WorldWideScience

Sample records for fire protection design

  1. DOE Standard: Fire protection design criteria

    International Nuclear Information System (INIS)

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ''Fire Protection'', and DOE 6430.1A, ''General Design Criteria''. It also contains the fire protection guidelines from two (now canceled) draft standards: ''Glove Box Fire Protection'' and ''Filter Plenum Fire Protection''. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities

  2. The importance of verifiable fire protection design

    Energy Technology Data Exchange (ETDEWEB)

    Medonos, Sava [Petrellus Ltd. (United Kingdom)]. E-mail: smm@petrellus.co.uk; Geddes, Paul [Global Solutions UK Ltd. (United Kingdom)]. E-mail: paul@globalsolutionsuk.com

    2004-07-01

    Simplistic methods based on the Hp/A ratio between the heated surface area and volume or a 2-dimensional analysis may be sufficient for the determination of fire protection coatings for simple components. For the optimization of fire protection of pressure systems and load bearing structures, however, they have proved to be inadequate, as they do not represent the response taking place. This often leads to over-protection or inadequate fire resistance. In the past 10 years there have been claims in petrochemical industry of 'methods' for fire protection 'optimization' based on a walk-down through a topside or plant, or a heat-up calculation of a few cross sections with no regard to stress. These methods are wrong. In the best case these 'methods of optimization' lead to high unnecessary costs and in the worst case in an explosion of a vessel, structural collapse, domino effects and cataclysmic fire throughout the plant. The operator or design contractor should always require a Method Statement including a proof of verification to obtain the adequate quality of fire protection. (author)

  3. 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

  4. Seismic design criteria of fire protection systems for DOE facilities

    International Nuclear Information System (INIS)

    Hardy, G.; Cushing, R.; Driesen, G.

    1991-01-01

    Fire protection systems are critical to the safety of personnel and to the protection of inventory during any kind of emergency situation that involves a fire. The importance of these fire protection systems is hightened for DOE facilities which often house nuclear, chemical or scientific processes. Current research into the topic of open-quotes fires following earthquakesclose quotes has demonstrated that the risks of a fire starting as a result of a major earthquake can be significant. Thus, fire protection systems need to be designed to withstand the anticipated seismic event for the site in question

  5. Basing of a complex design measures for protection against fire

    International Nuclear Information System (INIS)

    Kryuger, V.

    1983-01-01

    Fire impact on NPP radiation safety is analyzed. The general industry requirements to the protection system against fire are shown to be insufficient for NPPs. A complex of protection measures against fire is suggested that should be taken into account in the NPP designs [ru

  6. Internal fire protection analysis for the United Kingdom EPR design

    Energy Technology Data Exchange (ETDEWEB)

    Laid, Abdallah [Nuclear New Build Generation Company Ltd. (NNB GenCo), Barnwood (United Kingdom). EDF Energy Plc.; Cesbron, Mickael [Service Etudes et Project Thermiques et Nucleaires (SEPTEN), Lyon (France). EDF-SA

    2015-12-15

    In the deterministic design basis analysis of the United Kingdom (UK) EPR based nuclear power plants all postulated initiating events are grouped into two different types, internal faults and internal/external hazards. ''Internal Fires'' is one of the internal hazards analysed at the design stage of the UK EPR. In effect, the main safety objective for fire protection is to ensure that all the required safety functions are performed in the event of an internal fire. To achieve this safety objective, provisions for protection against fire risks are taken to: (i) limit the spread of a fire, protect the safety functions of the facility; (ii) limit the propagation of smoke and dispersion of toxic, radioactive, inflammable, corrosive or explosive materials, and (iii) ensure the achievement of a safe shutdown state, personnel evacuation and all other necessary emergency actions. This paper presents the UK EPR approach on how the above provisions are applied. Such provisions involve implementing means of fire prevention, surveillance, firefighting and limiting fire consequences, appropriate to the risks inherent to the facility. Overall, the design of the UK EPR fire protection systems is based on three types of measures: prevention, containment and control.

  7. Design guide for fire protection of grouped electrical cables

    International Nuclear Information System (INIS)

    Dungan, K.W.

    1991-05-01

    This paper develops design guidance for fire protection of grouped electrical cables using previous research and the concept of design objectives based on damage limits. A quantitative approach is taken to establishing performance-oriented design objectives and addressing fires exposing cables as well as cable fires. A one-page Design Calculation Checklist is developed and examples are shown. In addition, testing was done for placement of linear thermal detection on cable trays and recommendations are given. 32 refs., 10 figs., 8 tabs

  8. Design guides for cell atmosphere controls, utilities and fire protection

    International Nuclear Information System (INIS)

    Hill, A.J. Jr.; Peishel, F.L.; Slattery, E.F.

    1981-01-01

    Facilities for handling radioactive and toxic materials must be designed not only for efficient operation, but also for protection of the operating personnel and the public. The ventilation system is of primary importance in maintaining containment of any airborne radioactivity. The type, number, and location of in-cell services must be adequate for planned operations, but also must allow flexibility to accommodate expansion in the scope of operations or changes in programs. Fire protection systems and operational controls are mandatory to maintain containment of radioactivity in the event of an operating error or process accident that may result in a fire

  9. 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)

  10. LMFBR plant design features for sodium spill and fire protection

    International Nuclear Information System (INIS)

    Palm, R.E.

    1982-01-01

    Design features have been developed for an LMFBR plant to protect the concrete structures from potential liquid spills and fires and prevent sodium-concrete reactions. The inclusion of these features in the plant design reduces the severity of design basis accident conditions imposed on containment and other critical plant structures. Steel liners are provided in cells containing radioactive sodium systems, and catch pans are located in non-radioactive sodium system cells. The design requirements and descriptions of each of these protective features are presented. The loading conditions, analytical approach and numerical results are also included. Design of concrete cell structures that are subject to high temperature effects from sodium spills is discussed. The structural design considers the influence of high temperature on design properties of concrete and carbon steel materials based on results of a comprehensive test program. The development of these design features and high temperature design considerations for the Clinch River Breeder Reactor Plant (CRBRP) are presented in this paper

  11. Cold Vacuum Drying facility fire protection system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) fire protection system (FPS). The FPS provides fire detection, suppression, and loss limitation for the CVDF structure, personnel, and in-process spent nuclear fuel. The system provides, along with supporting interfacing systems, detection, alarm, and activation instrumentation and controls, distributive piping system, isolation valves, and materials and controls to limit combustibles and the associated fire loadings

  12. RCC-F: Design and construction rules for PWR fire protection systems

    International Nuclear Information System (INIS)

    2013-01-01

    The RCC-F code defines the rules for designing, building and installing the fire protection systems used to manage the nuclear hazards inherent in the outbreak of a fire inside the facility and thereby control the fundamental nuclear functions. The code provides fire protection recommendations in terms of: the industrial risk (loss of assets and/or operation), personnel safety, the environment. The code is divided into five main sections: generalities, design safety principles, fire protection design bases, construction provisions, rules for installing the fire protection components and equipment. The RCC-F code is available as an ETC-F version specifically for EPR projects (European pressurized reactor). Contents of the 2013 edition of the ETC-F code: Volume A - Generalities: Structure of ETC-F general points, documentation (in progress), chapter (provision) quality assurance; Volume B - Design safety principles: design nuclear safety principles; Volume C - Fire protection design bases: fire protection design bases; Volume D - Construction provisions: construction provisions; Volume E - Installation rules for fire protection: rules for installing the fire protection, components and equipment

  13. 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

  14. Cold Vacuum Dryer (CVD) Facility Fire Protection System Design Description (SYS 24)

    Energy Technology Data Exchange (ETDEWEB)

    SINGH, G.

    2000-10-17

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility fire protection system (FPS). The primary features of the FPS for the CVD are a fire alarm and detection system, automatic sprinklers, and fire hydrants. The FPS also includes fire extinguishers located throughout the facility and fire hydrants to assist in manual firefighting efforts. In addition, a fire barrier separates the operations support (administrative) area from the process bays and process bay support areas. Administrative controls to limit combustible materials have been established and are a part of the overall fire protection program. The FPS is augmented by assistance from the Hanford Fire Department (HED) and by interface systems including service water, electrical power, drains, instrumentation and controls. This SDD, when used in conjunction with the other elements of the definitive design package, provides a complete picture of the FPS for the CVD Facility.

  15. Cernavoda nuclear power plant: Modifications in the fire protection measures of the CANDU 6 standard design

    International Nuclear Information System (INIS)

    Covalschi, V.

    1998-01-01

    Having as purpose the improvement of fire safety at the Cernavoda NPP - both in the prevention and the protection aspects in the case of fire - we implemented some modifications in the CANDU 6 standard design. These improvements are inspired, mainly, from two sources: the world-wide achievements in the field of fire protection techniques, introduced in nuclear power plants since the middle of 70's, when the CANDU 6 design was completed; the national practice and experience in fire protection, usually applied in industrial objectives (conventional power plants, in particular). The absence of any incident may be considered as a proof of the efficiency of the implemented fire preventing and protection measures. (author)

  16. FIRE PROTECTION SYSTEMS AND TECHNOLOGIES

    Directory of Open Access Journals (Sweden)

    Aristov Denis Ivanovich

    2016-03-01

    Full Text Available The All-Russian Congress “Fire Stop Moscow” was de-voted to the analysis of the four segments of the industry of fire protection systems and technologies: the design of fire protec-tion systems, the latest developments and technologies of active and passive fire protection of buildings, the state and the devel-opment of the legal framework, the practice of fire protection of buildings and structures. The forum brought together the repre-sentatives of the industry of fire protection systems, scientists, leading experts, specialists in fire protection and representatives of construction companies from different regions of Russia. In parallel with the Congress Industrial Exhibition of fire protection systems, materials and technology was held, where manufacturers presented their products. The urgency of the “Fire Stop Moscow” Congress in 2015 organized by the Congress Bureau ODF Events lies primarily in the fact that it considered the full range of issues related to the fire protection of building and construction projects; studied the state of the regulatory framework for fire safety and efficiency of public services, research centers, private companies and busi-nesses in the area of fire safety. The main practical significance of the event which was widely covered in the media space, was the opportunity to share the views and information between management, science, and practice of business on implementing fire protection systems in the conditions of modern economic relations and market realities. : congress, fire protection, systems, technologies, fire protection systems, exhibition

  17. Design criteria document, Fire Protection Task, K Basin Essential Systems Recovery, Project W-405

    International Nuclear Information System (INIS)

    Johnson, B.H.

    1994-01-01

    The K Basin were constructed in the early 1950's with a 20 year design life. The K Basins are currently in their third design life and are serving as a near term storage facility for irradiated N Reactor fuel until an interim fuel storage solution can be implemented. In April 1994, Project W-405, K Basin Essential Systems Recovery, was established to address (among other things) the immediate fire protection needs of the 100K Area. A Fire Barrier Evaluation was performed for the wall between the active and inactive areas of the 105KE and 105KW buildings. This evaluation concludes that the wall is capable of being upgraded to provide an equivalent level of fire resistance as a qualified barrier having a fire resistance rating of 2 hours. The Fire Protection Task is one of four separate Tasks included within the scope of Project W405, K Basin Essential systems Recovery. The other three Tasks are the Water Distribution System Task, the Electrical System Task, and the Maintenance Shop/Support Facility Task. The purpose of Project W-405's Fire Protection Task is to correct Life Safety Code (NFPA 101) non-compliances and to provide fire protection features in Buildings 105KE, 105KW and 190KE that are essential for assuring the safe operation and storage of spent nuclear fuel at the 100K Area Facilities' Irradiated Fuel Storage Basins (K Basins)

  18. Loft fire protection

    International Nuclear Information System (INIS)

    White, E.R.; Jensen, J.D.

    1980-01-01

    Quantified criteria that was developed and applied to provide in-depth fire protection for the Loss of Fluid Test (LOFT) Facility are presented. The presentation describes the evolution process that elevated the facility's fire protection from minimal to that required for a highly protected risk or improved risk. Explored are some infrequently used fire protection measures that are poorly understood outside the fire protection profession

  19. 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

  20. Fire protection requirements of the insurance industry and their impact on nuclear power plant design and construction

    International Nuclear Information System (INIS)

    Deitchman, J.V.; King, W.T. Jr.; Nashman, T.A.

    1976-01-01

    The insurance industry, with its wealth of knowledge and experience in the fire protection area and with preservation of its funds at stake, has always been heavily involved in the fire protection programs of nuclear power plants. Since it was concerned with property preservation in addition to nuclear safety, the insurance industry placed more detailed emphasis on fire protection requirements than did the nuclear regulatory bodies. Since the Browns Ferry fire, however, the insurance industry, the Nuclear Regulatory Commission, the Advisory Committee on Reactor Safeguards and the utilities themselves have re-examined their approaches to fire protection. A more coordinated approach seems to have emerged, which is based largely upon insurance industry specifications and guidelines. The paper briefly summarizes the fire protection requirements of the insurance industry as they apply to nuclear power plants. Some of the ways these requirements affect project planning, plant design, and construction timing are reviewed, as well as some of the more controversial fire protection areas

  1. 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.

