products, organization of fire fighting procedures, instruction and training of fire personnel; 4. elimination of the consequences of sodium fires.

Safety test No. S-6, launch pad abort sequential test Phase II: solid propellant fire

International Nuclear Information System (INIS)

Snow, E.C.

1975-08-01

In preparation for the Lincoln Laboratory's LES 8/9 space mission, a series of tests was performed to evaluate the nuclear safety capability of the Multi-Hundred Watt (MHW) Radioisotope Thermoelectric Generator (RTG) to be used to supply power for the satellite. One such safety test is Test No. S-6, Launch Pad Abort Sequential Test. The objective of this test was to subject the RTG and its components to the sequential environments characteristic of a catastrophic launch pad accident to evaluate their capability to contain the 238 PuO 2 fuel. This sequence of environments was to have consisted of the blast overpressure and fragments, followed by the fireball, low velocity impact on the launch pad, and solid propellant fire. The blast overpressure and fragments were subsequently eliminated from this sequence. The procedures and results of Phase II of Test S-6, Solid Propellant Fire are presented. In this phase of the test, a simulant Fuel Sphere Assembly (FSA) and a mockup of a damaged Heat Source Assembly (HSA) were subjected to single proximity solid propellant fires of approximately 10-min duration. Steel was introduced into both tests to simulate the effects of launch pad debris and the solid rocket motor (SRM) casing that might be present in the fire zone. (TFD)

Do Undergraduate Engineering Faculty Include Occupational and Public Health and Safety in the Engineering Curriculum?

Science.gov (United States)

Farwell, Dianna; And Others

1995-01-01

The purpose of this study was to determine whether and, if so, why engineering faculty include occupational and public health and safety in their undergraduate engineering courses. Data were collected from 157 undergraduate engineering faculty from 65 colleges of engineering in the United States. (LZ)

A consideration of hazards, earthquakes, aircraft crashes, explosions and fires in the safety of laboratories and plants

International Nuclear Information System (INIS)

Doumenc, A.; Faure, J.; Mohammadioun, B.; Jacquet, P.

1987-03-01

Although laboratories and plants differ from nuclear reactors both in their characteristics and sitings, safety measures developed for the hazards of earthquakes, aircraft crashes, explosions and fires are very similar. These measures provide a satisfactory level of safety for these installations [fr

Laser-induced incandescence measurements in a fired diesel engine at 3 kHz

Science.gov (United States)

Boxx, I. G.; Heinold, O.; Geigle, K. P.

2015-01-01

Laser-induced incandescence (LII) was performed at 3 kHz in an optically accessible cylinder of a fired diesel engine using a commercially available diode-pumped solid-state laser and an intensified CMOS camera. The resulting images, acquired every 3° of crank angle, enabled the spatiotemporal tracking of soot structures during the expansion/exhaust stroke of the engine cycle. The image sequences demonstrate that soot tends to form in thin sheets that propagate and interact with the in-cylinder flow. These sheets tend to align parallel to the central axis of the cylinder and are frequently wrapped into conical spirals by aerodynamic swirl. Most of the soot is observed well away from the cylinder walls. Quantitative soot measurements were beyond the scope of this study but the results demonstrate the practical utility of using kHz-rate LII to acquire ensemble-averaged statistical data with high crank angle resolution over a complete engine cycle. Based on semi-quantitative measures of soot distribution, it was possible to identify soot dynamics related to incomplete charge exchange. This study shows that long-duration, multi-kHz acquisition rate LII measurements are viable in a fired diesel engine with currently available laser and camera technology, albeit only in the expansion and exhaust phase of the cycle at present. Furthermore, such measurements yield useful insight into soot dynamics and therefore constitute an important new tool for the development and optimization of diesel engine technology.

Safety risk management of underground engineering in China: Progress, challenges and strategies

Directory of Open Access Journals (Sweden)

Qihu Qian

2016-08-01

Full Text Available Underground construction in China is featured by large scale, high speed, long construction period, complex operation and frustrating situations regarding project safety. Various accidents have been reported from time to time, resulting in serious social impact and huge economic loss. This paper presents the main progress in the safety risk management of underground engineering in China over the last decade, i.e. (1 establishment of laws and regulations for safety risk management of underground engineering, (2 implementation of the safety risk management plan, (3 establishment of decision support system for risk management and early-warning based on information technology, and (4 strengthening the study on safety risk management, prediction and prevention. Based on the analysis of the typical accidents in China in the last decade, the new challenges in the safety risk management for underground engineering are identified as follows: (1 control of unsafe human behaviors; (2 technological innovation in safety risk management; and (3 design of safety risk management regulations. Finally, the strategies for safety risk management of underground engineering in China are proposed in six aspects, i.e. the safety risk management system and policy, law, administration, economy, education and technology.

Safety analysis of the existing 804 and 845 firing facilities

International Nuclear Information System (INIS)

Odell, B.N.

1986-01-01

A safety analysis was performed to determine if normal operations and/or potential accidents at the 804 and 845 Firing Facilities at Site 300 could present undue hazards to the general public, peronnel at Site 300, or have an adverse effect on the environment. The normal operation and credible accident that might have an effect on these facilities or have off-site consequence were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exception was explosives. Since this hazard has the potential for causing significant on-site and minimum off-site consequences, Bunkers 804 and 845 have been classified as moderate hazard facilties per DOE Order 5481.1A. This safety analysis concluded that the operation at these facilities will present no undue risk to the health and safety of LLNL employees or the public

Critical firing and misfiring boundary in a spark ignition methanol engine during cold start based on single cycle fuel injection

International Nuclear Information System (INIS)

Li, Zhaohui; Gong, Changming; Qu, Xiang; Liu, Fenghua; Sun, Jingzhen; Wang, Kang; Li, Yufeng

2015-01-01

The influence of the mass of methanol injected per cycle, ambient temperature, injection and ignition timing, preheating methods, and supplying additional liquefied petroleum gas (LPG) injection into the intake manifold on the critical firing and misfiring boundary of an electronically injection controlled spark ignition (SI) methanol engine during cold start were investigated experimentally based on a single cycle fuel injection with cycle-by-cycle control strategy. The critical firing and misfiring boundary was restricted by all parameters. For ambient temperatures below 16 °C, methanol engines must use auxiliary start-aids during cold start. Optimal control of the methanol injection and ignition timing can realize ideal next cycle firing combustion after injection. Resistance wire and glow plug preheating can provide critical firing down to ambient temperatures of 5 °C and 0 °C, respectively. Using an additional LPG injection into the intake manifold can provide critical firing down to an ambient temperature of −13 °C during cold start. As the ambient temperature decreases, the optimal angle difference between methanol injection timing and LPG injection timing for critical firing of a methanol engine increases rapidly during cold start. - Highlights: • A single cycle fuel injection and cycle-by-cycle control strategy are used to study. • In-cylinder pressure and instantaneous speed were used to determine firing boundary. • For the ambient temperatures below 16 °C, an auxiliary start-aids must be used. • A preheating and additional LPG were used to expand critical firing boundary. • Additional LPG can result in critical firing down to ambient temperature of −13 °C

Analysis of sodium pool fire in SFEF for assessing the limiting pool fire

International Nuclear Information System (INIS)

Mangarjuna Rao, P.; Ramesh, S.S.; Nashine, B.K.; Kasinathan, N.; Chellapandi, P.

2011-01-01

Accidental sodium leaks and resultant sodium fires in Liquid Metal Fast Breeder Reactor (LMFBR) systems can create a threat to the safe operation of the plant. To avoid this defence-in depth approach is implemented from the design stage of reactor itself. Rapid detection of sodium leak and fast dumping of the sodium into the storage tank of a defective circuit, leak collection trays, adequate lining of load bearing structural concrete and extinguishment of the sodium fire are the important defensive measures in the design, construction and operation of a LMFBR for protection against sodium leaks and their resultant fires. Evaluation of sodium leak events and their consequences by conducting large scale engineering experiments is very essential for effective implementation of the above protection measures for sodium fire safety. For this purpose a Sodium Fire Experimental Facility (SFEF) is constructed at SED, IGCAR. SFEF is having an experimental hall of size 9 m x 6 m x 10 m with 540 m 3 volume and its design pressure is 50 kPa. It is a concrete structure and provided with SS 304 liner, which is fixed to the inside surfaces of walls, ceiling and floor. A leak tight door of size (1.8 m x 2.0 m) is provided to the experimental hall and the facility is provided with a sodium equipment hall and a control room. Experimental evaluation of sodium pool fire consequences is an important activity in the LMFBR sodium fire safety related studies. An experimental program has been planned for different types of sodium fire studies in SFEF. A prior to that numerical analysis have been carried out for enclosed sodium pool fires using SOFIRE-II sodium pool fire code for SFEF experimental hall configuration to evaluate the limiting pool fire. This paper brings out results of the analysis carried out for this purpose. Limiting pool fire of SFEF depends on the exposed surface area of the pool, amount of sodium in the pool, oxygen concentration and initial sodium temperature. Limiting

The French fire protection concept. Vulnerability analysis

International Nuclear Information System (INIS)

Kaercher, M.