  2. Fire Protection Engineering Design Brief Template. Hydrogen Refueling Station.

    Energy Technology Data Exchange (ETDEWEB)

    LaFleur, Angela Christine [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Muna, Alice Baca [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Groth, Katrina M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    Building a hydrogen infrastructure system is critical to supporting the development of alternate- fuel vehicles. This report provides a methodology for implementing a performance-based design of an outdoor hydrogen refueling station that does not meet specific prescriptive requirements in NFPA 2, The Hydrogen Technologies Code . Performance-based designs are a code-compliant alternative to meeting prescriptive requirements. Compliance is demonstrated by comparing a prescriptive-based fueling station design with a performance-based design approach using Quantitative Risk Assessment (QRA) methods and hydrogen risk assessment tools. This template utilizes the Sandia-developed QRA tool, Hydrogen Risk Analysis Models (HyRAM), which combines reduced-order deterministic models that characterize hydrogen release and flame behavior with probabilistic risk models to quantify risk values. Each project is unique and this template is not intended to account for site-specific characteristics. Instead, example content and a methodology are provided for a representative hydrogen refueling site which can be built upon for new hydrogen applications.

  3. Fire protection measures

    International Nuclear Information System (INIS)

    Bittner

    1997-01-01

    The presentation could only show a very brief overview of the analysis results of a wide study of the existing fire protection situation at Mochovce. As far not already done the next steps will be the selection of the final suppliers of the different measures, the detailed design and the implementation of the measures. As part of the further assistance in fire protection EUCOM will perform compliance checks of the DD and implementation and assist EMO for raising problems. Especially during the implementation of the measures the belonging quality checks have a high priority. Assuming that the implementation of measures will be in accordance with with the study results and the relevant basic design requirements it can be stated that safety level concerning fire protection will be in accordance with international requirement like IAEA 50 SG D2. The next step of our work will be the delta analysis for 2 unit and the relevant basic design as far as there are differences to unit 1. (author)

  4. 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

  5. Clinch River breeder reactor sodium fire protection system design and development

    International Nuclear Information System (INIS)

    Foster, K.W.; Boasso, C.J.; Kaushal, N.N.

    1984-01-01

    To assure the protection of the public and plant equipment, improbable accidents were hypothesized to form the basis for the design of safety systems. One such accident is the postulated failure of the Intermediate Heat Transfer System (IHTS) piping within the Steam Generator Building (SGB), resulting in a large-scale sodium fire. This paper discusses the design and development of plant features to reduce the consequences of the accident to acceptable levels. Additional design solutions were made to mitigate the sodium spray contribution to the accident scenario. Sodium spill tests demonstrated that large sodium leaks can be safely controlled in a sodium-cooled nuclear power plant

  6. Aircraft Fire Protection Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Navy Aircraft Protection Laboratory provides complete test support for all Navy air vehicle fire protection systems.The facility allows for the simulation of a...

  7. Standpipe systems for fire protection

    CERN Document Server

    Isman, Kenneth E

    2017-01-01

    This important new manual goes beyond the published NFPA standards on installation of standpipe systems to include the rules in the International Building Code, municipal fire codes, the National Fire Code of Canada, and information on inspection, testing, and maintenance of standpipe systems. Also covered are the interactions between standpipe and sprinkler systems, since these important fire protection systems are so frequently installed together. Illustrated with design examples and practical applications to reinforce the learning experience, this is the go-to reference for engineers, architects, design technicians, building inspectors, fire inspectors, and anyone that inspects, tests or maintains fire protection systems. Fire marshals and plan review authorities that have the responsibility for reviewing and accepting plans and hydraulic calculations for standpipe systems are also an important audience, as are firefighters who actually use standpipe systems. As a member of the committees responsible for s...

  8. 14 CFR 33.17 - Fire protection.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fire protection. 33.17 Section 33.17... STANDARDS: AIRCRAFT ENGINES Design and Construction; General § 33.17 Fire protection. (a) The design and... protection unless damage by fire will not cause leakage or spillage of a hazardous quantity of flammable...

  9. 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

  10. Sodium fire protection

    International Nuclear Information System (INIS)

    Raju, C.; Kale, R.D.

    1979-01-01

    Results of experiments carried out with sodium fires to develop extinguishment techniques are presented. Characteristics, ignition temperature, heat evolution and other aspects of sodium fires are described. Out of the powders tested for extinguishment of 10 Kg sodium fires, sodium bi-carbonate based dry chemical powder has been found to be the best extinguisher followed by large sized vermiculite and then calcium carbonate powders distributed by spray nozzles. Powders, however, do not extinguish large fires effectively due to sodium-concrete reaction. To control large scale fires in a LMFBR, collection trays with protective cover have been found to cause oxygen starvation better than flooding with inert gas. This system has an added advantage in that there is no damage to the sodium facilities as has been in the case of powders which often contain chlorine compounds and cause stress corrosion cracking. (M.G.B.)

  11. 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

  12. Proposal for the award of a blanket purchase contract for the design, supply, installation and maintenance of automatic fire-detection, fire-protection and voice-alarm systems for the Super Proton Synchrotron

    CERN Document Server

    2017-01-01

    Proposal for the award of a blanket purchase contract for the design, supply, installation and maintenance of automatic fire-detection, fire-protection and voice-alarm systems for the Super Proton Synchrotron

  13. A novel method to design water spray cooling system to protect floating roof atmospheric storage tanks against fires

    Directory of Open Access Journals (Sweden)

    Iraj Alimohammadi

    2015-01-01

    Full Text Available Hydrocarbon bulk storage tank fires are not very common, but their protection is essential due to severe consequences of such fires. Water spray cooling system is one of the most effective ways to reduce damages to a tank from a fire. Many codes and standards set requirements and recommendations to maximize the efficiency of water spray cooling systems, but these are widely different and still various interpretations and methods are employed to design such systems. This article provides a brief introduction to some possible design methods of cooling systems for protection of storage tanks against external non-contacting fires and introduces a new method namely “Linear Density Method” and compares the results from this method to the “Average Method” which is currently in common practice. The average Method determines the flow rate for each spray nozzle by dividing the total water demand by the number of spray nozzles while the Linear Density Method determines the nozzle flow rate based on the actual flow over the surface to be protected. The configuration of the system includes a one million barrel crude oil floating roof tank to be protected and which is placed one half tank diameter from a similar adjacent tank with a full surface fire. Thermal radiation and hydraulics are modeled using DNV PHAST Version 6.53 and Sunrise PIPENET Version 1.5.0.2722 software respectively. Spray nozzles used in design are manufactured by Angus Fire and PNR Nozzles companies. Schedule 40 carbon steel pipe is used for piping. The results show that the cooling system using the Linear Density Method consumes 3.55% more water than the design using the average method assuming a uniform application rate of 4.1 liters per minute. Despite higher water consumption the design based on Linear Density Method alleviates the problems associated with the Average Method and provides better protection.

  14. Fire protection for clean rooms

    International Nuclear Information System (INIS)

    Kirson, D.

    1990-01-01

    The fire protection engineer often must decide what size fire can be tolerated before automatic fire suppression systems actuate. Is it a wastepaper basket fire, a bushel basket fire...? In the case of state-of-the-art clean rooms, the answer clearly is not even an incipient fire. Minor fires in clean rooms can cause major losses. This paper discusses what a clean room is and gives a brief overview of the unique fire protection challenges encountered. The two major causes of fire related to clean rooms in the semiconductor industry are flammable/pyrophoric gas fires in plastic ducts and polypropylene wet bench fires. This paper concentrates on plastic ductwork in clean rooms, sprinkler protection in ductwork, and protection for wet benches

  15. Fire protection at nuclear power plants

    International Nuclear Information System (INIS)

    1999-11-01

    The guide presents specific requirements for the design and implementation of fire protection arrangements at nuclear power plants and for the documents relating to the fire protection that are to be submitted to STUK (Finnish Radiation and Nuclear Safety Authority). Inspections of the fire protection arrangements to be conducted by STUK during the construction and operation of the power plants are also described in this guide. The guide can also be followed at other nuclear facilities

  16. Fire protection considerations in the design of plutonium handling and storage facility

    International Nuclear Information System (INIS)

    Blanchard, A.

    2000-01-01

    Unwanted fire in a facility that handles plutonium must be addressed early in the facility design. Such fires have the potential for transporting radioactive contamination throughout the building and widespread downwind dispersal. Features that mitigate such events can be severely challenged during the fire. High temperatures can cause storage containers to burst; a very efficient dispersal mechanism for radioactive contamination. The fire will also establish ventilation patterns that cause the migration of smoke and radioactive contamination throughout the facility. The smoke and soot generated by the fire will enter the exhaust system and travel to the filtration system where it will deposit on the filters. The quantity of smoke generated during a typical multi-room fire is expected to blind most High Efficiency Particulate Airfilter (HEPA) media. The blinding can have two possible outcomes. (1) The air movement though the facility is reduced, compromising the negative pressure containment and allowing contamination to leave the building though doors and other openings; or (2) the filters collapse allowing the contamination to bypass the filtration media and exit the building through the filter plenum. HEPA filter blinding during severe fires can be prevented or mitigated. Increasing the face surface area of HEPA filters will increase the smoke filtration capacity of the system, thus preventing blinding. As an alternative sandfilters can be provided to mitigate the effects of the HEPA filter bypass. Both concepts have distinct advantages. This paper will explore these two design concepts and two others; it will describe the design requirements necessary for each concept to prevent unacceptable contamination spread. The intent is to allow the filter media selection to be based on a comprehensive understanding of the four different design concepts

  17. 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 ...

  18. Fire protection guidelines for nuclear power plants

    International Nuclear Information System (INIS)

    1976-06-01

    Guidelines acceptable to the NRC staff for implementing in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. Suitable bases and justification should be provided for alternative approaches to establish acceptable implementaion of General Design Criterion 3

  19. 10 CFR 36.27 - Fire protection.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Fire protection. 36.27 Section 36.27 Energy NUCLEAR REGULATORY COMMISSION LICENSES AND RADIATION SAFETY REQUIREMENTS FOR IRRADIATORS Design and Performance Requirements for Irradiators § 36.27 Fire protection. (a) The radiation room at a panoramic irradiator must...

  20. SFPE handbook of fire protection engineering

    CERN Document Server

    Gottuk, Daniel; Jr, John; Harada, Kazunori; Kuligowski, Erica; Puchovsky, Milosh; Torero, Jose´; Jr, John; WIECZOREK, CHRISTOPHER

    2016-01-01

    Revised and significantly expanded, the fifth edition of this classic work offers both new and substantially updated information. As the definitive reference on fire protection engineering, this book provides thorough treatment of the current best practices in fire protection engineering and performance-based fire safety. Over 130 eminent fire engineers and researchers contributed chapters to the book, representing universities and professional organizations around the world. It remains the indispensible source for reliable coverage of fire safety engineering fundamentals, fire dynamics, hazard calculations, fire risk analysis, modeling and more. With seventeen new chapters and over 1,800 figures, the this new edition contains: • Step-by-step equations that explain engineering calculations • Comprehensive revision of the coverage of human behavior in fire, including several new chapters on egress system design, occupant evacuation scenarios, combustion toxicity and data for human behavior analysis • Rev...

  1. National Fire Protection Association

    Science.gov (United States)

    ... closed NFPA Journal® NFPA Journal® Update (newsletter) Fire Technology ... die from American home fires, and another 13,000 are injured each year. This is the story of fire that the statistics won't show ...

  2. Fire protection concept for power stations

    International Nuclear Information System (INIS)

    Zitzmann, H.

    The author shows how a systematic approach permits the design of a fire-protected power station. The special conditions of an individual power station are here treated as marginal conditions. The article describes how the concept is realized in the completed power station, taking account of the information provided by fire statistics. (orig.) [de

  3. PG BN 1600 sodium fire protection system

    International Nuclear Information System (INIS)

    Bar, J.; Urbancik, L.

    1978-12-01

    A design was developed of a fire protection system for steam generator of a 1600 MW sodium cooled fast reactor (BN-1600). Chemical reactions are described of liquid sodium with atmospheric components and solid materials coming into contact with sodium in its release from the steam generator, and in safeguarding protection against sodium fires. The requirements for the purity of nitrogen as an atmosphere inert to liquid sodium are given. Characteristics and basic parameters are shown of level and spray fires, elementary terms are explained concerning the properties of aerosols formed during fires, the methods and means of release signalling and fire alarm are described as are fire precautions using fire-fighting equipment, modifying the support tank and the cell bottom and building sewage pits. The design of the system comprises an alarm system for liquid sodium using point and line electric contact sensors and flame photometer based aerosol sensors as well as a fire-fighting system based on the system of channelling liquid sodium into emergency discharge tanks filled with an inert gas, a set of fire extinguishers and other fire fighting material, and measures for the elimination of sodium fire consequences. (J.B.)

  4. Fire protection for telecommunications central offices

    International Nuclear Information System (INIS)

    McKenna, L.A. Jr.

    1990-01-01

    The provision of continuous, uninterrupted telecommunications service is vital to modern life. In order to provide uninterrupted service to customers, a service continuity program has been in place with AT and T for many years. This program integrates many different protection strategies and plans, each designed to mitigate one of the many threats to service continuity. The fire protection program implemented within AT and T is a part of this service continuity program. In the design of this program, a number of unusual problems had to be addressed due to the service continuity requirements. Typical solutions to fire protection problems (ignition prevention, detection, and suppression) which are embodied in building and fire prevention codes are inadequate to provide service continuity. This presentation outlines the basic arrangement of a telecommunications central office, the specific fire protection problems encountered, the fire protection philosophy developed through the use of a systems approach, and the implementation of the fire protection program. Special emphasis is placed on the strategies employed in lieu of more traditional fire protection schemes and the stimuli for selecting them

  5. Flexural behaviour of partially bonded carbon fibre reinforced polymers strengthened concrete beams: Application to fire protection systems design

    International Nuclear Information System (INIS)

    Firmo, J.P.; Arruda, M.R.T.; Correia, J.R.; Tiago, C.

    2015-01-01

    Highlights: • The mechanical behaviour of partially bonded CFRP strengthened beams was modelled. • Two dimensional non-linear finite element models were developed. • Partially bonded beams can present similar flexural strength to fully bonded ones. • Relations between the bonded length and the strength reduction were proposed. • The proposed relations were used for the design of fire protection systems. - Abstract: Recent fire resistance tests on reinforced concrete (RC) beams strengthened with carbon fibre reinforced polymers (CFRP) laminates showed that it is possible to attain considerable fire endurance provided that thermal insulation is applied at the anchorage zones of the strengthening system. With such protection, although the CFRP laminate prematurely debonds in the central part of the beam, it transforms into a cable fixed at the extremities until one of the anchorage zones loses its bond strength. The main objective of this paper is to propose a simplified methodology for the design of fire protection systems for CFRP strengthened-RC beams, which is based on applying thicker insulation at the anchorage zones (promoting the above mentioned “cable behaviour”) and a thinner one at the current zone (avoiding tensile rupture of the carbon fibres). As a first step towards the validation of this methodology, finite element (FE) models were developed to simulate the flexural behaviour at ambient temperature of full-scale RC beams strengthened with CFRP laminates according to the externally bonded reinforcement (EBR) and near surface mounted (NSM) techniques, in both cases fully or partially bonded (the latter simulating the cable). The FE models were calibrated with results of 4-point bending tests on small-scale beams and then extended for different beam geometries, with spans (L) varying from 2 m to 5 m, in which the influence of the CFRP bonded length (l b ) and the loading type (point or uniformly distributed) on the strength reduction was

  6. 49 CFR 193.2801 - Fire protection.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Fire protection. 193.2801 Section 193.2801...: FEDERAL SAFETY STANDARDS Fire Protection § 193.2801 Fire protection. Each operator must provide and maintain fire protection at LNG plants according to sections 9.1 through 9.7 and section 9.9 of NFPA 59A...

  7. Fire Protection Informational Exchange

    Science.gov (United States)

    2016-07-01

    durable and launderable. A summary of contractor lead efforts to achieve these goals was presented. 3.19 US Naval Air Systems Command The NAVAIR fire... contractors spoke next concerning their companies’ technologies for fuel fire mitigation. Randy Fontinakes from Meggitt summarized his company’s products...decomprHalon FUS~ ht Surgeon’a Manual, USN: 0 Mdentlry, rapid d.eC)mpt"tMion • moct.rate .ctfvtty, rapkl decomprualon c: 0 Ill 5 1000 +- ph~lo4oglcal

  8. Fire Models and Design Fires

    DEFF Research Database (Denmark)

    Poulsen, Annemarie

    The aim of this project is to perform an experimental study on the influence of the thermal feedback on the burning behavior of well ventilated pre-flashover fires. For the purpose an experimental method has been developed. Here the same identical objects are tested under free burn conditions...... carried out by Carleton University and NRC-IRC performed on seven different types of fire loads representing commercial premises, comprise the tests used for the study. The results show that for some of the room test the heat release rate increased due to thermal feedback compared to free burn for a pre......-flashover fire. Two phenomena were observed, that relate well to theory was found. In an incipient phase the heat release rate rose with the temperature of the smoke layer/enclosure boundaries. This increase was also found to depend on the flammability properties of the burning object. The results also...

  9. 29 CFR 1926.150 - Fire protection.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 8 2010-07-01 2010-07-01 false Fire protection. 1926.150 Section 1926.150 Labor... (CONTINUED) SAFETY AND HEALTH REGULATIONS FOR CONSTRUCTION Fire Protection and Prevention § 1926.150 Fire protection. (a) General requirements. (1) The employer shall be responsible for the development of a fire...

  10. Particular features of fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Krueger, W.

    1985-01-01

    The particular features of fire protection in nuclear power plants that are connected with the need to ensure nuclear and radiation safety even during an emergency are outlined followed by the recommendation to lay them down in special fire protection standards. These, in conjunction with comprehensive fire hazard analyses, could serve to work out complex concepts for the fire protection of individual nuclear power plants. Such concepts would be very useful for review and assessment of the fire protection design during the licensing process and for later inspections. (author)

  11. Fire protection countermeasures for containment ventilation systems

    International Nuclear Information System (INIS)

    Alvares, N.J.; Beason, D.G.; Bergman, W.; Ford, H.W.; Lipska, A.E.

    1980-01-01

    The goal of this project is to find countermeasures to protect HEPA filters in exit ventilation ducts from the heat and smoke generated by fire. Several methods for partially mitigating the smoke exposure to the HEPA filters were identified through testing and analysis. These independently involve controlling the fuel, controlling the fire, and intercepting the smoke aerosol prior to its sorption on the HEPA filter. Exit duct treatment of aerosols is not unusual in industrial applications and involves the use of scrubbers, prefilters, and inertial impaction, depending on the size, distribution, and concentration of the subject aerosol. However, when these unmodified techniques were applied to smoke aerosols from fires on materials, common to experimental laboratories of LLNL, it was found they offered minimal protection to the HEPA filters. Ultimately, a continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. This technique is capable of protecting HEPA filters over the total duration of the test fires. The reason for success involved the modificaton of the prefiltration media. Commercially available filter media has a particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, we laminated rolling filter media with the desired properties. It is not true that the use of rolling prefilters solely to protect HEPA filters from fire-generated smoke aerosols is cost effective in every type of containment system, especially if standard fire-protection systems are available in the space. But in areas of high fire risk, where the potential fuel load is large and ignition sources are plentiful, the complication of a rolling prefilter in exit ventilation ducts to protect HEPA filters from smoke aerosols is definitely justified

  12. 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

  13. 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...

  14. 46 CFR 176.810 - Fire protection.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Fire protection. 176.810 Section 176.810 Shipping COAST...) INSPECTION AND CERTIFICATION Material Inspections § 176.810 Fire protection. (a) At each initial and... and have the vessel ready for inspection of its fire protection equipment, including the following: (1...

  15. 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)

  16. Fire protection countermeasures for containment ventilation systems

    International Nuclear Information System (INIS)

    Alvares, N.; Beason, D.; Bergman, V.; Creighton, J.; Ford, H.; Lipska, A.

    1980-01-01

    The goal of this project is to find countermeasures to protect High Efficiency Particulate Air (HEPA) filters, in exit ventilation ducts, from the heat and smoke generated by fire. Initially, methods were developed to cool fire-heated air by fine water spray upstream of the filters. It was recognized that smoke aerosol exposure to HEPA filters could also cause disruption of the containment system. Through testing and analysis, several methods to partially mitigate the smoke exposure to the HEPA filters were identified. A continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. The technique is capable of protecting HEPA filters over the total time duration of the test fires. The reason for success involved the modification of the prefiltration media. Commercially available filter media has particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, rolling filter media were laminated with the desired properties. The approach was Edisonian, but truncation in short order to a combination of prefilters was effective. The application of this technique was qualified, since it is of use only to protect HEPA filters from fire-generated smoke aerosols. It is not believed that this technique is cost effective in the total spectrum of containment systems, especially if standard fire protection systems are available in the space. But in areas of high-fire risk, where the potential fuel load is large and ignition sources are plentiful, the complication of a rolling prefilter in exit ventilation ducts to protect HEPA filters from smoke aerosols is definitely justified

  17. 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

  18. Fire protection guidelines for nuclear power plants, June 1976

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Guidelines acceptable to the NRC staff for implementing in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. Suitable bases and justification should be provided for alternative approaches to establish acceptable implementation of General Design Criterion 3

  19. General fire protection guidelines for egyptian nuclear facilities. Vol. 4

    Energy Technology Data Exchange (ETDEWEB)

    Radhad, S; Hussien, A Z; Hammad, F H [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt)

    1996-03-01

    The purpose of this paper is to establish the regulatory requirements of that will provide and ensure fire protection of egyptian nuclear facilities. Those facilities that use, handle and store low and/or medium radioactive substances are included. Two or more classes of occupancy are considered to occur in the same building or structure. Fir protection measures and systems were reviewed for three of the egyptian Nuclear facilities. These are egypt first nuclear reactor (ETRR-1) building and systems, hot laboratories buildings and facilities, and the building including the AECL type Is-6500 industrial cobalt-60 gamma irradiator {sup E}gypt`s mega gamma I{sup .} The study includes the outlines of the various aspects of fire protection with a view to define the relevant highlights and scope of egyptian guideline for nuclear installations. The study considers fire protection aspects including the following items: 1- Site selection. 2- General facility design. 3- Fire alarm, detection and suppression systems. (4- Protection for specific areas/control room, cable spreading room, computer room) 5- Fire emergency response planning. 6- Fire water supply. 7- Emergency lighting and communication. 8- Rescue and escape routes. 9- Explosion protection. 10-Manual fire fighting. 11- Security consideration in the interest of fire protection. 12- quality assurance programme. Therefore, first of all the design stage, then during the construction stage, and later during the operation stage, measures must be taken to forestall the risks associated with the outbreak of fire and to ensure that consequences of fire accidents remain limited.

  20. General fire protection guidelines for egyptian nuclear facilities. Vol. 4

    International Nuclear Information System (INIS)

    Radhad, S.; Hussien, A.Z.; Hammad, F.H.

    1996-01-01

    The purpose of this paper is to establish the regulatory requirements of that will provide and ensure fire protection of egyptian nuclear facilities. Those facilities that use, handle and store low and/or medium radioactive substances are included. Two or more classes of occupancy are considered to occur in the same building or structure. Fir protection measures and systems were reviewed for three of the egyptian Nuclear facilities. These are egypt first nuclear reactor (ETRR-1) building and systems, hot laboratories buildings and facilities, and the building including the AECL type Is-6500 industrial cobalt-60 gamma irradiator E gypt's mega gamma I . The study includes the outlines of the various aspects of fire protection with a view to define the relevant highlights and scope of egyptian guideline for nuclear installations. The study considers fire protection aspects including the following items: 1- Site selection. 2- General facility design. 3- Fire alarm, detection and suppression systems. 4- Protection for specific areas/control room, cable spreading room, computer room) 5- Fire emergency response planning. 6- Fire water supply. 7- Emergency lighting and communication. 8- Rescue and escape routes. 9- Explosion protection. 10-Manual fire fighting. 11- Security consideration in the interest of fire protection. 12- quality assurance programme. Therefore, first of all the design stage, then during the construction stage, and later during the operation stage, measures must be taken to forestall the risks associated with the outbreak of fire and to ensure that consequences of fire accidents remain limited

  1. Rx fire laws: tools to protect fire: the `ecological imperative?

    Science.gov (United States)

    Dale Wade; Steven Miller; Johnny Stowe; James Brenner

    2006-01-01

    The South is the birthplace of statutes and ordinances that both advocate and protect the cultural heritage of woods burning, which has been practiced in this region uninterrupted for more than 10,000 years. We present a brief overview of fire use in the South and discuss why most southern states recognized early on that periodic fire was necessary to sustain fire...