1998-01-01

The French fire protection concept is based on a principle of three levels of defence in depth: fire prevention, fire containing and fire controlling. Fire prevention is based on arrangements which prevent the fire from starting or which make difficult for the fire to start. Fire containing is based on design measures so that the fire will have no impact on the safety of the installation. For fire controlling, equipment nad personnel are on duty in order to detect, to fight and to gain control over the fire as early as possible. The French fire protection concept gives priority to fire containing based on passive structural measures. All buildings containing safety equipment are divided into fire compartments (or fire areas) and fire cells (or fire zones). Basically, a compartment houses safety equipment belonging to one division (or train) so that the other division is always available to reach the plant safe shut down or to mitigate an accident. Because there is a large number of fire compartments and fire cells, deviations from the general principle can be observed. To this reason the RCC-I (Design and Construction Rules applicable for fire protection) requires to implement an assessment of the principle of division. This assessment is called vulnerability analysis. The vulnerability analysis is usually performed at the end of the project, before erection. It is also possible to perform a vulnerability analysis in an operating nuclear power plant in the scope of a fire safety upgrading programme. In the vulnerability analysis, the functional failure of all the equipment (except for those protected by a qualified fire barrier, designed or able to withstand the fire consequences) within the fire compartment or cell, where the fire breaks out, is postulated. The potential consequences for the plant safety are analysed

Accord on “Fire and Building Safety in Bangladesh”: A Breakthrough Agreement?

Directory of Open Access Journals (Sweden)

Zillur Rahman

2014-03-01

Full Text Available This discussion aims to review the emergence of the “Accord on Fire and Building Safety in Bangladesh” signed on May 13, 2013, and evaluate if it is an international agreement “breakthrough”. The Accord is signed not only by the global clothing brands and national garment unions but also by international trade union organizations, which is a new development. This raises a question: could this agreement set a new international negotiating precedence in industrial relations between transnational corporations and international trade union organizations? In Bangladesh, globalization has played an important role for booming garment industries. Yet, lack of workers’ rights, weak safety situations, and poor working conditions have continuously been reported. Local and international solidarity movements and garment workers’ welfare associations have been emphasizing workers’ rights and better and safer working environments in workplaces since the beginning of the 1990s. However, their voices were not highly considered even there were some initiatives. Following the ‘Rana Plaza’ garment factory building collapse in April 2013, one of the world’s worst industrial accidents, with more than 1,100 dead workers, some strong measures have been taken—one of these, signing the ‘Accord on Fire and Building Safety in Bangladesh’. This is a strong achievement of a long struggle to take collective action for improving the safety in garment factories in Bangladesh. Although the Accord is understood as a game changer or breakthrough in relation to national and international agreements, do we really know yet if it is a breakthrough or not when it comes to its implementation?

Games that "work": using computer games to teach alcohol-affected children about fire and street safety.

Science.gov (United States)

Coles, Claire D; Strickland, Dorothy C; Padgett, Lynne; Bellmoff, Lynnae

2007-01-01

Unintentional injuries are a leading cause of death and disability for children. Those with developmental disabilities, including children affected by prenatal alcohol exposure, are at highest risk for injuries. Although teaching safety skills is recommended to prevent injury, cognitive limitations and behavioral problems characteristic of children with fetal alcohol spectrum disorder make teaching these skills challenging for parents and teachers. In the current study, 32 children, ages 4-10, diagnosed with fetal alcohol syndrome (FAS) and partial FAS, learned fire and street safety through computer games that employed "virtual worlds" to teach recommended safety skills. Children were pretested on verbal knowledge of four safety elements for both fire and street safety conditions and then randomly assigned to one condition. After playing the game until mastery, children were retested verbally and asked to "generalize" their newly acquired skills in a behavioral context. They were retested after 1 week follow-up. Children showed significantly better knowledge of the game to which they were exposed, immediately and at follow-up, and the majority (72%) was able to generalize all four steps within a behavioral setting. Results suggested that this is a highly effective method for teaching safety skills to high-risk children who have learning difficulties.

Psychological Safety and Norm Clarity in Software Engineering Teams

OpenAIRE

Lenberg, Per; Feldt, Robert

2018-01-01

In the software engineering industry today, companies primarily conduct their work in teams. To increase organizational productivity, it is thus crucial to know the factors that affect team effectiveness. Two team-related concepts that have gained prominence lately are psychological safety and team norms. Still, few studies exist that explore these in a software engineering context. Therefore, with the aim of extending the knowledge of these concepts, we examined if psychological safety and t...

Environmental optimisation of natural gas fired engines - calculation of health externalities

Energy Technology Data Exchange (ETDEWEB)

Frohn, L.M.; Becker, T.; Christensen, Jesper; Hertel, O.; Silver, J.D.; Villadsen, H. (Aarhus Univ., National Environmental Research Institute, Dept. of Atmospheric Environment, Roskilde (Denmark)); Soees Hansen, M. (Aarhus Univ., National Environmental Research Institute, Dept. of Policy Analysis, Roskilde (Denmark)); Skou Andersen, M. (European Environment Agency, Copenhagen (Denmark))

2010-07-01

The measured emissions of WP1 of the project has been applied as input for model calculations with the EVA model system. The DEHM model which calculates the regional scale delta-concentrations has been further developed to handle the low signal to noise ratio of the delta-concentrations related to the small sources that the gas fired engines constitute. All combinations of engine settings and locations have been run as scenarios with the EVA system, however the results have been grouped into themes to investigate changes related to location as well as changes related to engine settings. New exposure-response relations have been implemented in the system related to the chemical components nitrogen dioxide, formaldehyde, ethene and propene. The choice of high-exposure location in the calculations has unfortunately turned out to be less optimal. The location at Store Valby has previously been applied in studies with the EVA system as a high-exposure site, however in previous applications, the emission sources have been large power plants with stack heights of around 150 meters. The height of the stack of the gas fired engines is only around 30 meters, and the consequence is that the emitted components reach the surface closer to the stack, thereby giving high exposure in an area located further to the southwest, where the population density is not as high as in central Copenhagen. In general the marginal health costs (in Euro pr kg) of carbon monoxide and formaldehyde emissions are very small. The emissions of formaldehyde are also small and the resulting costs for this component is therefore very small. The emission of carbon monoxide is much larger, however the small marginal cost makes the contribution to the total costs small, also for this component. The marginal health costs of nitrogen oxides and ethene emissions show little variation with engine scenario. However the general picture is that as the NO{sub x} emissions increase (either by increasing ignition

The aspects of fire safety at landfills

Directory of Open Access Journals (Sweden)

Aleshina Tat'yana Anatol'evna

2014-01-01

Full Text Available Starting with 2008 and till 2013 there have been alarm messages about fires occurring at landfill places in Russia. Landfill fires are especially dangerous as they emit dangerous fumes from the combustion of the wide range of materials within the landfill. Subsurface landfill fires, unlike typical fires, cannot be put out with water. The article includes the analysis of the sources and causes of conflagrations at landfills. There maintains the necessity to eliminate the reasons, which cause the fires. There are quantification indices of environmental, social and economic effects of fires at landfills all over Russia. Surface fires generally burn at relatively low temperatures and are characterized by the emission of dense white smoke and the products of incomplete combustion. The smoke includes irritating agents, such as organic acids and other compounds. Higher temperature fires can cause the breakdown of volatile compounds, which emit dense black smoke. Surface fires are classified as either accidental or deliberate. For the ecologic security there is a need in the execution of proper hygienic requirements to the content of the places as well as international recommendations. In addition to the burning and explosion hazards posed by landfill fires, smoke and other by-products of landfill fires also present a health risk to firefighters and others exposed to them. Smoke from landfill fires generally contains particulate matter (the products of incomplete combustion of the fuel source, which can aggravate pre-existing pulmonary conditions or cause respiratory distress and damage ecosystem. The monitoring of conducting preventive inflamings and transition to alternative, environment friendly methods of waste disposal is needed.

Effects of ship casualties on reactor safety and marine reactor design

International Nuclear Information System (INIS)

Agena, H.H.