  2. 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...

  3. 14 CFR 25.854 - Lavatory fire protection.

    Science.gov (United States)

    2010-01-01

    ... AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY AIRPLANES Design and Construction Fire Protection § 25.854 Lavatory fire protection. For airplanes with a passenger capacity of 20 or more: (a) Each lavatory must be... disposal receptacle for towels, paper, or waste, located within the lavatory. The extinguisher must be...

  4. Planning for fire control and protection of personnel

    International Nuclear Information System (INIS)

    Rule, A.V.

    1989-01-01

    Because nuclear installations are designed and built to high standards with segregation and fire barriers included, the risk from fires is not high. However, small fires can become large and nuclear sites present additional hazards to fire fighters because of radiation release and from metal fires (magnesium alloys and sodium) which require special techniques of firefighting. All sites have their own fire fighting force which would tackle a fire initially and these should train and work in close cooperation with the Local Authority fire service. The main points raised concern radiation protection for the fire fighters including the issuing of emergency dosemeters and potassium iodate tablets, decontamination of personnel, vehicles and equipment, communications, and the need for standardisation of plans at all installations throughout the country. (U.K.)

  5. Aging assessment for active fire protection systems

    International Nuclear Information System (INIS)

    Ross, S.B.; Nowlen, S.P.; Tanaka, T.

    1995-06-01

    This study assessed the impact of aging on the performance and reliability of active fire protection systems including both fixed fire suppression and fixed fire detection systems. The experience base shows that most nuclear power plants have an aggressive maintenance and testing program and are finding degraded fire protection system components before a failure occurs. Also, from the data reviewed it is clear that the risk impact of fire protection system aging is low. However, it is assumed that a more aggressive maintenance and testing program involving preventive diagnostics may reduce the risk impact even further

  6. Fire prevention and protection for trackless equipment

    Energy Technology Data Exchange (ETDEWEB)

    Burger, A.J.

    1988-10-01

    With the increased use of trackless diesel and electrical equipment underground, the fire danger associated with this equipment has increased. The need for adequate fire prevention and protection on all aspects of trackless mechanised mining must be taken into consideration. This paper describes briefly the causes of fires on trackless equipment and the precautions taken to reduce the risk of ignition. 1 tab.

  7. The Calculation and Design of Fire suppression system in the proton accelerator research center

    International Nuclear Information System (INIS)

    Jeon, G. P.; Kim, J. Y.; Cho, J. H.; Min, Y. S.; Mun, K. J.; Cho, J. S.; Nam, J. M.; Park, S. S.; Joo, H. G.

    2010-01-01

    The fire protection system is composed of various fire suppression systems and fire detection and alarm systems. The primary function of the fire protection system is to protect life and property from a fire through detecting fires quickly and suppressing those fires that occur. In this paper, we described the fire suppression system only. The fire suppression system capacity for fire hydrant, the water mist system, sprinkler system and clean agent system is calculated and designed in compliance with the applicable Korean Acts that are applicable to fire protection and the NFSC code

  8. 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

  9. Designing fire safe interiors.

    Science.gov (United States)

    Belles, D W

    1992-01-01

    Any product that causes a fire to grow large is deficient in fire safety performance. A large fire in any building represents a serious hazard. Multiple-death fires almost always are linked to fires that grow quickly to a large size. Interior finishes have large, continuous surfaces over which fire can spread. They are regulated to slow initial fire growth, and must be qualified for use on the basis of fire tests. To obtain meaningful results, specimens must be representative of actual installation. Variables--such as the substrate, the adhesive, and product thickness and density--can affect product performance. The tunnel test may not adequately evaluate some products, such as foam plastics or textile wall coverings, thermoplastic materials, or materials of minimal mass. Where questions exist, products should be evaluated on a full-scale basis. Curtains and draperies are examples of products that ignite easily and spread flames readily. The present method for testing curtains and draperies evaluates one fabric at a time. Although a fabric tested alone may perform well, fabrics that meet test standards individually sometimes perform poorly when tested in combination. Contents and furnishings constitute the major fuels in many fires. Contents may involve paper products and other lightweight materials that are easily ignited and capable of fast fire growth. Similarly, a small source may ignite many items of furniture that are capable of sustained fire growth. Upholstered furniture can reach peak burning rates in less than 5 minutes. Furnishings have been associated with many multiple-death fires.(ABSTRACT TRUNCATED AT 250 WORDS)

  10. Nuclear power plant fire protection: fire detection (subsystems study Task 2)

    International Nuclear Information System (INIS)

    Berry, D.L.

    1977-12-01

    This report examines the adequacy of fire detection in the context of nuclear power plant safety. Topics considered are: (1) establishing area detection requirements, (2) selecting specific detector types, (3) locating and spacing detectors, and (4) performing installation tests and maintenance. Based on a thorough review of fire detection codes and standards and fire detection literature, the report concludes that current design and regulatory guidelines alone are insufficient to ensure satisfactory fire detection system performance. To assure adequate fire detection, this report recommends the use of in-place testing of detectors under conditions expected to occur normally in areas being protected

  11. 46 CFR 169.311 - Fire protection.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Fire protection. 169.311 Section 169.311 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) NAUTICAL SCHOOLS SAILING SCHOOL VESSELS Construction and Arrangement Hull Structure § 169.311 Fire protection. (a) The general construction of the vessel...

  12. 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

  13. Incineration process fire and explosion protection

    International Nuclear Information System (INIS)

    Ziegler, D.L.

    1975-01-01

    Two incinerators will be installed in the plutonium recovery facility under construction at the Rocky Flats Plant. The fire and explosion protection features designed into the incineration facility are discussed as well as the nuclear safety and radioactive material containment features. Even though the incinerator system will be tied into an emergency power generation system, a potential hazard is associated with a 60-second delay in obtaining emergency power from a gas turbine driven generator. This hazard is eliminated by the use of steam jet ejectors to provide normal gas flow through the incinerator system during the 60 s power interruption. (U.S.)

  14. 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.

  15. 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

  16. 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.

  17. 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

  18. The principles of protection against fires in nuclear facilities

    International Nuclear Information System (INIS)

    Dupuy, Ph.; Gupta, O.

    2000-01-01

    Because of the presence of fissile or radioactive materials in nuclear facilities, their protection against fires is different from that of classical industrial installations. 3 priorities have been defined, in importance order: 1) maintaining nuclear safety in order to protect public and environment, 2) protection of workers, and 3) limiting the damages on the installation. The prevention of fires is based on 4 rules: 1) limiting as much as possible the quantity of inflammable materials and imposing a strict control of any use of igniting source, 2) assuring a permanent monitoring of the installation by means of reliable devices able to detect any fire starting, 3) designing the sectorization of the installation in order to keep fire in delimited zones and prevent its extension, and 4) enhancing the efficiency of the fire brigade intervention. (A.C.)

  19. Fire Extinguisher Training for Fire Watch and Designated Workers, Course 9893

    Energy Technology Data Exchange (ETDEWEB)

    Harris, Jimmy D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-04-19

    At Los Alamos National Laboratory (LANL), all workers must be aware of LANL fire protection policies and be trained on what to do in the event of a fire. This course, Fire Extinguisher Training for Fire Watch and Designated Workers (#9893), provides awareness-level and hands-on training for fire watch personnel and designated workers. Fire watch personnel and designated workers are appointed by line management and must receive both awareness-level training and hands-on training in the use of portable fire extinguishers to extinguish an incipient-stage fire. This training meets the requirements of the Occupational Safety and Health Administration (OSHA) Code of Federal Regulations (CFR) 29 CFR 1910.157, Portable Fire Extinguishers, and Procedure (P) 101-26, Welding, Cutting, and Other Spark-/Flame-Producing Operations.

  20. Fire Extinguisher Designated Worker and Fire Watch: Self-Study Course 15672

    Energy Technology Data Exchange (ETDEWEB)

    Harris, Jimmy D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-07-08

    At Los Alamos National Laboratory (LANL), all workers must be aware of LANL fire protection policies and be trained on what to do in the event of a fire. This course, Fire Extinguisher Training for Fire Watch and Designated Workers (#9893), provides awareness-level and hands-on training for fire watch personnel and designated workers. Fire watch personnel and designated workers are appointed by line management and must receive both awareness-level training and hands-on training in the use of portable fire extinguishers to extinguish an incipient-stage fire. This training meets the requirements of the Occupational Safety and Health Administration (OSHA) Code of Federal Regulations (CFR) 29 CFR 1910.157, Portable Fire Extinguishers, and Procedure (P) 101-26, Welding, Cutting, and Other Spark-/Flame-Producing Operations.

  1. Fire protection for launch facilities using machine vision fire detection

    Science.gov (United States)

    Schwartz, Douglas B.

    1993-02-01

    Fire protection of critical space assets, including launch and fueling facilities and manned flight hardware, demands automatic sensors for continuous monitoring, and in certain high-threat areas, fast-reacting automatic suppression systems. Perhaps the most essential characteristic for these fire detection and suppression systems is high reliability; in other words, fire detectors should alarm only on actual fires and not be falsely activated by extraneous sources. Existing types of fire detectors have been greatly improved in the past decade; however, fundamental limitations of their method of operation leaves open a significant possibility of false alarms and restricts their usefulness. At the Civil Engineering Laboratory at Tyndall Air Force Base in Florida, a new type of fire detector is under development which 'sees' a fire visually, like a human being, and makes a reliable decision based on known visual characteristics of flames. Hardware prototypes of the Machine Vision (MV) Fire Detection System have undergone live fire tests and demonstrated extremely high accuracy in discriminating actual fires from false alarm sources. In fact, this technology promises to virtually eliminate false activations. This detector could be used to monitor fueling facilities, launch towers, clean rooms, and other high-value and high-risk areas. Applications can extend to space station and in-flight shuttle operations as well; fiber optics and remote camera heads enable the system to see around obstructed areas and crew compartments. The capability of the technology to distinguish fires means that fire detection can be provided even during maintenance operations, such as welding.

  2. Solution of Fire Protection in Historic Buildings

    Science.gov (United States)

    Iringová, Agnes; Idunk, Róbert

    2016-12-01

    The paper introduces optimization of the functional use of renovated spaces in historic buildings in terms of fire risk. It brings assessment of fire protection in the folk house Habánsky Dvor, situated in the village of Veľké Leváre, whose function was changed into the museum. It goes into static analysis of existing load-bearing structures and assessment of their fire resistance according to Eurocodes.

  3. 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...

  4. Sodium Fire Demonstration Facility Design and Operation

    International Nuclear Information System (INIS)

    Cho, Youngil; Kim, Jong-Man; Lee, Jewhan; Hong, Jonggan; Yeom, Sujin; Cho, Chungho; Jung, Min-Hwan; Gam, Da-Young; Jeong, Ji-Young

    2014-01-01

    Although sodium has good characteristics such as high heat transfer rate and stable nuclear property, it is difficult to manage because of high reactivity. Sodium is solid at the room temperature and it easily reacts with oxygen resulting in fire due to the reaction heat. Thus, sodium must be stored in a chemically stable place, i.e., an inert gas-sealed or oil filled vessel. When a sodium fire occurs, the Na 2 O of white fume is formed. It is mainly composed of Na 2 O 2 , NaOH, and Na 2 CO 3 , ranging from 0.1 to several tens of micrometers in size. It is known that the particle size increases by aggregation during floating in air. Thus, the protection method is important and should be considered in the design and operation of a sodium system. In this paper, sodium fire characteristics are described, and the demonstration utility of outbreak of sodium fire and its extinguishing is introduced. In this paper, sodium fire characteristics and a demonstration facility are described. The introduced sodium fire demonstration facility is the only training device used to observe a sodium fire and extinguish it domestically. Furthermore, the type of sodium fire will be diversified with the enhancement of the utility. It is expected that this utility will contribute to experience in the safe treatment of sodium by the handlers

  5. Fire protection in power plants

    International Nuclear Information System (INIS)

    Penot, J.