1978-01-01

Ship casualties such as collision, grounding, fire and explosions, leakage and partial flooding may severely impair the safety of the nuclear reactor plant and result in nuclear hazards to the crew and the environment. Engineered safeguards are being discussed for protection against such consequences: manoeuvrability, structural (passive) collision and fire protection, protection against external fires and pressure waves, after heat transmission in case of a casualty, and after heat transmission out off the sunk wreck. Existing requirements will be discussed, shortly

Safety outcomes for engineering asset management organizations: Old problem with new solutions?

International Nuclear Information System (INIS)

Novak, Jeremy; Farr-Wharton, Ben; Brunetto, Yvonne; Shacklock, Kate; Brown, Kerry

2017-01-01

The issue of safety and longevity of engineering assets is of increasing importance because of their impact when disasters happen. This paper addresses a literature gap by examining the role of workplace relationships in employees' safety behaviour, and builds on the Resilience Engineering (RE) framework by examining some organisational culture factors affecting how employees behave. A Social Exchange framework is used to examine the impact of supervisor-employee relationships, employee commitment to safety practices, and the type of maintenance culture upon employees’ commitment to safety and safety outcomes. Survey data from 284 technical and engineering employees in engineering asset management organisations within Australia were analyzed using Structural Equation Modelling (SEM). Effective employee relationships with management and a proactive maintenance culture were associated with employee commitment to safety culture and safety outcomes. The findings provide empirical support for embedding an effective organisational culture focused on a proactive maintenance approach, along with ensuring employees are committed to safety processes, to ensure safety outcomes and also asset longevity. One study contribution is that good safety outcomes do not develop in a vacuum; instead they are built on effective workplace relationships. Therefore, SET helps to explain the forming of effective safety culture. - Highlights: • Effective workplace relationships with management positively affect organisational safety outcomes. • Supported maintenance cultures positively affect organisational safety outcomes. • Asset longevity requires strong focus on maintenance and safety embedded in the work cultures and everyday practices of employees.

Modeling for safety in a synthesis-centric systems engineering framework

NARCIS (Netherlands)

Markovski, J.; Mortel - Fronczak, van de J.M.; Ortmeier, F.; Daniel, P.

2012-01-01

The ever-increasing complexity of safety-critical systems puts high demands on safety assurance and certification. We focus on the development of control software, where safety) requirements engineering plays a crucial and delicate role. Nowadays, most of the safety features are ensured by the

49 CFR 193.2611 - Fire protection.

Science.gov (United States)

2010-10-01

... 49 Transportation 3 2010-10-01 2010-10-01 false Fire protection. 193.2611 Section 193.2611 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY...: FEDERAL SAFETY STANDARDS Maintenance § 193.2611 Fire protection. (a) Maintenance activities on fire...

Fire protection

International Nuclear Information System (INIS)

Janetzky, E.

1980-01-01

Safety and fire prevention measurements have to be treated like the activities developing, planning, construction and erection. Therefore it is necessary that these measurements have to be integrated into the activities mentioned above at an early stage in order to guarantee their effectiveness. With regard to fire accidents the statistics of the insurance companies concerned show that the damage caused increased in the last years mainly due to high concentration of material. Organization of fire prevention and fire fighting, reasons of fire break out, characteristics and behaviour of fire, smoke and fire detection, smoke and heat venting, fire extinguishers (portable and stationary), construction material in presence of fire, respiratory protection etc. will be discussed. (orig./RW)

Human and organization factors: engineering operating safety into offshore structures

International Nuclear Information System (INIS)

Bea, Robert G.

1998-01-01

History indicates clearly that the safety of offshore structures is determined primarily by the humans and organizations responsible for these structures during their design, construction, operation, maintenance, and decommissioning. If the safety of offshore structures is to be preserved and improved, then attention of engineers should focus on to how to improve the reliability of the offshore structure 'system,' including the people that come into contact with the structure during its life-cycle. This article reviews and discusss concepts and engineering approaches that can be used in such efforts. Two specific human factor issues are addressed: (1) real-time management of safety during operations, and (2) development of a Safety Management Assessment System to help improve the safety of offshore structures

Study of the Accident Environment During Sea Transport of Nuclear Material: Analysis of an Engine-room Fire on a Purpose-built Ship (invited paper)

International Nuclear Information System (INIS)

Yamamoto, K.; Kitamura, T.; Shibata, K.; Ouchi, Y.; Ito, T.; Hohnstreiter, G.F.; Pierce, J.D.; Koski, J.A.; Dukart, R.K.

2000-01-01

The programme goal was to show that the IAEA safe transport regulations adequately cover the thermal effects of an engine-room fire on plutonium transport packages stowed aboard a purpose-built ship. The packages are stored in transport containers located in a cargo hold of the ship. For this study, it was assumed that the packages in No 5 hold, adjacent to an engine-room, could be subject to heating due to a fire in the engine-room. The No 5 hold and the engine-room are separated by a water-filled bulkhead. This study addressed the heat transfer from an engine-room fire that could heat and evaporate water out of the water-filled bulkhead and the resulting temperature conditions around the packages and inside the packages near their elastometric seals. (author)

Patient safety - the role of human factors and systems engineering.

Science.gov (United States)

Carayon, Pascale; Wood, Kenneth E

2010-01-01

Patient safety is a global challenge that requires knowledge and skills in multiple areas, including human factors and systems engineering. In this chapter, numerous conceptual approaches and methods for analyzing, preventing and mitigating medical errors are described. Given the complexity of healthcare work systems and processes, we emphasize the need for increasing partnerships between the health sciences and human factors and systems engineering to improve patient safety. Those partnerships will be able to develop and implement the system redesigns that are necessary to improve healthcare work systems and processes for patient safety.

Patient Safety: The Role of Human Factors and Systems Engineering

Science.gov (United States)

Carayon, Pascale; Wood, Kenneth E.

2011-01-01

Patient safety is a global challenge that requires knowledge and skills in multiple areas, including human factors and systems engineering. In this chapter, numerous conceptual approaches and methods for analyzing, preventing and mitigating medical errors are described. Given the complexity of healthcare work systems and processes, we emphasize the need for increasing partnerships between the health sciences and human factors and systems engineering to improve patient safety. Those partnerships will be able to develop and implement the system redesigns that are necessary to improve healthcare work systems and processes for patient safety. PMID:20543237

Understanding safety and production risks in rail engineering planning and protection.

Science.gov (United States)

Wilson, John R; Ryan, Brendan; Schock, Alex; Ferreira, Pedro; Smith, Stuart; Pitsopoulos, Julia

2009-07-01

Much of the published human factors work on risk is to do with safety and within this is concerned with prediction and analysis of human error and with human reliability assessment. Less has been published on human factors contributions to understanding and managing project, business, engineering and other forms of risk and still less jointly assessing risk to do with broad issues of 'safety' and broad issues of 'production' or 'performance'. This paper contains a general commentary on human factors and assessment of risk of various kinds, in the context of the aims of ergonomics and concerns about being too risk averse. The paper then describes a specific project, in rail engineering, where the notion of a human factors case has been employed to analyse engineering functions and related human factors issues. A human factors issues register for potential system disturbances has been developed, prior to a human factors risk assessment, which jointly covers safety and production (engineering delivery) concerns. The paper concludes with a commentary on the potential relevance of a resilience engineering perspective to understanding rail engineering systems risk. Design, planning and management of complex systems will increasingly have to address the issue of making trade-offs between safety and production, and ergonomics should be central to this. The paper addresses the relevant issues and does so in an under-published domain - rail systems engineering work.

Surface Fire Hazards Analysis Technical Report-Constructor Facilities

International Nuclear Information System (INIS)

Flye, R.E.

2000-01-01

The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives identified in DOE Order 420.1, Change 2, Facility Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: The occurrence of a fire or related event; A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public, or the environment; Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; Property losses from a fire and related events exceeding defined limits established by DOE; and Critical process controls and safety class systems being damaged as a result of a fire and related events

Maintenance of civil engineering structures important to safety of Nuclear Power Plants

International Nuclear Information System (INIS)

2002-03-01

Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. This safety standard is written to specify the objectives and minimum requirements for the design of civil engineering buildings/structures that are to be fulfilled to provide adequate assurance for safety of nuclear installations in India

Happy 50th Birthday Smokey Bear! A Learning Kit about Forests and Fire Safety for Grades K-3.