    1986-01-01

    Graphex-CK 23 is a unique sodium fire extinction product. Minimum amounts of powder are required for very fast action. The sodium can be put to use again, when the fire has been extinguished. It can be applied in other industrial branches and with other metals, e.g. sodium/potassium circuits or lithium coolant in power plants. [de

  6. Fire Resistance Tests of Various Fire Protective Coatings

    Directory of Open Access Journals (Sweden)

    Mindaugas GRIGONIS

    2011-03-01

    Full Text Available Tests were carried out on more than 14 different samples of fire protective coatings in order to investigate a relation between the thickness of the intumescent fire protection coating and the time of exposure to heat. A number of coatings of different chemical composition enabled to determine the fire resistance behaviour patterns. During test the one-side and volumetric methods were employed in observance of the standard temperature-time curves. For one-side method, the coating was applied on one side and all edges of the specimen, whereas for volumetric test the specimens were completely covered with fire protective coating. It is shown that a layer of coating protects the specimen's surface from heat exposure for a certain period of time until full oxidation of the coating occurs. The efficiency of fire protective coatings also depends on thickness of the charred layer of the side exposed to heat.http://dx.doi.org/10.5755/j01.ms.17.1.257

  7. Quality assurance through fire protection documentation

    Energy Technology Data Exchange (ETDEWEB)

    Spitzer, Franz [KAEFER Industrie GmbH, Kirchheim (Germany); Winter, Harald [Harald Winter Software, Unterschleissheim (Germany)

    2010-07-01

    Legal and organisational requirements regarding fire protection have become more and more stringent. In doing so owners must take account of public law and insurance law. A specialised fire protection management system - FiProMan - can assist in meeting these requirements quickly and efficiently by ensuring quality, carrying out subsequent installation work, repair work and making maintenance planable. In addition, the legal requirements of continuance are met. (orig.)

  8. Parametric Fires for Structural Design

    DEFF Research Database (Denmark)

    Hertz, Kristian

    2012-01-01

    The authorities, the construction association, and a number of companies in Denmark have supported the author writing a guide for design of building structures for parametric fires. The guide is published by the ministry as a supplement to the building regulations. However, consultants and contra......The authorities, the construction association, and a number of companies in Denmark have supported the author writing a guide for design of building structures for parametric fires. The guide is published by the ministry as a supplement to the building regulations. However, consultants...... and contractors have asked for a reference in English in order to make the guide-lines and the background for them available internationally. The paper therefore presents recommendations from the design guide especially concerning how to assess parametric design fires based on the opening factor method for large...... compartments. Findings leading to the guide-lines are discussed, and it is indicated what a safe design fire model means for structural design and how it differs from a safe design fire model for evacuation. Furthermore, the paper includes some experiences from the application of the design guide in practise...

  9. Stochastic representation of fire behavior in a wildland fire protection planning model for California.

    Science.gov (United States)

    J. Keith Gilless; Jeremy S. Fried

    1998-01-01

    A fire behavior module was developed for the California Fire Economics Simulator version 2 (CFES2), a stochastic simulation model of initial attack on wildland fire used by the California Department of Forestry and Fire Protection. Fire rate of spread (ROS) and fire dispatch level (FDL) for simulated fires "occurring" on the same day are determined by making...

  10. Fire protection of nuclear power plant cable ducts

    International Nuclear Information System (INIS)

    Kandrac, J.; Lukac, L.

    1987-01-01

    Fire protection of cable ducts in the Bohunice and Dukovany V-2 nuclear power plants is of a fourtier type. The first level consists in preventive measures incorporated in the power plant design and layout. The second level consists in early detection and a quick repressive action provided by an electric fire alarm system and a stationary spray system, respectively. Fire partitions and glands represent the third level while special spray, paint and lining materials represent the fourth level of the protection. Briefly discussed are the results of an analysis of the stationary spray system and the effects reducing the efficiency of a fire-fighting action using this system. The analysis showed the need of putting off cable duct fires using mobile facilities in case the stationary spray system cannot cope any longer. (Z.M.). 3 figs., 2 refs

  11. New probabilistic decision-making tools for fire protection systems

    International Nuclear Information System (INIS)

    Ksobiech, C.; Mowrer, F.

    1991-01-01

    The FIVE methodology provides guidance to utilities in performing an examination of potential plant severe accidents caused by fire initiated events. FIVE is oriented toward uncovering limiting plant design or operating characteristics (vulnerabilities) that make certain fire-initiated events more likely than others. It provides a combination of deterministic and probabilistic techniques for examining a power plant's fire probability and protection characteristics. It includes a two phase progressive screening method and a third phase consisting of a plant walkdown/verification process. The FIVE methodology centers on providing assurance of the availability of at least one train of the safe shutdown systems. FIVE has been developed for implementation by plant personnel who are most experienced with their plant's operations, fire hazards and fire protection features. The methodology provides these plant personnel with guidelines to quickly screen the plant down to the most significant locations where vulnerabilities may exist and then identify options to reduce the vulnerabilities

  12. 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

  13. Improvement of fire protection measures for nuclear power plants

    International Nuclear Information System (INIS)

    2012-01-01

    Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic tool to actual plants, With regard to fire tests for the fire data acquisition, cable fire test and oil fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, CFAST were implemented in order to analyze the fire progression phenomena, Trial simulation of fire hazard as Metal-Clad Switch Gear Fire of ONAGAWA NPP in Tohoku earthquake (HEAF accident). (author)

  14. Analysis of fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Hosser, D.; Schneider, U.

    1982-01-01

    Regulations and test specifications for fire prevention in nuclear power plants are presented as well as the fire protection measures in a newly constructed nuclear power plant. Although the emphasis is placed differently, all rules are based on the following single measures: Fire prevention, fire detection, fire fighting, fire checking, attack, flight, and rescue, organisational measures. (orig./GL) [de

  15. Training of fire protection personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Blaser, W.

    1980-01-01

    Training of fire protection personnel in nuclear power plants is divided up in three categories: training of fire protection commissioners which is mostly carried out externally; training of fire fighting personnel in the form of basic and repeated training usually by the fire protection commissioner; training of other employers with regard to behaviour in case of fire and during work involving a fire hazard. (orig.) [de

  16. Reliability Based Optimization of Fire Protection

    DEFF Research Database (Denmark)

    Thoft-Christensen, Palle

    fire protection (PFP) of firewalls and structural members. The paper is partly based on research performed within the EU supported research project B/E-4359 "Optimized Fire Safety of Offshore Structures" and partly on research supported by the Danish Technical Research Council (see Thoft-Christensen [1......]). Special emphasis is put on the optimization software developed within the project.......It is well known that fire is one of the major risks of serious damage or total loss of several types of structures such as nuclear installations, buildings, offshore platforms/topsides etc. This paper presents a methodology and software for reliability based optimization of the layout of passive...

  17. Fire protection in ventilation systems and in case of fire operating ventilation systems

    International Nuclear Information System (INIS)

    Zitzelsberger, J.

    1983-01-01

    The fire risks in ventilation systems are discussed. It follows a survey of regulations on fire prevention and fire protection in ventilation systems and smoke and heat exhaust systems applicable to nuclear installations in the Federal Republic of Germany. Fire protection concepts for normal systems and for systems operating also in case of fire will be given. Several structural elements for fire protection in those systems will be illustrated with regard to recent research findings

  18. Development of a risk informed fire protection program

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, J.; McDevitt, B.; Sawyer, O.; Volk, M.A.; Drennan, J.; Sweely, C.

    2015-07-01

    Over the past decade, one of the largest challenges for the Nuclear Power Plant (NPP) Operator in the United States has been the implementation of risk-informed, performance-based (RI-PB) fire protection strategies into their fire protection program. Regardless of whether a utility decides to fully transition their licensing basis from deterministic to risk based, or if they simply complete a fire probabilistic risk assessment (FPRA) in order to augment their current program, it is clear that risk-informed, performance based fire protection strategies and the associated challenges are the growing trend in the United States and are here to stay. The experience of the nuclear industry in the United States with the implementation of RI-PB fire protection strategies can provide a great deal of insight for plants and utilities that follow, either by choice or necessity, a similar path. The similarities in the design of the United States and Spanish nuclear plants make these insights even more significant contributions to the strategy and planning for the Spanish fleet. The experience in United States will provide guidance to avoid similar missteps and better plan for the challenges of the transition process. As the Spanish fleet develops risk-informed and deterministic strategies to improve fire safety, an understanding of the challenges and lessons learned from the United States experience will save time and money. (Author)

  19. Fire protection in the nuclear power plant

    International Nuclear Information System (INIS)

    Takuma, Masao

    1977-01-01

    According to the publication by US NRC, 32 fires have occurred in the nuclear power stations in operation, but most of them were small fire, and did not affect the safety of the nuclear power stations. The largest fire was that which occurred in the Browns Ferry Nuclear Power Station of TVA, USA, in March, 1976. It did not jeopardize the safety of the reactor facilities, and the leak of radioactive substance did not occur at all. But the investigation was made extensively by the joint committee of both houses, the government and others, and the deficiency in the countermeasures to fire was found, and it was clarified that some revision would by required on the standard applied heretofore. It was the valuable experience for improving further the safety of nuclear power stations. The fire occurred by the ignition of the polyurethane for sealing cable penetrations due to candle flame for testing. About 1600 cables were burned. When fire breaks out in a nuclear power station, it is necessary to stop and cool the reactor without fail, and to prevent the leak of radioactive substances definitely. In case of the fire in Browns Ferry, these requirements were fulfilled satisfactorily. The countermeasures on the basis of the experience in Browns Ferry and the design of the counterplan to fire in nuclear power stations are explained. (Kako, I.)

  20. Safety study of fire protection for nuclear fuel cycle facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Based on the investigation of fire protection standards for domestic and foreign nuclear facilities, the fire protection guideline for nuclear fuel cycle facility has been completed. In 2012, trial operation is started by private company using the guideline. In addition, the acquisition of fire evaluation data for a components (electric cable) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

  1. Safety study of fire protection for nuclear fuel cycle facility

    International Nuclear Information System (INIS)

    2013-01-01

    Based on the investigation of fire protection standards for domestic and foreign nuclear facilities, the fire protection guideline for nuclear fuel cycle facility has been completed. In 2012, trial operation is started by private company using the guideline. In addition, the acquisition of fire evaluation data for a components (electric cable) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

  2. WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Bigbee

    2000-06-21

    The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

  3. WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    J. D. Bigbee

    2000-01-01

    The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

  4. Improvement of fire protection measures for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic Tool to actual plants (FDT{sup S}), With regard to fire tests for the fire data acquisition, cable fire test and High Energy Arcing Faults (HEAF) fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, and CFAST were implemented in order to analyze the fire progression phenomena. Trial simulation of HEAF accident of Onagawa NPP in Tohoku earthquake. (author)

  5. 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)

  6. DOE Fire Protection Handbook, Volume I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The Department of Energy (DOE) Fire Protection Program is delineated in a number of source documents including; the Code of Federal Regulations (CFR), DOE Policy Statements and Orders, DOE and national consensus standards (such as those promulgated by the National Fire Protection Association), and supplementary guidance, This Handbook is intended to bring together in one location as much of this material as possible to facilitate understanding and ease of use. The applicability of any of these directives to individual Maintenance and Operating Contractors or to given facilities and operations is governed by existing contracts. Questions regarding applicability should be directed to the DOE Authority Having Jurisdiction for fire safety. The information provided within includes copies of those DOE directives that are directly applicable to the implementation of a comprehensive fire protection program. They are delineated in the Table of Contents. The items marked with an asterisk (*) are included on the disks in WordPerfect 5.1 format, with the filename noted below. The items marked with double asterisks are provided as hard copies as well as on the disk. For those using MAC disks, the files are in Wordperfect 2.1 for MAC.

  7. Effective fire protection for turbines ensures high operational availability; Wirksamer Brandschutz fuer Turbinen stellt hohe Verfuegbarkeit sicher

    Energy Technology Data Exchange (ETDEWEB)

    Knop, Arnd [Minimax GmbH und Co. KG, Bad Oldesloe (Germany). Div. Energy

    2013-10-01

    Designing fire protection in power plants is extremely complex and related to different requirements from operators, insurers, and experts. High- and low-pressure water mist systems are increasingly used in turbine fire protection, as they have ideal properties for this type of application. There are multifaceted fire risks in the areas adjacent to a turbine. Therefore, an overall view of all protected areas is indispensable for effective and reliable fire protection. The paper provides a detailed look at the entire spectrum of possible fire protection technologies for turbines and their adjacent areas, describes functionalities and itemises the benefits of individual fire protection measures. (orig.)

  8. Methodology for fire PSA during design process

    International Nuclear Information System (INIS)

    Kollasko, Heiko; Blombach, Joerg

    2009-01-01

    Fire PSA is an essential part of a full scope level 1 PSA. Cable fires play an important role in fire PSA. Usually, cable routing is therefore modeled in detail. During the design of new nuclear power plants the information on cable routing is not yet available. However, for the use of probabilistic safety insights during the design and for licensing purposes a fire PSA may be requested. Therefore a methodology has been developed which makes use of the strictly divisional separation of redundancies in the design of modern nuclear power plants: cable routing is not needed within one division but replaced by the conservative assumption that all equipment fails due to a fire in the concerned division; critical fire areas are defined where components belonging to different divisions may be affected by a fire. For the determination of fire frequencies a component based approach is proposed. The resulting core damage frequencies due to fire are conservative. (orig.)