Science.gov (United States)

Hall, Meryl

For over 50 years, the primary goal of Smokey Bear has been to introduce the forest fire prevention message to young children. This learning kit provides the K-3 teacher with activities and resources to help students learn about Smokey Bear and fire safety, about forests as habitats, and about what they can do to protect forests. Students are…

A fire risk analysis method for nuclear installations

Energy Technology Data Exchange (ETDEWEB)

Ormieres, Yannick; Lacoue, Jocelyne [Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES, SA2I, Fontenay-aux-Roses (France)

2013-07-01

A fire safety analysis (FSA) is requested to justify the adequacy of fire protection measures set by the operator of a nuclear facility. An IRSN document outlines a global process for such a comprehensive fire safety analysis and focuses on compliance with performance criteria for fire protection measures. These performance criteria are related to the vulnerability of targets to effects of fire, and not only based upon outside radiological consequences caused by a fire. In his FSA, the operator has to define the safety functions to be preserved in the case of a fire in order to be compliant with nuclear safety objectives. Then, the operator has to justify the adequacy of fire protection measures, defined according to defence in depth principles. One of the key points of the fire analysis is the assessment of possible fire scenarios in the facility. Given the large number of possible fire scenarios, it is then necessary to evaluate ''reference fires'' which are envelope of all possible fire scenarios and which are used by the operator for the design of fire protection measures. (orig.)

Fire safety in nuclear power stations

International Nuclear Information System (INIS)

Kench, R.L.

1988-01-01

This is the first of a three-part report on the fire hazards in nuclear power stations and some of the precautions necessary. This part lists the United Kingdom reactors, outlines how they work, the fuels used, the use of moderators and coolants and the control systems. Although the risk of fire is no higher than in fossil-fuel stations the consequences can be more serious. The radioactive materials used mean that there is biological shielding round the core, limitations on waste emissions allowed and limited access to some zones. Reliable shut-down systems are needed. Care in the use of water to fight fires must be exercised -it can act as a moderator and cause an otherwise safe core to go critical. The Wigner effect in graphite moderated reactors is explained. Fires in graphite can be extinguished by carbon dioxide. Argon, chlorine and sodium silicate can also be effective. In sodium cooled reactors fires can be allowed to burn themselves out, or TEC and argon could be used to extinguish the flame. (UK)

77 FR 32394 - Safety Zones: Catawba Island Club Fire Works, Catawba Island Club, Port Clinton, OH; Racing for...

Science.gov (United States)

2012-06-01

...[deg]51'18.70'' W (NAD 83). This safety zone will be enforced from 9:15 p.m. until 9:45 p.m. on May 27...[deg]51[min]18.70[sec] W (NAD 83). (2) Enforcement period. This safety zone will be enforced between 9...-AA00 Safety Zones: Catawba Island Club Fire Works, Catawba Island Club, Port Clinton, OH; Racing for...

Criticality safety engineering at the Savannah River Site - the 1990s

International Nuclear Information System (INIS)

Chandler, J.R.; Apperson, C.E. Jr.

1996-01-01

The privatization and downsizing effort that is ongoing within the U.S. Department of Energy (DOE) is requiring a change in the management of criticality safety engineering resources at the Savannah River Site (SRS). Downsizing affects the number of criticality engineers employed by the prime contractor, Westinghouse Savannah River Company (WSRC), and privatization affects the manner in which business is conducted. In the past, criticality engineers at the SRS have been part of the engineering organizations that support each facility handling fissile material. This practice led to different criticality safety engineering organizations dedicated to fuel fabrication activities, reactor loading and unloading activities, separation and waste management operations, and research and development

Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

Science.gov (United States)

Duarte, Alberto

2007-01-01

Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

Fire Risk Analysis and Optimization of Fire Prevention Management for Green Building Design and High Rise Buildings: Hong Kong Experience

Directory of Open Access Journals (Sweden)

Yau Albert

2014-12-01

Full Text Available There are many iconic high rise buildings in Hong Kong, for example, International Commercial Centre, International Financial Centre, etc. Fire safety issue in high rise buildings has been raised by local fire professionals in terms of occupant evacuation, means of fire-fighting by fire fighters, sprinkler systems to automatically put off fires in buildings, etc. Fire risk becomes an important issue in building fire safety because it relates to life safety of building occupants where they live and work in high rise buildings in Hong Kong. The aim of this research is to identify the fire risk for different types of high rise buildings in Hong Kong and to optimise the fire prevention management for those high rise buildings with higher level of fire risk and to validate the model and also to carry out the study of the conflict between the current fire safety building code and the current trend of green building design. Survey via the 7-point scale questionnaire was conducted through 50 participants and their responses were received and analysed via the statistical tool SPSS software computer program. A number of statistical methods of testing for significantly difference in samples were adopted to carry out the analysis of the data received. When the statistical analysis was completed, the results of the data analysis were validated by two Fire Safety Experts in this area of specialisation and also by quantitative fire risk analysis.

Experimental study of fire barriers preventing vertical fire spread in ETISs

Directory of Open Access Journals (Sweden)

Xin Huang

2013-11-01

Full Text Available In recent years, the external thermal insulation system (ETIS has been applied increasingly in a large amount of buildings for energy conservation purpose. However, the increase use of combustible insulation materials in the ETIS has raised serious fire safety problems. Fires involving this type of ETIS have caused severe damage and loss. In order to improve its fire safety, fire barriers were suggested to be installed. This paper introduces fire experiments that have been done to study the effects of fire barriers on preventing vertical fire spread along the ETIS. The experiments were performed according to BS 8414-1:2002 “Fire performance of external cladding systems – Part 1: Test method for non-loadbearing external cladding systems applied to the face of the building”. The test facility consists of a 9 m high wall. The fire sources were wood cribs with a fire size of 3 ± 0.5 MW. The insulation materials were expanded polystyrene foam (EPS. The fire barrier was a horizontal strip of rockwool with a width of 300 mm. Thermocouples were used to measure temperatures outside and inside the ETIS. A series of experiments with different fire scenarios were done: no fire barrier, two fire barriers and three fire barriers at different heights. Test results were compared. The results show that the ETIS using EPS without fire barriers almost burned out, while the ETIS with fire barriers performed well in preventing fire spread. The temperatures above the fire barrier were much lower than those below the fire barrier, and most of the insulation materials above the top fire barrier stayed in place.

Fire safety in atomic power plants

International Nuclear Information System (INIS)

Kench, R.L.; British Insurance

1988-01-01

The main reactor types are described briefly - Magnox, advanced gas cooled, pressurized water and fast reactors. Fire risks exist at fuel stores and spent fuel storage facilities. Simple fire prevention measures are suggested. Solid radioactive wastes can also be combustible. Various fire prevention measures for the different storage methods, eg compaction, are given. Gaseous and liquid wastes are also considered. The main types of reactor accident are described and the causes of four incidents - at Chernobyl, Windscale, Brownsferry and Three Mile Island, are examined. (U.K.)

30 CFR 77.306 - Fire protection.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fire protection. 77.306 Section 77.306 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY....306 Fire protection. Based on the need for fire protection measures in connection with the particular...

Supervisor's experiments on radiation safety trainings in school of engineering

International Nuclear Information System (INIS)

Nomura, Kiyoshi

2005-01-01

Radiation safety training courses in School of Engineering, The University of Tokyo, were introduced. The number of radiation workers and the usage of radiation and radioisotopes have been surveyed for past 14 years. The number of radiation workers in School of Engineering has increased due to the treatment of X-ray analysis of materials, recently. It is important for workers to understand the present situation of School of Engineering before the treatment of radiation and radioisotopes. What the supervisor should tell to radiation workers were presented herewith. The basic questionnaires after the lecture are effective for radiation safety trainings. (author)

System safety engineering in the development of advanced surface transportation vehicles

Science.gov (United States)

Arnzen, H. E.

1971-01-01

Applications of system safety engineering to the development of advanced surface transportation vehicles are described. As a pertinent example, the paper describes a safety engineering efforts tailored to the particular design and test requirements of the Tracked Air Cushion Research Vehicle (TACRV). The test results obtained from this unique research vehicle provide significant design data directly applicable to the development of future tracked air cushion vehicles that will carry passengers in comfort and safety at speeds up to 300 miles per hour.

A Comparison of the mechanical engineering and safety engineering student’s ICT attitudes at the Obuda University

Directory of Open Access Journals (Sweden)

Kiss Gabor

2016-01-01

Full Text Available Communication and technology are critical to education. However, using technology in education is not an easy task as communication barriers emerge. The aim of this research is to analyze the ICT attitudes from different faculties at the Obuda University that is between the mechanical engineering students and safety engineering students from the Donát Bánki Mechanical Safety Engineer Faculty. The students from these two groups will use different ICT tool at work after their graduation; the mechanical engineering students will work mostly with designer ICT tools, the safety engineering students will use security systems. It would be important to know whether instructors, when using ICT, have to follow different teaching methods and approaches in these two different groups or not. We measured the ICT attitude with a tool consisting of 23 items (Likert scaled. We worked with 361 students. The data analysis was performed with SPSS software using descriptive statistics and Mann-Whitney test. The results show both groups having the same positive ICT attitude however with one difference.