  9. Constructive fire protection of steel corrugated beams of buildings and other structures

    Directory of Open Access Journals (Sweden)

    Ilyin Nikolay

    2017-01-01

    Full Text Available The research introduces a methodology of establishing indicators of fire safety of a building in relation to a guaranteed duration of steel fire-proof corrugated beams resistance in conditions of standard fire tests. Indicators of fire safety are also established in the assessment of design limits of steel fire-proof corrugated beams during design process, construction or maintenance of the building as well as in reducing economic costs when testing steel structures for fire resisting property. The suggested methodology introduces the system of actions aimed to design constructive fire protection of steel corrugated beams of buildings. Technological effect is achieved by conducting firing tests of steel construction by non-destructive methods; the evaluation of fire resistance of fire-proof elements of corrugated beams (corrugated web, upper and lower shelves is identified by the least fire-proof element of a welded I-beam. In this methodology fire resistance duration of the constituent elements of a welded I-beam with account of its fire protection ability is described with an analytic function taken as variables. These variables are intensity strength of stresses and the degree of fire protection of a compound element.

  10. Fire Propagation Performance of Intumescent Fire Protective Coatings Using Eggshells as a Novel Biofiller

    Directory of Open Access Journals (Sweden)

    M. C. Yew

    2014-01-01

    Full Text Available This paper aims to synthesize and characterize an effective intumescent fire protective coating that incorporates eggshell powder as a novel biofiller. The performances of thermal stability, char formation, fire propagation, water resistance, and adhesion strength of coatings have been evaluated. A few intumescent flame-retardant coatings based on these three ecofriendly fire retardant additives ammonium polyphosphate phase II, pentaerythritol and melamine mixed together with flame-retardant fillers, and acrylic binder have been prepared and designed for steel. The fire performance of the coatings has conducted employing BS 476: Part 6-Fire propagation test. The foam structures of the intumescent coatings have been observed using field emission scanning electron microscopy. On exposure, the coated specimens’ B, C, and D had been certified to be Class 0 due to the fact that their fire propagation indexes were less than 12. Incorporation of ecofriendly eggshell, biofiller into formulation D led to excellent performance in fire stopping (index value, (I=4.3 and antioxidation of intumescent coating. The coating is also found to be quite effective in water repellency, uniform foam structure, and adhesion strength.

  11. Report on task I: fire protection system study

    International Nuclear Information System (INIS)

    Bernard, E.A.; Cano, G.L.

    1977-02-01

    This study (1) evaluates, on a comparative basis, the national and international regulatory and insurance standards that serve as guidance for fire protection within the nuclear power industry; (2) analyzes the recommendations contained in the major reports on the Browns Ferry Fire; (3) proposes quantitative safety goals and evaluation methods for Nuclear Power Plant Fire Protection Systems (NPPFPS); (4) identifies potential improvements that may be incorporated into NPPFPS; and (5) recommends a plan of action for continuation of the fire protections systems study

  12. Regulatory point of view on defense in depth approach to fire protection in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Rinta-Filppula, Samu; Lehto, Matti; Vaelikangas, Pekka [Radiation and Nuclear Safety Authority STUK, Helsinki (Finland)

    2015-12-15

    The defense-in-depth (DiD) principle is a relatively new approach to fire protection design, even though DiD has been used in nuclear power plant (NPP) safety evaluation and design for decades (IAEA 75-INSAG-3, Rev. 1/INSAG-12). It is the main design criterion in fire protection in the latest edition of Finnish Radiation and Nuclear Safety Authority (STUK) issued guide YVL B.8 for the fire protection in nuclear facilities. The DiD approach to fire protection consists of four levels of defense: preventing the ignition of fires, detecting and extinguishing of ignited fires, preventing fire growth and spreading, confining the fire so that safety functions can be performed irrespective of the effects of the fire. The design of fire protection should take all these levels into account so that fire protection is well balanced and not dependent on a single fire protection factor or level of DiD. Despite being central to the design of fire protection, corresponding evaluations of DiD are done according to more or less unambiguous methods. The main goal of this study is to start the development of such, as much as possible, unambiguous systematic and logical method. First issue then is to build a picture of how fire safety features are executed on different levels of DiD and what is the corresponding safety importance to NPP. The Loviisa NPP was studied as an example case due to a long history of fire safety improvements since commissioning in 1977. The improvements are sorted qualitatively by their means of fire safety impact and level of DiD approach to fire protection and general plant DiD. The correspondence between the two DiD principles is an interesting issue which is discussed in this paper. Finally, Fire PRA is used to determine the safety importance of the improvements. The method proposed for the evaluation of DiD approach to fire protection is a combined ignition root cause analysis - event tree of fire scenario - consequential failure modes and effects analysis

  13. 29 CFR Appendix A to Subpart L of... - Fire Protection

    Science.gov (United States)

    2010-07-01

    ... dioxide, or dry chemical. Combustible metal (Class D hazards) fires pose a different type of fire problem... control this type of fire. Therefore, certain metals have specific dry powder extinguishing agents which... use on certain metal fires provide the best protection; however, there are also some “universal” type...

  14. 46 CFR 194.15-7 - Fire protection.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Fire protection. 194.15-7 Section 194.15-7 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OCEANOGRAPHIC RESEARCH VESSELS HANDLING, USE... § 194.15-7 Fire protection. (a) If a fixed or semiportable fire-fighting system is installed, it shall...

  15. Applications of Living Fire PRA models to Fire Protection Significance Determination Process in Taiwan

    International Nuclear Information System (INIS)

    De-Cheng, Chen; Chung-Kung, Lo; Tsu-Jen, Lin; Ching-Hui, Wu; Lin, James C.

    2004-01-01

    The living fire probabilistic risk assessment (PRA) models for all three operating nuclear power plants (NPPs) in Taiwan had been established in December 2000. In that study, a scenario-based PRA approach was adopted to systematically evaluate the fire and smoke hazards and associated risks. Using these fire PRA models developed, a risk-informed application project had also been completed in December 2002 for the evaluation of cable-tray fire-barrier wrapping exemption. This paper presents a new application of the fire PRA models to fire protection issues using the fire protection significance determination process (FP SDP). The fire protection issues studied may involve the selection of appropriate compensatory measures during the period when an automatic fire detection or suppression system in a safety-related fire zone becomes inoperable. The compensatory measure can either be a 24-hour fire watch or an hourly fire patrol. The living fire PRA models were used to estimate the increase in risk associated with the fire protection issue in terms of changes in core damage frequency (CDF) and large early release frequency (LERF). In compliance with SDP at-power and the acceptance guidelines specified in RG 1.174, the fire protection issues in question can be grouped into four categories; red, yellow, white and green, in accordance with the guidelines developed for FD SDP. A 24-hour fire watch is suggested only required for the yellow condition, while an hourly fire patrol may be adopted for the white condition. More limiting requirement is suggested for the red condition, but no special consideration is needed for the green condition. For the calculation of risk measures, risk impacts from any additional fire scenarios that may have been introduced, as well as more severe initiating events and fire damages that may accompany the fire protection issue should be considered carefully. Examples are presented in this paper to illustrate the evaluation process. (authors)

  16. Chemical Solutions of Fire Protection Problems

    Directory of Open Access Journals (Sweden)

    Vakhitova, L.M.

    2015-11-01

    Full Text Available The modern approaches to the creation of fire protective coatings by modifying intumescent systems by nanomaterials with study of the chemical reaction mechanisms under the high temperatures influence were considered. A systematic study of the interactions of components of polyphosphate type intumescent blend were carried out, a well-defined correlations between the directions of chemical processes and fire retardant properties of intumescent coatings were found. Efficient ways to simultaneous increase of fireprotective efficiency and performance characteristics of intumescent coatings (operatin life, resistance to environmental factors and bioсontamination were proposed. The results of fundamental research allowed to develop new formulations of flame retardant compositions, whose properties have been confirmed by tests in accordance with existing standardized methods, these results were introduced into production.

  17. 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.)

  18. Development of a Smart Residential Fire Protection System

    Directory of Open Access Journals (Sweden)

    Juhwan Oh

    2013-01-01

    Full Text Available Embedded system is applied for the development of smart residential fire detection and extinguishing system. Wireless communication capability is integrated into various fire sensors and alarm devices. The system activates the fire alarm to warn occupants, executes emergency and rescue calls to remote residents and fire-fighting facility in an intelligent way. The effective location of extra-sprinklers within the space of interest for the fire extinguishing system is also investigated. Actual fire test suggests that the developed wireless system for the smart residential fire protection system is reliable in terms of sensors and their communication linkage.

  19. A new design method for industrial portal frames in fire

    OpenAIRE

    Song, YY; Huang, Z; Burgess, IW; Plank, RJ

    2009-01-01

    For single-storey steel portal frames in fire, especially when they are situated close to a site perimeter, it is imperative that the boundary walls stay close to vertical, so that fires which occur are not allowed to spread to adjacent properties. A current UK fire design guide requires either that the whole frame be protected as a single element, or that the rafter may be left unprotected if column bases and foundations are designed to resist the forces and moments generated by rafter colla...

  20. Intelligent buildings, automatic fire alarm and fire-protection control system

    International Nuclear Information System (INIS)

    Tian Deyuan

    1999-01-01

    The author describes in brief the intelligent buildings, and the automatic fire alarm and fire-protection control system. On the basis of the four-bus, three-bus and two-bus, a new transfer technique was developed

  1. Fire fighting at Chernobyl and fire protection at UK nuclear power stations

    International Nuclear Information System (INIS)

    Bindon, F.J.L.

    1987-01-01

    The fire fighting measures undertaken by the fire crews at the Chernobyl reactor accident are described. This information highlights the need to develop engineering equipment which will give a far greater degree of personnel protection to fire crews and others in radiological accidents. The British position on fire protection at nuclear power stations is outlined. The general levels of radiation exposure which would be used as a guide to persons in the vicinity of a radiation accident are also given. (UK)

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

    OpenAIRE

    A. V. Zhovna

    2008-01-01

    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 docume...

  3. 46 CFR 194.20-7 - Fire protection.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Fire protection. 194.20-7 Section 194.20-7 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OCEANOGRAPHIC RESEARCH VESSELS HANDLING, USE... Fire protection. (a) Each chemical storeroom shall be protected by a fixed automatic carbon dioxide...

  4. 46 CFR 153.460 - Fire protection systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Fire protection systems. 153.460 Section 153.460... Requirements for Flammable Or Combustible Cargoes § 153.460 Fire protection systems. Each self-propelled ship... protection system listed beside the cargo in Table 1 and described in the footnotes to Table 1. (b) The...

  5. Modern tools to evaluate and optimize fire protection systems

    International Nuclear Information System (INIS)

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

    1980-01-01

    Modern techniques, such as fault tree analysis, can be used to obtain engineering descriptions of specific fire protection systems. The analysis allows establishment of an optimum level of fire protection, and evaluates the level of protection provided by various systems. A prime example: the application to fusion energy experiments

  6. 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....

  7. Factors Controlling Vegetation Fires in Protected and Non-Protected Areas of Myanmar

    Science.gov (United States)

    Biswas, Sumalika; Vadrevu, Krishna Prasad; Lwin, Zin Mar; Lasko, Kristofer; Justice, Christopher O.

    2015-01-01

    Fire is an important disturbance agent in Myanmar impacting several ecosystems. In this study, we quantify the factors impacting vegetation fires in protected and non-protected areas of Myanmar. Satellite datasets in conjunction with biophysical and anthropogenic factors were used in a spatial framework to map the causative factors of fires. Specifically, we used the frequency ratio method to assess the contribution of each causative factor to overall fire susceptibility at a 1km scale. Results suggested the mean fire density in non-protected areas was two times higher than the protected areas. Fire-land cover partition analysis suggested dominant fire occurrences in the savannas (protected areas) and woody savannas (non-protected areas). The five major fire causative factors in protected areas in descending order include population density, land cover, tree cover percent, travel time from nearest city and temperature. In contrast, the causative factors in non-protected areas were population density, tree cover percent, travel time from nearest city, temperature and elevation. The fire susceptibility analysis showed distinct spatial patterns with central Myanmar as a hot spot of vegetation fires. Results from propensity score matching suggested that forests within protected areas have 11% less fires than non-protected areas. Overall, our results identify important causative factors of fire useful to address broad scale fire risk concerns at a landscape scale in Myanmar. PMID:25909632

  8. Factors controlling vegetation fires in protected and non-protected areas of myanmar.

    Directory of Open Access Journals (Sweden)

    Sumalika Biswas

    Full Text Available Fire is an important disturbance agent in Myanmar impacting several ecosystems. In this study, we quantify the factors impacting vegetation fires in protected and non-protected areas of Myanmar. Satellite datasets in conjunction with biophysical and anthropogenic factors were used in a spatial framework to map the causative factors of fires. Specifically, we used the frequency ratio method to assess the contribution of each causative factor to overall fire susceptibility at a 1km scale. Results suggested the mean fire density in non-protected areas was two times higher than the protected areas. Fire-land cover partition analysis suggested dominant fire occurrences in the savannas (protected areas and woody savannas (non-protected areas. The five major fire causative factors in protected areas in descending order include population density, land cover, tree cover percent, travel time from nearest city and temperature. In contrast, the causative factors in non-protected areas were population density, tree cover percent, travel time from nearest city, temperature and elevation. The fire susceptibility analysis showed distinct spatial patterns with central Myanmar as a hot spot of vegetation fires. Results from propensity score matching suggested that forests within protected areas have 11% less fires than non-protected areas. Overall, our results identify important causative factors of fire useful to address broad scale fire risk concerns at a landscape scale in Myanmar.

  9. Factors controlling vegetation fires in protected and non-protected areas of myanmar.

    Science.gov (United States)

    Biswas, Sumalika; Vadrevu, Krishna Prasad; Lwin, Zin Mar; Lasko, Kristofer; Justice, Christopher O

    2015-01-01

    Fire is an important disturbance agent in Myanmar impacting several ecosystems. In this study, we quantify the factors impacting vegetation fires in protected and non-protected areas of Myanmar. Satellite datasets in conjunction with biophysical and anthropogenic factors were used in a spatial framework to map the causative factors of fires. Specifically, we used the frequency ratio method to assess the contribution of each causative factor to overall fire susceptibility at a 1km scale. Results suggested the mean fire density in non-protected areas was two times higher than the protected areas. Fire-land cover partition analysis suggested dominant fire occurrences in the savannas (protected areas) and woody savannas (non-protected areas). The five major fire causative factors in protected areas in descending order include population density, land cover, tree cover percent, travel time from nearest city and temperature. In contrast, the causative factors in non-protected areas were population density, tree cover percent, travel time from nearest city, temperature and elevation. The fire susceptibility analysis showed distinct spatial patterns with central Myanmar as a hot spot of vegetation fires. Results from propensity score matching suggested that forests within protected areas have 11% less fires than non-protected areas. Overall, our results identify important causative factors of fire useful to address broad scale fire risk concerns at a landscape scale in Myanmar.

  10. Fire protection maintenance at Browns Ferry Nuclear Plant

    International Nuclear Information System (INIS)

    Kern, J.R.

    1989-01-01

    This paper describes two approaches to staffing and organizing a fire protection maintenance group. Both have been used at Browns Ferry Nuclear Plant. One takes traditional craft functions and relocates them from the plant maintenance department to the fire protection section. The other expands the role to include response to fire, medical, and hazardous material emergencies. Both approaches remove the fire protection supervisor from a purely staff role, and involve him/her in direct-line management functions. This results in improved technical direction to the craftsmen, improved quality of the work performed, and improved craft morale. It also assures the fire protection supervisor of much more detailed knowledge of the overall status of the fire protection systems

  11. 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

  12. Appraisal of Passive and Active Fire Protection Systems in Student’s Accommodation

    Directory of Open Access Journals (Sweden)

    Ismail I.

    2014-03-01

    Full Text Available Fire protection systems are very important systems that must be included in buildings. They have a great significance in reducing or preventing the occurrences of fire. This paper presents an assessment of fire protection systems in student’s accommodation. Student accommodation is a particular type of building that provides shelter for students at University. In addition, it is also supposed to be an attractive environment, conducive to learning, and importantly, safe for occupation. The fire safety of occupants in a building, must be in accordance with the requirements of the building’s code. Therefore, the design of the building must comply with the Uniform Building By-Law (UBBL 1984 of Malaysia, and provide all of the required safety features. This paper describes the findings from investigations of passive and active fire protection systems installed in buildings, based on fire safety requirements, UBBL (1984.

  13. Perspective methods of fire and explosion protection of 'Ukrytie' object

    International Nuclear Information System (INIS)

    Zakhmatov, V.D.; Potikha, V.M.; Shkarabura, N.G.

    1999-01-01

    There are 5 atomic power stations in Ukraine-Chernobyl, Zaporozhe, Rivne, Khmelnytsk, Yuzhnoukrainsk. Fire statistics on them: 1993 - 5 fires, 1994 - 2, 1995 - 2, 1996 - 3, 1997-98 no fires. The most valuable unique experience, accumulated in Ukraine, -is extinguishing of different fires, arising in the radioactive zone. There were the following kinds of fires: burning roof of the 4-th bloc; forest fires; fires in cable tunnels; spilled oil in wrecked constructions and buildings. Professional impulse fire-extinguisher is one of the most perspective developments. These fire-extinguishers have high power, range and scale of action. They are universal: able to solve different tasks in extinguishing, to decontaminate, for group and individual light and heat protection, for preventing explosions of dust and gas of up to 50 m 3 volume and in the open space

  14. Numerical case studies of vertical wall fire protection using water spray

    Directory of Open Access Journals (Sweden)

    L.M. Zhao

    2014-11-01

    Full Text Available Studies of vertical wall fire protection are evaluated with numerical method. Typical fire cases such as heated dry wall and upward flame spread have been validated. Results predicted by simulations are found to agree with experiment results. The combustion behavior and flame development of vertical polymethylmethacrylate slabs with different water flow rates are explored and discussed. Water spray is found to be capable of strengthening the fire resistance of combustible even under high heat flux radiation. Provided result and data are expected to provide reference for fire protection methods design and development of modern buildings.

  15. CFES--California Fire Economics Simulator: A Computerized System for Wildland Fire Protection Planning

    Science.gov (United States)

    Jeremy S. Fried; J. Keith Gilless; Robert E. Martin

    1987-01-01

    The University of California's Department of Forestry and Resource Management, under contract with the California Department of Forestry and Fire Protection, has developed and released the first version of the California Fire Economics Simulator (CFES). The current release is adapted from the Initial Action Assessment component of the USFS's National Fire...

  16. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Wright, H.A.

    1981-01-01

    This lecture describes briefly the chronological order of events which may arise for a very serious emergency situation in a nuclear power plant for which preparations should be made even though the situation has an extremely low probability of happening. The planning and preparedness required are expected to cope with a whole spectrum of emergency situations, from minor accidents to serious plant failures which also lead to releases of significant quantities of radioactive material beyond the site boundary. Fire protection aspects will be briefly covered, and some guidance will be provided on exercises to ensure the plans are feasible and the appropriate personnel and facilities are in a satisfactory state of preparedness. (orig./RW)

  17. Passive fire building protection system evaluation (case study: millennium ict centre)

    Science.gov (United States)

    Rahman, Vinky; Stephanie

    2018-03-01

    Passive fire protection system is a system that refers to the building design, both regarding of architecture and structure. This system usually consists of structural protection that protects the structure of the building and prevents the spread of fire and facilitate the evacuation process in case of fire. Millennium ICT Center is the largest electronic shopping center in Medan, Indonesia. As a public building that accommodates the crowd, this building needs a fire protection system by the standards. Therefore, the purpose of this study is to evaluate passive fire protection system of Millennium ICT Center building. The study was conducted to describe the facts of the building as well as direct observation to the research location. The collected data is then processed using the AHP (Analytical Hierarchy Process) method in its weighting process to obtain the reliability value of passive fire protection fire system. The results showed that there are some components of passive fire protection system in the building, but some are still unqualified. The first section in your paper

  18. 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...

  19. Special Report on Lessons Learned (1985-2011). Volume 2: Handbook of Recommended Design Practices (Fire Protection and Life Safety Design Guidelines for Special Purpose Underground Structures)

    Science.gov (United States)

    2012-10-01

    threaten transportation tunnels. Refer to NFPA 502, “Standards for Road Tunnels, Bridges and other Limited Access Highways” and some of the newer... Pendant or upright sprinkler heads (except deluge heads) should be protected by wire cages at locations where human activity could easily hit the head or... bridged by this UFC. UFC 3-601-02 provides a single integrated manual that answers the questions of what and when to test it for just about every type of

  20. Defence-in-depth strategy of fire protection and its relevance after final shutdown (by the example of Germany)

    Energy Technology Data Exchange (ETDEWEB)

    Beesen, Michael; Ernst, Benjamin; Fischer, Guenter [TUeV SUeD Industrie Service GmbH (Germany)

    2015-12-15

    Nuclear power plants (NPP) are protected against internal and external fires by a fire protection defence-in-depth concept including the following precautionary measures: operational, structural and equipment related fire protection measures as well as manual fire fighting. The fire protection measures are designed in consideration of fires to be expected (from fire loads permanently and temporarily present together with potential ignition sources) in order to prevent a violation of both the protection goals of public law and the nuclear protection goals / radiological safety objectives in case of internal and external fires. The aspect ''What is the future significance of the fire protection defence-in-depth concept?'' needs to be considered with regard to the situation following the final shutdown. From our point of view as a TSO (technical safety organization) both the non-nuclear protection goals (e.g. prevent occurrence of a fire; ensure escape and rescue of humans) as well as the nuclear ones have to be ensured after final shutdown of a nuclear plant. The protection goals of public law will almost completely remain after the plant has stopped commercial operation while the nuclear safety objectives will be stepwise reduced in consideration of the decommissioning status until the end of the nuclear supervision. Nevertheless, the fire protection concept must clearly specify those fire protection measures that are necessary to ensure the plants' safety. The situation on site regularly needs to be under examination to check if the fire protection concept covers all conditions to be considered and if the existing fire protection measures are sufficient or if an adaption is necessary.

  1. 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.

  2. Literature study regarding fire protection in nuclear power plants. Part 2: Fire detection and -extinguishing systems

    International Nuclear Information System (INIS)

    Isaksson, S.

    1996-01-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Detection and extinguishing systems in Swedish nuclear power plants have only to a limited extent been designed after functional demands, such as a maximum acceptable damage or a maximum time to detect a fire. The availability of detection systems is difficult to assess, partly because of lack of statistics. The user interface is very important in complex systems as nuclear plants. An extinguishing system designed according to the insurance companies' regulations will only fulfill the basic demands. It should be noted that normal sprinkler design does not aim for extinguishing fires, the objective is to control fire until manual extinguishment is possible. There is a great amount of statistics on wet and dry pipe sprinkler systems, while statistics are more scarce for deluge systems. The statistics on the reliability of gaseous extinguishing systems have been found very scarce. A drawback of these systems is that they are normally designed for one shot only. There are both traditional and more recent extinguishing systems that can replace halons. From now on there will be a greater need for a thorough examination of the properties needed for the individual application and a quantification of the acceptable damage. There are several indications on the importance of a high quality maintenance program as well as carefully developed routines for testing and surveillance to ensure the reliability of detection and extinguishing systems. 78 refs, 8 figs, 10 tabs

  3. Fire protection of safe shutdown capability at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Sullivan, K.

    1993-01-01

    The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the U.S. are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and composites important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50)

  4. Still a hot issue. US fire protection 20 years on

    International Nuclear Information System (INIS)

    Hathaway, L.R.

    1995-01-01

    Current fire protection concerns in the US nuclear industry are reviewed. Twenty years ago, a fire at the Brown's Ferry nuclear plant triggered a vigorous programme of regulation by the US Nuclear Regulatory Commission (NRC) and a still active response by power plant operators in seeking protection measures to meet the NRC criteria. The largest fire protection issue facing the industry concerns Thermo-Lag, a product formed from resins, subliming materials and fibreglass. This fire resistant wrap was installed in about 75 plants to provide a barrier between safety related cable systems. The Brown's Ferry fire has re-emphasised the importance of the separation criteria between redundant safety systems. Since 1989, however, there have been doubts about the adequacy of Thermo-Lag barriers and a major testing and analysis project addressing the problem is currently being sponsored by six utilities. Other regulatory- related issues facing the industry are the recently proposed defence-in-depth fire protection methodology, and for the future, fire protection strategies to cover shutdown, turbine generators and penetration seals through fire barriers. (UK)

  5. Optimization of investment economic in PCI using the methodology of benefits design in analysis of the spread of fires with FDS (Fire Dynamics Simulator) in areas of nuclear fire

    International Nuclear Information System (INIS)

    Salellas, J.