Management of fire and industrial safety - challenges during commissioning of a NPP

International Nuclear Information System (INIS)

Maiti, Subhaschandra; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

2006-01-01

Construction and commissioning period of NPP are reduced world over drastically by stringent schedule for financial and economic reasons. For meeting the schedule, commissioning of components and systems are started immediate after installation, while construction activities are continued in parallel at the same place. Parallel activities' and 'Time Constraint' have brought new challenges to 'Management of Fire and Industrial Safely' during commissioning. An innovative approach was used during such phase of commissioning of TAPP-3 and 4. This paper outlines challenges encountered during this phase and special approach and measures used to meet those challenges. This paper also outlines problems encountered during implementation of these measures and subsequent change in approach to ensure smooth and safe execution of activities. Primarily, challenges were conflicting requirements by various agencies to carryout commissioning in parallel with construction activities concurrently. Main challenges were related to fall hazard, chemical hazard, fire hazard, electrical safety, work in confined space, housekeeping problem. Moreover it was within exclusion zone of another operating plant, which added one more dimension to those challenges. Conventional Safely management approach was little short to resolve these challenges. Such challenges were envisaged; analyzed and innovative measures were arrived at. Along with conventional safely analysis like Job Safely or Hazard Analysis (JSA or JHA), Accident Analysis, Accident Trend Analysis, Fire Hazard Analysis (FHA), innovative method like 'Area-Job- Hazard Charting' and 'Ratio Analysis' were used to understand activity dependent time varying hazard scenarios. Based on this analysis, decision were taken to change various existing elements of safely management like safety organizations; standard operating procedures (SOP); emergency operating procedures (EOP); resource allocation, planning and scheduling; safely training; safely

Advances in safety countermeasures at the Tomari NPP of Hokkaido Electric Power on the basis of Fukushima Daiichi NPP accident. Fire protection and other advances

International Nuclear Information System (INIS)

Shibata, Taku; Dasai, Katsumi

2014-01-01

Fire protections for the nuclear power plants have been based on the fire laws and the conventional guide. After Fukushima Daiichi NPP accident, many safety countermeasures - also about Fire Protection - have been discussed in the Japanese authorities. This paper shows our present activities in the Tomari NPP about the fire protections from the view points of Fire Prevention, Fire Detection/Suppression Systems and Fire Protection, and other advances. (author)

Large fire scenarios in relation to sabotage of nuclear installations

International Nuclear Information System (INIS)

Contri, P.; Guerpinar, A.; ); Schneider, U.

2005-01-01

The analyses of sabotage scenarios carried out in recent years identified two major damaging mechanisms associated with such scenarios, namely: the mechanical interaction of solid bodies or pressure waves with the installations and the fire-related effects from burning substances. While the former effect may be addressed by available analytical tools developed for accidental scenarios, the latter deserves a new, specific engineering effort. In fact, all nuclear facilities are designed in relation to accidental fires; even so, they need to be assessed in relation to sabotage induced fire scenarios due to the special characteristics of such scenarios, not addressed by the current engineering practice for the design of nuclear installations. Conventional fire hazard analysis is based on the hypothesis of the presence of combustible materials in the buildings and limited number of contemporaneous sources of fire. In addition, conventional fire safety assessment relies upon the presence of mitigation measures and fire related operational procedures. In a sabotage event the validity of all these assumptions need to be checked and if the assumptions cannot be supported, then the analysis should be revised and other alternatives of protection should be developed. Also the implementation of emergency planning should be reviewed to take account of this concern. This paper collects state-of-the-art experience from some Countries, which represents the background information for the development of new IAEA documents in this field. The paper reviews how the current design practice for nuclear installations can cope with large fire scenarios caused by malevolent actions and provides recommendations to designers and operators on how to address these issues in a reasonable framework. (authors)

Fire safety regulations for nuclear power plants in Germany and the various dimensions of German KTA standardization activities. Is there a benefit today?

International Nuclear Information System (INIS)

Wittmann, R.

1998-01-01

In Germany the mandate for preparing nuclear safety standards is given to the KTA (Nuclear Safety Standards Commission) which has restrictive procedures to definitely ensure consensus principle. The KTA was up to now not in a position to approve comprehensive fire safety relevant standards, although its corresponding program is now 22 years old. KTA 2101.1 ''Basic Principles of Fire Protection in NPPs'' (12/85) is the only one published as valid safety standard. Drafts for 3 additional standards referring fire protection of structural elements, electrical and mechanical components as well as for rescue routes have been agreed upon in working groups, supervised and accepted by the responsible KTA subcommittee, but have not been approved by the full committee of the KTA up to now. Some of these drafts are already more than 5 years old. From the today's point of view the earliest possibility to have a comprehensive and actual set of fire relevant KTA standards will be in the second half of the year 1999. This would then be 24 years after the first KTA decision to start such a program. (author)

Nitrous Oxide/Paraffin Hybrid Rocket Engines

Science.gov (United States)

Zubrin, Robert; Snyder, Gary

2010-01-01

Nitrous oxide/paraffin (N2OP) hybrid rocket engines have been invented as alternatives to other rocket engines especially those that burn granular, rubbery solid fuels consisting largely of hydroxyl- terminated polybutadiene (HTPB). Originally intended for use in launching spacecraft, these engines would also be suitable for terrestrial use in rocket-assisted takeoff of small airplanes. The main novel features of these engines are (1) the use of reinforced paraffin as the fuel and (2) the use of nitrous oxide as the oxidizer. Hybrid (solid-fuel/fluid-oxidizer) rocket engines offer advantages of safety and simplicity over fluid-bipropellant (fluid-fuel/fluid-oxidizer) rocket en - gines, but the thrusts of HTPB-based hybrid rocket engines are limited by the low regression rates of the fuel grains. Paraffin used as a solid fuel has a regression rate about 4 times that of HTPB, but pure paraffin fuel grains soften when heated; hence, paraffin fuel grains can, potentially, slump during firing. In a hybrid engine of the present type, the paraffin is molded into a 3-volume-percent graphite sponge or similar carbon matrix, which supports the paraffin against slumping during firing. In addition, because the carbon matrix material burns along with the paraffin, engine performance is not appreciably degraded by use of the matrix.

Cooperation of the site and public fire and safety services in case of an incident

International Nuclear Information System (INIS)

Bauch, M.

1997-01-01

This report describes the cooperation between the site and the public fire and safety services in case of an incident. As an example, the measures and facilities of the Hoechst site of the Hoechst AG and the organisational and technical background are presented. (orig.) [de

Fires in rooms containing electrical components - incident planning, fire fighting tactics, risks

International Nuclear Information System (INIS)

Magnusson, Tommy; Ottosson, Jan; Lindskog, BertiI; Soederquist Bende, Evy; Eriksson, Fredrik; Haffling, Stefan

2006-12-01

On July 1, 2005 a fire occurred within an electrical switch room at Forsmark Nuclear Power Plant. At the evaluation of the incident it was identified that the pre-fire plans did not give sufficient information in order to make the appropriate decisions. Questions raised based on the incident are how decisions are made and orders are delegated with respect to the incident command, which fire fighting tactic should be used, which types of extinguishing media should be used, what are the risks with respect to safety of staff and safety of the reactor. Lessons learned from the fire at Forsmark were that pre-incident planning was at hand but the information was not sufficient to make the correct initial decisions that might be critical for life and property. One of the most crucial ingredients in all safety related work is to utilize previous experience in order to maintain a high degree of safety. Lessons learnt are also the foundation on which the ability to construct or create strong barriers against a certain fault phenomena, fault mechanism or type of initial event. In the case of nuclear processes, fire is considered as an important and critical initial event which has to be recognized in a number of cases in order to maintain a safe process. The likelihood for a fire to represent an initial event should not be underestimated and can therefore not be neglected, probabilistically or deterministically, unless the inherent safety systems can not control the event in an acceptable manner. Regardless of safety measures and lessons learnt from previous experiences in the construction and the operation of the nuclear facility, fires can occur. Previous experiences point out that process system, e.g. systems that are part of the turbine, are more frequently subject to fire incidents compared to ordinary safety systems. Fires in electrical components, often electrical cabinets, can be difficult to handle and to extinguish quickly. This report presents the background work

30 CFR 56.4202 - Fire hydrants.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fire hydrants. 56.4202 Section 56.4202 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL MINES Fire Prevention and Control...

30 CFR 57.4202 - Fire hydrants.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fire hydrants. 57.4202 Section 57.4202 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Fire Prevention and Control...

Behaviour of electrical cables under fire conditions

International Nuclear Information System (INIS)

Bertrand, R.; Chaussard, M.; Gonzalez, R.; Lacoue, J.; Mattei, J.M.; Such, J.M.

2002-01-01

A Fire Probabilistic Safety Assessment - called the Fire PSA - is being carried out by the French Institute of Radiological Protection and Nuclear Safety (IPSN) to be used in the framework of the safety assessment of operating 900 MWe PWRs. The aim of this study is to evaluate the core damage conditional probability which could result from a fire. A fire can induce unavailability of safety equipment, notably damaging electrical cables introducing a significant risk contributor. The purpose of this paper is to present the electrical cable fire tests carried out by IPSN to identify the failure modes and to determine the cable damage criteria. The impact of each kind of cable failure mode and the methodology used to estimate the conditional probability of a failure mode when cable damage occurred is also discussed. (orig.) [de

Radiological protection. Responsibility of the Safety Engineering Company

International Nuclear Information System (INIS)

Netto, A.L.

1987-01-01

This subject takes care of the Safety Engineering at the Radiologic Protection area on the X and Gama Rays Services. It mainly emphasis the case of that companies that, due do not have proper X and Gama Rays Services utilize partime task force on this area, but answer themselves for the safety of their employees in case of any accident occurence. (author) [pt

Human factors and systems engineering approach to patient safety for radiotherapy.

Science.gov (United States)

Rivera, A Joy; Karsh, Ben-Tzion

2008-01-01

The traditional approach to solving patient safety problems in healthcare is to blame the last person to touch the patient. But since the publication of To Err is Human, the call has been instead to use human factors and systems engineering methods and principles to solve patient safety problems. However, an understanding of the human factors and systems engineering is lacking, and confusion remains about what it means to apply their principles. This paper provides a primer on them and their applications to patient safety.

Human Factors and Systems Engineering Approach to Patient Safety for Radiotherapy

International Nuclear Information System (INIS)

Rivera, A. Joy; Karsh, Ben-Tzion

2008-01-01

The traditional approach to solving patient safety problems in healthcare is to blame the last person to touch the patient. But since the publication of To Err is Human, the call has been instead to use human factors and systems engineering methods and principles to solve patient safety problems. However, an understanding of the human factors and systems engineering is lacking, and confusion remains about what it means to apply their principles. This paper provides a primer on them and their applications to patient safety

The importance of fire simulation in fire prediction

Directory of Open Access Journals (Sweden)

Jevtić Radoje B.

2014-01-01

Full Text Available The appearance of fire in objects with lot of humans inside represents very possible real situation that could be very danger and could cause destructive consequences on human lives and material properties. Very important influence in fire prediction, fire protection, human and material properties safety could be a fire simulation in object. This simulation could give many useful information of possible fire propagation; possible and existed evacuation routes; possible and exited placing of fire, smoke, temperature conditions in object and many other information of crucial importance for human lives and material properties, such as the best places for sensors position, optimal number of sensors, projection of possible evacuation routes etc. There are many different programs for fire simulation. This paper presents complete fire simulation in Electrotechnical school Nikola Tesla in Niš in FDS.

CCDP evaluation of the fire areas of KSNP using CFAST

International Nuclear Information System (INIS)

Lee, Yoon Hwan; Yang, Joon Eon; Kim, Jong Hoon

2005-01-01

During the past decade, the nuclear power industry has been moving away from prescriptive rules and practices toward risk-informed and performance-based engineering analysis to support the decision making for plant fire protection programs. For example, the National Fire Protection Association (NFPA) prepared NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants 2001 Edition. One crucial element in supporting the risk-informed fire protection is availability of simple and reliable methods and tools for evaluating the likelihood and consequences of fire scenarios. These tools directly benefit risk-informed and performance-based fire protection and application of risk information to resolve fire protection issues. Now the deterministic analysis results for the cable integrity is not given in case of performing the fire PSA. So it is necessary to apply the results for the fire modeling to the fire PSA model to develop the more realistic model. This document is intended to analyze the peak temperature of the upper gas layer using the fire modeling code, CFAST , to evaluate the integrity of the cable located on the dominant pump rooms, and to assess the CCDP(Conditional Core Damage Probability) using the results of the cable integrity. Accordingly, the fire safety assessment for the dominant fire areas using the fire modeling code will be capable of evaluating the consequences of the fire scenario, of reducing the the uncertainty, and to develop a more realistic model

Proceedings of the SRESA national conference on reliability and safety engineering

International Nuclear Information System (INIS)

Varde, P.V.; Vaishnavi, P.; Sujatha, S.; Valarmathi, A.

2014-01-01

The objective of this conference was to provide a forum for technical discussions on recent developments in the area of risk based approach and Prognostic Health Management of critical systems in decision making. The reliability and safety engineering methods are concerned with the way which the product fails, and the effects of failure is to understand how a product works and assures acceptable levels of safety. The reliability engineering addresses all the anticipated and possibly unanticipated causes of failure to ensure the occurrence of failure is prevented or minimized. The topics discussed in the conference were: Reliability in Engineering Design, Safety Assessment and Management, Reliability analysis and Assessment , Stochastic Petri nets for reliability Modeling, Dynamic Reliability, Reliability Prediction, Hardware Reliability, Software Reliability in Safety Critical Issues, Probabilistic Safety Assessment, Risk Informed Approach, Dynamic Models for Reliability Analysis, Reliability based Design and Analysis, Prognostics and Health Management, Remaining Useful Life (RUL), Human Reliability Modeling, Risk Based Applications, Hazard and Operability Study (HAZOP), Reliability in Network Security and Quality Assurance and Management etc. The papers relevant to INIS are indexed separately

Fire protection in nuclear power plants. Pt. 3. Fire protection for mechanical and electrotechnical equipment and components

International Nuclear Information System (INIS)

1994-01-01

The KTA rule applies to LWRs and defines requirements to be met for fire protection of equipment and installations of the safety system, and all safety-relevant systems, and of those operating systems that under the effect of fire, may cause improper functioning of safety system components. (orig./HP) [de

Cogeneration with natural gas fired internal combustion engines: Italian utility's 10 years operating experience

International Nuclear Information System (INIS)

Montermini, G.P.

1992-01-01

This paper describes the experience that AGAC, an Italian gas and water utility, has acquired in the operation of a 116 Km long district heating network serving about 40,000 inhabitants. The network is powered by a mix of methane fuelled Otto and diesel cycle engines, coal fired fluidized bed boilers, and methane fired boilers producing annually about 153,000 kW of thermal energy, 2,300 kW of cooling energy, and 28.8 million kWh of electric power. This paper reports on the performance of this system in terms of production and sales trends, equipment efficiency and compatibility with new European Communities air pollution standards

Evaluation of the influence of a postulated lubrication oil fire on safety related cables in the top shield platform of PFBR RCB by using FDS Code

International Nuclear Information System (INIS)

Mangarjuna Rao, P.; Jayasuriya, C.; Nashine, B.K.; Chellapandi, P.; Velusamy, K.

2010-01-01

Top deck of Prototype Fast Breeder Reactor (PFBR) primary system houses redundant safety related systems like Control and Safety Rod Drive Mechanisms (CSRDM), Diverse Safety Rod Drive Mechanism (DSRDM), subassembly outlet sodium temperature measurement system and central canal plug. These systems protrude out from the reactor through the Control Plug (CP), which is supported on the Top Shield (TS) of PFBR. Control and instrumentation signal cables and power cables of these safety related systems that are coming out from the CP are routed through Top Shield Platform (TSP, which is concentric with Reactor Vault (RV) at EL 34.1 m above the TS) to the peripheral local instrumentation control centers via the cable junction boxes supported on TS. Influence approach fire hazard analysis (FHA) has been carried out to evaluate the condition of redundant safety related cables under the scenario of a postulated oil fire in the TSP using Fire Dynamics Simulator code (FDS, Version 5). FDS is a computational fluid dynamics (CFD) based fire analysis code and it is developed by National Institute of Standards and Technology (NIST), USA. In this paper the details of the model developed and the results of the analysis carried out are discussed. In TSP, a postulated oil fire scenario with complete inventory of a primary sodium pump (PSP) lubrication oil leak (200 lt) has been considered at 30 m elevation on the TS. Computational model with the geometry of TSP and with other important structural components on TS like PSPs, intermediate heat exchangers (IHXs), large rotating plug (LRP), small rotating plug (SRP), CP and etc. has been developed along with a fire of 1800 kW/m 2 heat release rate in the vicinity of the PSP1. Numerical simulation has been carried out to evaluate this oil fire influence on the typical safety related cables routed at 34 m elevation. It has been found that the surface temperature of the cables that are routed directly above the fire only crosses the ignition

The role of engineering judgement, safety culture, and organizational factors in risk assessment

International Nuclear Information System (INIS)

Muzumdar, Ajit; Professor, Visiting

1996-01-01

This paper reviews the role of engineering judgement, safety culture, and organizational factors in risk assessment by examining the reasons for human-based error. The need for more emphasis on producing engineers with good engineering judgement is described. The progress in quantifying the role of safety culture and organizational factors in risk assessment studies is summarized

Safety improvements made at the Loviisa nuclear power plant to reduce fire risks originating from the turbine generators

International Nuclear Information System (INIS)

Virolainen, T.; Marttila, J.; Aulamo, H.

1998-01-01

Comprehensive upgrading measures have been completed for the Loviisa Nuclear Power Plant (modified VVER440/V213). These were carried out from the start of the design phase and during operation to ensure safe plant shutdown in the event of a large turbine generator oil fire. These modifications were made mainly on a deterministic basis according to specific risk studies and fire analyses. As part of the probabilistic safety assessment, a fire risk analysis was made that confirmed the importance of these upgrading measures. In fact, they should be considered as design basis modifications for all VVER440 plants. (author)

Passive and engineered safety features of the prototype fast reactor (PFR), Dounreay

International Nuclear Information System (INIS)

Gregory, C.V.

1991-01-01

Prototype fast reactor (PFR) combines passive and engineered safety features. Natural convection, a strong negative power coefficient, the decay heat removal system, and a fuel design able to operate beyond failure are all inherent and passive safety features of the PFR. The reliable shutdown system and the protection provided against SGU leaks are example of engineered protection. Experience at PFR demonstrates the worth and potential of a range of passive and engineered safeguards

Fire tests and their relevance

International Nuclear Information System (INIS)

Malhotra, H.L.

1984-01-01

Background information is provided about the nature of fire tests in general, not specifically designed for testing nuclear flasks. Headings are: brief history (including various temperature/time fire curves); the current position; types of tests; validation of fire tests; fire safety system. (U.K.)

Electrical Switchgear Building No. 5010-ESF Fire Hazards Technical Report

International Nuclear Information System (INIS)

N.M. Ruonavaara

2001-01-01

The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives, identified in DOE Order 420.1, Change 2, Fire Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: (1) The occurrence of a fire or related event; (2) A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of the employees, the public, and the environment; (3) Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; (4) Property losses from a fire and related events exceeding defined limits established by DOE; and (5) Critical process controls and safety class systems being damaged as a result of a fire and related event

Mean composite fire severity metrics computed with Google Earth Engine offer improved accuracy and expanded mapping potential

Science.gov (United States)

Parks, Sean; Holsinger, Lisa M.; Voss, Morgan; Loehman, Rachel A.; Robinson, Nathaniel P.

2018-01-01

Landsat-based fire severity datasets are an invaluable resource for monitoring and research purposes. These gridded fire severity datasets are generally produced with pre-and post-fire imagery to estimate the degree of fire-induced ecological change. Here, we introduce methods to produce three Landsat-based fire severity metrics using the Google Earth Engine (GEE) platform: the delta normalized burn ratio (dNBR), the relativized delta normalized burn ratio (RdNBR), and the relativized burn ratio (RBR). Our methods do not rely on time-consuming a priori scene selection and instead use a mean compositing approach in which all valid pixels (e.g. cloud-free) over a pre-specified date range (pre- and post-fire) are stacked and the mean value for each pixel over each stack is used to produce the resulting fire severity datasets. This approach demonstrates that fire severity datasets can be produced with relative ease and speed compared the standard approach in which one pre-fire and post-fire scene are judiciously identified and used to produce fire severity datasets. We also validate the GEE-derived fire severity metrics using field-based fire severity plots for 18 fires in the western US. These validations are compared to Landsat-based fire severity datasets produced using only one pre- and post-fire scene, which has been the standard approach in producing such datasets since their inception. Results indicate that the GEE-derived fire severity datasets show improved validation statistics compared to parallel versions in which only one pre-fire and post-fire scene are used. We provide code and a sample geospatial fire history layer to produce dNBR, RdNBR, and RBR for the 18 fires we evaluated. Although our approach requires that a geospatial fire history layer (i.e. fire perimeters) be produced independently and prior to applying our methods, we suggest our GEE methodology can reasonably be implemented on hundreds to thousands of fires, thereby increasing opportunities

Environmental optimisation of natural gas fired engines. Main report

Energy Technology Data Exchange (ETDEWEB)

Kvist, T. et al.

2010-10-15

The overall aim of the project has been to assess to which extent it is possible to reduce the emissions by adjusting the different engines examined and to determine the cost of the damage caused by emissions from natural gas combustion. However, only health and climate effects are included. The emissions of NO{sub x}, CO and UHC as well as the composition of the hydrocarbon emissions were measured for four different stationary lean-burn natural-gas fired engines installed at different combined heat and power (CHP) units in Denmark. The units were chosen to be representative of the natural gas fired engine-based power production in Denmark. The measurements showed that NO{sub x} emissions were relatively more sensitive to engine setting than UHC, CO and formaldehyde emissions. By reducing the NO{sub x} emissions to 40 % of the initial value (from 500 to 200 mg/m3(n) at 5 % O{sub 2}) the UHC emission was increased by 10 % to 50 % of the initial value. The electrical efficiency was reduced by 0.5 to 1.0 percentage point. Externalities in relation to power production are defined as the costs, which are not directly included in the price of the produced power. Health effects related to air pollution from power plants fall under this definition and usually dominate the results on external costs. For determination of these effects the exposure of the population, the impact of the exposure and the societal costs accompanying the impacts have been evaluated. As expected, it was found that when the engines are adjusted in order to reduce NO{sub x} emissions, the emission of UHC increases and vice versa. It was found that at high NO{sub x} emission levels (500 mg/m3{sub n} at 5 % O{sub 2}) the external costs related to the NO{sub x} emissions are 15 to 25 times the costs related to UHC emissions. At low NO{sub x} emission levels (200 mg/m3{sub n} at 5 % O{sub 2}) the costs related to NO{sub x} are 5 to 8 times the costs related to UHC emissions. Apparently, the harmfulness

Electric shock and electrical fire specialty

International Nuclear Information System (INIS)

2011-02-01

This book deals with electric shock and electrical fire, which is made up seven chapters. It describes of special measurement for electric shock and electrical fire. It mentions concretely about electrical fire analysis and precautionary measurement, electrical shock analysis cases, occurrence of static electricity and measurement, gas accident, analysis of equipment accident and precautionary measurement. The book is published to educate the measurement on electric shock and electrical fire by electrical safety technology education center in Korea Electrical Safety Corporation.

Econometric analysis of fire suppression production functions for large wildland fires

Science.gov (United States)

Thomas P. Holmes; David E. Calkin

2013-01-01

In this paper, we use operational data collected for large wildland fires to estimate the parameters of economic production functions that relate the rate of fireline construction with the level of fire suppression inputs (handcrews, dozers, engines and helicopters). These parameter estimates are then used to evaluate whether the productivity of fire suppression inputs...

Motorcoach Fire Safety Analysis.

Science.gov (United States)

2009-07-01

This purpose of this study was to collect and analyze information from Government, industry, and media sources on the causes, frequency, and severity of motorcoach fires in the U.S., and to identify potential risk reduction measures. The Volpe Center...

Safety assessment of complex engineered and natural systems: radioactive waste disposal

International Nuclear Information System (INIS)

McNeish, J.A.; Vallikat, V.; Atkins, J.; Balady, M.A.

1997-01-01

Evaluation of deep, geologic disposal of nuclear waste requires the probabilistic safety assessment of a complex system from the coupling of various processes and sub-systems, parameter and model uncertainties, spatial and temporal variabilities, and the multiplicity of designs and scenarios. Both the engineered and natural system are included in the evaluation. Each system has aspects with considerable uncertainty both in important parameters and in overall conceptual models. The study represented herein provides a probabilistic safety assessment of a potential respository system for multiple engineered barrier system (EBS) design and conceptual model configurations (CRWMS M and O, 1996a) and considers the effects of uncertainty on the overall results. The assessment is based on data and process models available at the time of the study and doesnt necessarily represent the current safety evaluation. In fact, the percolation flux through the repository system is now expected to be higher than the estimate used for this study. The potential effects of higher percolation fluxes are currently under study. The safety of the system was assessed for both 10,000 and 1,000,000 years. Use of alternative conceptual models also produced major improvement in safety. For example, use of a more realistic engineered system release model produced improvement of over an order of magnitude in safety. Alternative measurement locations for the safety assessment produced substantial increases in safety, through the results are based on uncertain dilution factors in the transporting groundwater. (Author)

Improving Freight Fire Safety: Analysis and Testing of Real Engine Conditions to Progress Development of Mist-controlling Additives for Fire Mitigation

Science.gov (United States)

2009-12-01

The formation of a fuel mist resulting from high shear stresses acting on the fuel during violent sloshing and tank rupture under the energy of a crash severely increases the occurrence and intensity of fires in transportation related accidents. In o...

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

1992-01-01

The Code on Design (Safety Series 50-C-D (Rev. 1)) within the NUSS (Nuclear Safety Standards) programme of the IAEA points out the necessity of measures for protecting plant items which are important to safety against fires of internal and external origin. Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice. Figs, 1 tab

Improving Safety through Human Factors Engineering.

Science.gov (United States)

Siewert, Bettina; Hochman, Mary G

2015-10-01

Human factors engineering (HFE) focuses on the design and analysis of interactive systems that involve people, technical equipment, and work environment. HFE is informed by knowledge of human characteristics. It complements existing patient safety efforts by specifically taking into consideration that, as humans, frontline staff will inevitably make mistakes. Therefore, the systems with which they interact should be designed for the anticipation and mitigation of human errors. The goal of HFE is to optimize the interaction of humans with their work environment and technical equipment to maximize safety and efficiency. Special safeguards include usability testing, standardization of processes, and use of checklists and forcing functions. However, the effectiveness of the safety program and resiliency of the organization depend on timely reporting of all safety events independent of patient harm, including perceived potential risks, bad outcomes that occur even when proper protocols have been followed, and episodes of "improvisation" when formal guidelines are found not to exist. Therefore, an institution must adopt a robust culture of safety, where the focus is shifted from blaming individuals for errors to preventing future errors, and where barriers to speaking up-including barriers introduced by steep authority gradients-are minimized. This requires creation of formal guidelines to address safety concerns, establishment of unified teams with open communication and shared responsibility for patient safety, and education of managers and senior physicians to perceive the reporting of safety concerns as a benefit rather than a threat. © RSNA, 2015.

Prevent recurrence of nuclear disaster (3). Agenda on nuclear safety from earthquake engineering

International Nuclear Information System (INIS)

Kameda, Hiroyuki; Takada, Tsuyoshi; Ebisawa, Katsumi; Nakamura, Susumu

2012-01-01

Based on results of activities of committee on seismic safety of nuclear power plants (NPPs) of Japan Association for Earthquake Engineering, which started activities after Chuetsu-oki earthquake and then experienced Great East Japan Earthquake, (under close collaboration with the committee of Atomic Energy Society of Japan started activities simultaneously), and taking account of further development of concept, agenda on nuclear safety were proposed from earthquake engineering. In order to prevent recurrence of nuclear disaster, individual technical issues of earthquake engineering and comprehensive issues of integration technology, multidisciplinary collaboration and establishment of technology governance based on them were of prime importance. This article described important problems to be solved; (1) technical issues and mission of seismic safety of NPPs, (2) decision making based on risk assessment - basis of technical governance, (3) framework of risk, design and regulation - framework of required technology governance, (4) technical issues of earthquake engineering for nuclear safety, (5) role of earthquake engineering in nuclear power risk communication and (6) importance of multidisciplinary collaboration. Responsibility of engineering would be attributed to establishment of technology governance, cultivation of individual technology and integration technology, and social communications. (T. Tanaka)

Comparison of the characteristics of fire and non-fire households in the 2004-2005 survey of fire department-attended and unattended fires.

Science.gov (United States)

Greene, Michael A

2012-06-01

Comparison of characteristics of fire with non-fire households to determine factors differentially associated with fire households (fire risk factors). National household telephone survey in 2004-2005 by the US Consumer Product Safety Commission with 916 fire households and a comparison sample of 2161 non-fire households. There were an estimated 7.4 million fires (96.6% not reported to fire departments) with 130,000 injuries. Bivariate analysis and multivariate logistic regression analyses to assess differences in household characteristics. Significant factors associated with fire households were renting vs. owning (OR 1.988 pfire households with non-cooking fires (OR 1.383 p=0.0011). Single family houses were associated with non-fire households in the bivariate analysis but not in the multivariate analyses. Renting, household members under 18 years old and smokers are risk factors for unattended fires, similar to the literature for fatal and injury fires. Differences included household members over 65 years old (associated with non-fire households), college/postgraduate education (associated with fire households) and lack of significance of income. Preventing cooking fires (64% of survey incidents), smoking prevention efforts and fire prevention education for families with young children have the potential for reducing unattended fires and injuries.

Review of fire protection in the nuclear facilities of the Atomic Energy Commission, 1947--1975

International Nuclear Information System (INIS)

Maybee, W.W.

1979-01-01

In the 28 years in which it grew from a temporary wartime bomb development program to a federal agency with over $30 billion worth of facilities housing much of the nation's advanced research efforts, the Atomic Energy Commission set many records for safety. Among the best was a cumulative fire loss ratio of 12 cents per $100 of value. A 1969 fire--one of four in its history that exceeded $1 million in loss--incurred damages totaling $26 million and prompted major additions to its fire protection programs. The added programs, encompassing additional fire protection engineers, new protection systems, independent inspection programs, and new performance-based goals, resulted in an order-of-magnitude improvement. The cumulative fire loss ratio after 1969 was 0.06 cents per $100 of value, a record few industries have ever achieved

Kempe's engineers year-book for 1977. Volume II

Energy Technology Data Exchange (ETDEWEB)

Prockter, C.E. (ed.)

1977-01-01

The second volume of this two-volume yearbook contains data on: electrical and electronic engineering; aerodynamics and aircraft propulsion; gas turbines; internal combustion engines; motor vehicles; fuels; fluidics; nuclear energy; gas and gas engineering; steam engineering and steam turbines; marine diesel engines; naval architecture; mining engineering; industrial explosives; air compression, pneumatic equipment, etc.; refrigeration, heating, ventilation and air conditioning; lighting; industrial safety and protection; fire protection; highway engineering; surveying; foundation and earthwork; cements, mortars and clay products; buildings; public health engineering; concretes; design of steel structures; bridges and bridgework; paints and coatings; patents, designs and trade marks; depreciation; legal notes for engineers; factory planning and layout; and agricultural engineering. (1325p.) A subject index is provided. (LCL)

Behaviour of French electrical cables under fire conditions

Energy Technology Data Exchange (ETDEWEB)

Bertrand, R.; Chaussard, M.; Gonzalez, R.; Lacoue, J.; Mattei, J.M.; Such, J.M

2001-12-01

A fire Probabilistic Safety Assessment - called fire PSA - is being carried out by the French Institute of Nuclear Safety and Protection (IPSN) to be used in the framework of the safety assessment of operating 900 MWe PWRs. The aim of this study is to evaluate the core damage conditional probability which could result from a fire. A fire can induce unavailability of safety equipment notably damaging electrical cables that are a significant risk contributor. The purpose of this communication is to present the electrical cable fire tests carried out by IPSN to identify the failure modes and to determine the cable damage criteria. Moreover, are indicated the impact of each kind of cable failure mode and the methodology used to estimate the conditional probability of a failure mode when cable damage occurred. (authors)

Fires: what plant locations should we really protect

International Nuclear Information System (INIS)

Berry, D.L.

1980-01-01

A fire protection analysis technique was developed from earlier work involving the protection of nuclear power plants against acts of sabotage. Characteristics unique to fire phenomena were used to modify the sabotage analysis methodology. These characteristics include the effects of fuel loads, ventilation rates, heat loss areas, barrier ratings, and plant locations. The new fire analysis technique was applied to an example nuclear power plant having 85 different plant areas. It was found that some safety and nonsafety areas were both highly vulnerable to fire spread and important to overall safety, while other areas were found to be of marginal importance to fire safety

Nuclear power plant fire protection: philosophy and analysis

International Nuclear Information System (INIS)

Berry, D.L.

1980-05-01

This report combines a fire severity analysis technique with a fault tree methodology for assessing the importance to nuclear power plant safety of certain combinations of components and systems. Characteristics unique to fire, such as propagation induced by the failure of barriers, have been incorporated into the methodology. By applying the resulting fire analysis technique to actual conditions found in a representative nuclear power plant, it is found that some safety and nonsafety areas are both highly vulnerable to fire spread and impotant to overall safety, while other areas prove to be of marginal importance. Suggestions are made for further experimental and analytical work to supplement the fire analysis method

Suppression of pool fires with HRC-125 in a simulated engine nacelle.