    2015-01-01

    Fire simulation analysis allows knowing the evolution and spread fire in areas of interest within a NPP such as control room, cable room and multi zone comportment among others. fires are a main concern regarding safety analysis of NPP. IDOM has the capability to carry out fire simulations, taken in to account smoke control, fire spread, toxicity levels, ventilation and all physical phenomena. As a result, appropriate fire protection measures can be assessed in each scenario. CFD tools applied to fire simulations can determine with higher resolution all damages caused during the fire. Furthermore, such tools can reduce costs due to a lower impact of design modifications. (Author)

  6. Fire protection in Angra-2 nuclear power plant. The use of fire protection collars on plastic piping systems

    International Nuclear Information System (INIS)

    Oliveira Segabinaze, R. de

    1994-01-01

    The object of this paper is to briefly the use of fire protection collars on plastic piping systems passing through wall and floor penetration. The fire protection collars consist of a stainless steel housing, in which the leading edges of two pivoting plates are in constant pressure contact with the pipe. In case of fire these plates react on the softened pipe with a guillotine action, thereby stopping the flow; within the housing a foam material expands to fill the space when subject to the heat of the fire. The piping project has to be modified to permit the fixing of the collars to walls and floor penetrations. (author). 2 refs, 9 figs

  7. United States position paper on sodium fires, design and testing

    International Nuclear Information System (INIS)

    Hilliard, R.K.; Johnson, R.P.

    1983-01-01

    The first Specialists' Meeting on sodium fire technology sponsored by the International Working Group on Fast Reactors (IWGFR) was held in Richland, Washington in 1972. The group concluded that the state-of-technology at that time was inadequate to support the growing LMFBR industry. During the second IWGFR Specialists' Meeting on sodium fires, held in Cadarache, France in 1978, a large quantity of technical information was exchanged and areas were identified where additional work was needed. Advances in several important areas of sodium fire technology have been made in the United States since that time, including improved computer codes, design of a sodium fire protection system for the CRBRP, measurement of water release from heated concrete, and testing and modeling of the sodium-concrete reaction. Research in the U.S. related to sodium fire technology is performed chiefly at the Energy Systems Group of Rockwell International (including Atomics International), the Hanford Engineering Development Laboratory (HEDL), and the Sandia National Laboratories (SNL). The work at the first two laboratories is sponsored by the U.S. Department of Energy, while that at the latter is sponsored by the U.S. Nuclear Regulatory Commission. Various aspects of sodium fire related work is also performed at several other laboratories. The current status of sodium fire technology in the U.S. is summarized in this report

  8. Designing radiation protection signs

    International Nuclear Information System (INIS)

    Rodriguez, M.A.; Richey, C.L.

    1995-01-01

    Entry into hazardous areas without the proper protective equipment is extremely dangerous and must be prevented whenever possible. Current postings of radiological hazards at the Rocky Flats Environmental Technology Site (RFETS) do not incorporate recent findings concerning effective warning presentation. Warning information should be highly visible, quickly, and easily understood. While continuing to comply with industry standards (e.g., Department of Energy (DOE) guidelines), these findings can be incorporated into existing radiological sign design, making them more effective in terms of usability and compliance. Suggestions are provided for designing more effective postings within stated guidelines

  9. Reserves protect against deforestation fires in the Amazon.

    Directory of Open Access Journals (Sweden)

    J Marion Adeney

    Full Text Available BACKGROUND: Reserves are the principal means to conserve forests and biodiversity, but the question of whether reserves work is still debated. In the Amazon, fires are closely linked to deforestation, and thus can be used as a proxy for reserve effectiveness in protecting forest cover. We ask whether reserves in the Brazilian Amazon provide effective protection against deforestation and consequently fires, whether that protection is because of their location or their legal status, and whether some reserve types are more effective than others. METHODOLOGY/PRINCIPAL FINDINGS: Previous work has shown that most Amazonian fires occur close to roads and are more frequent in El Niño years. We quantified these relationships for reserves and unprotected areas by examining satellite-detected hot pixels regressed against road distance across the entire Brazilian Amazon and for a decade with 2 El Niño-related droughts. Deforestation fires, as measured by hot pixels, declined exponentially with increasing distance from roads in all areas. Fewer deforestation fires occurred within protected areas than outside and the difference between protected and unprotected areas was greatest near roads. Thus, reserves were especially effective at preventing these fires where they are known to be most likely to burn; but they did not provide absolute protection. Even within reserves, at a given distance from roads, there were more deforestation fires in regions with high human impact than in those with low impact. The effect of El Niño on deforestation fires was greatest outside of reserves and near roads. Indigenous reserves, limited-use reserves, and fully protected reserves all had fewer fires than outside areas and did not appear to differ in their effectiveness. CONCLUSIONS/SIGNIFICANCE: Taking time, regional factors, and climate into account, our results show that reserves are an effective tool for curbing destructive burning in the Amazon.

  10. Reserves Protect against Deforestation Fires in the Amazon

    Science.gov (United States)

    Adeney, J. Marion; Christensen, Norman L.; Pimm, Stuart L.

    2009-01-01

    Background Reserves are the principal means to conserve forests and biodiversity, but the question of whether reserves work is still debated. In the Amazon, fires are closely linked to deforestation, and thus can be used as a proxy for reserve effectiveness in protecting forest cover. We ask whether reserves in the Brazilian Amazon provide effective protection against deforestation and consequently fires, whether that protection is because of their location or their legal status, and whether some reserve types are more effective than others. Methodology/Principal Findings Previous work has shown that most Amazonian fires occur close to roads and are more frequent in El Niño years. We quantified these relationships for reserves and unprotected areas by examining satellite-detected hot pixels regressed against road distance across the entire Brazilian Amazon and for a decade with 2 El Niño-related droughts. Deforestation fires, as measured by hot pixels, declined exponentially with increasing distance from roads in all areas. Fewer deforestation fires occurred within protected areas than outside and the difference between protected and unprotected areas was greatest near roads. Thus, reserves were especially effective at preventing these fires where they are known to be most likely to burn; but they did not provide absolute protection. Even within reserves, at a given distance from roads, there were more deforestation fires in regions with high human impact than in those with low impact. The effect of El Niño on deforestation fires was greatest outside of reserves and near roads. Indigenous reserves, limited-use reserves, and fully protected reserves all had fewer fires than outside areas and did not appear to differ in their effectiveness. Conclusions/Significance Taking time, regional factors, and climate into account, our results show that reserves are an effective tool for curbing destructive burning in the Amazon. PMID:19352423

  11. Wildland Fire Research: Water Supply and Ecosystem Protection

    Science.gov (United States)

    Research is critical to better understand how fires affect water quality and supply and the overall health of an ecosystem. This information can be used to protect the safety of drinking water and assess the vulnerability of water supplies.

  12. Cold Vacuum Drying (CVD) Facility, Diesel Generator Fire Protection

    International Nuclear Information System (INIS)

    SINGH, G.

    2000-01-01

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Fire Protection and Detection System installed by Project W-441 (Cold Vacuum Drying Facility and Diesel Generator Building) functions as required by project specifications

  13. Cold Vacuum Drying (CVD) Facility, Diesel Generator Fire Protection

    CERN Document Server

    Singh, G

    2000-01-01

    This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Fire Protection and Detection System installed by Project W-441 (Cold Vacuum Drying Facility and Diesel Generator Building) functions as required by project specifications.

  14. Nuclear Power Plant Fire Protection Research Program

    International Nuclear Information System (INIS)

    Datta, A.

    1985-07-01

    The goal is to develop test data and analytical capabilities to support the evaluation of: (1) the contribution of fires to the risk from nuclear power plants; (2) the effects of fires on control room equipment and operations; and (3) the effects of actuation of fire suppression systems on safety equipment. A range of fire sources will be characterized with respect to their energy and mass evolution, including smoke, corrosion products, and electrically conductive products of combustion. An analytical method for determining the environment resulting from fire will be developed. This method will account for the source characteristics, the suppression action following detection of the fire, and certain parameters specific to the plant enclosure in which the fire originates, such as the geometry of the enclosure and the ventilation rate. The developing local environment in the vicinity of safety-related equipment will be expressed in terms of temperatures, temperature rise rates, heat fluxes, and moisture and certain species content. The response of certain safe shutdown equipment and components to the environmental conditions will be studied. The objective will be to determine the limits of environmental conditions that a component may be exposed to without impairment of its ability to function

  15. 78 FR 55765 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...

    Science.gov (United States)

    2013-09-11

    ... Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Draft..., ``Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN-FIRE).'' In... caused by impaired fire protection features at nuclear power plants. The report documents the history of...

  16. 78 FR 45573 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...

    Science.gov (United States)

    2013-07-29

    ... Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... Nuclear Power Plant Fire Protection (CARMEN-FIRE), Draft Report for Comment.'' DATES: Comments on this... caused by impaired fire protection features at nuclear power plants. The report documents the history of...

  17. Diesel generator fire protection: getting the balance right

    International Nuclear Information System (INIS)

    Enzmann, Hans; Swiss Reinsurance Co., Zurich)

    1986-01-01

    A wide range of different approaches to the fire protection of diesel generators can be found in nuclear power plants around the world. In some cases there is too little protection. In others there is far too much, such that fire prevention has been overemphasised at the expense of diesel generator operability and overall nuclear safety. A risk assessment check list developed in Switzerland could help to achieve the right balance. (author)

  18. 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

  19. Intumescent paint as fire protection coating

    Directory of Open Access Journals (Sweden)

    R. B. R.S. OLIVEIRA

    Full Text Available Abstract This paper is a compendium on intumescent paint and its main features regarding chemical composition, thermophysical properties and performance as a fire-retardant material. Some of the main technical publications and lines of research on the subject are presented herein. The purpose of this paper is to show the current stage of the technical research being conducted on the topic and enable a better understanding of this fire-retardant material.

  20. Literature study regarding fire protection in nuclear power plants. Part I: Fire rated separations

    International Nuclear Information System (INIS)

    Isaksson, S.

    1995-06-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Conventional building codes can not give guidance on where to make fire rated separations in order to separate redundant trains of safety systems. The separation must originate in functional demands from the authorities on what functions are essential during and after a fire, and under what circumstances these functions shall be retained, i.e. the number of independent faults and initiating events. As a basic demand it is suggested to rate the strength of separations according to conventional building code, based on fire load. The whole separating construction shall have the same fire rating, including the ventilation system. Deviations from the basic demand can de done in case it can be proven that it is possible to compensate some or all of the fire rating with other measures. There is a general lack of statistical information regarding the reliability of fire separating constructions such as walls, fire doors, penetration seals and fire dampers. The amount of cables penetrating a seal is in many cases much higher in real installations than what has been tested for type approval. It would therefore be valuable to perform a furnace test with a more representative amount of cables passing through a penetration seal. Tests have shown that the 20 foot horizontal separation distance stipulated by NRC is not a guarantee against fire damage. Spatial separations based on general requirements shall not be allowed, but considered from case to case based on actual circumstances. For fire protection by isolation or coatings, it is of great importance to choose the method of protection carefully, to be compatible with the material it shall be applied on, and the environment and types of fire that may occur. 48 refs, 2 figs, 5 tabs

  1. A conceptual framework for formulating a focused and cost-effective fire protection program based on analyses of risk and the dynamics of fire effects

    International Nuclear Information System (INIS)

    Dey, M.K.

    1999-01-01

    This paper proposes a conceptual framework for developing a fire protection program at nuclear power plants based on probabilistic risk analysis (PRA) of fire hazards, and modeling the dynamics of fire effects. The process for categorizing nuclear power plant fire areas based on risk is described, followed by a discussion of fire safety design methods that can be used for different areas of the plant, depending on the degree of threat to plant safety from the fire hazard. This alternative framework has the potential to make programs more cost-effective, and comprehensive, since it will allow a more systematic and broader examination of fire risk, and provide a means to distinguish between high and low risk fire contributors. (orig.)

  2. Fire protection at hot laboratories: Prevention, surveillance and fire-fighting

    International Nuclear Information System (INIS)

    Chappellier, A.M.

    1976-01-01

    After pointing out that fire in a hot laboratory can be an important factor contributing to a radioactivity accident, the author briefly recalls the items to be taken into account in a fire hazard analysis. He then describes various important aspects of prevention, detection and fire-fighting which - at the French Commissariat a l'Energie Atomique - are governed by already defined rules or by guidelines which are sufficiently advanced to give a clear idea of the final conclusions to be drawn therefrom. From the point of view protection, the concept of fire sector has been evolved, at hot laboratories, becomes the fire and contamination sector, so as to ensure under all circumstances the containment of any radioactive materials dispersed in the premises on fire. Regarding fire detection, a study should be made on the constraints specific to the facility and liable to affect detector operation. These include ventilation, radiations, neutral or corrosive atmosphere, etc. As regards fire-fighting, two particular aspects are dealt with, namely the question of using water in case of fire and action to be taken concerning ventilation. A practical example - the protection of a ventilation system - is described. In conclusion the paper refers to the need for a thorough analysis specific to each hot laboratory, and to the importance of preparing an operational plan so as to avoid any dangerous improvisations in case of an accident. (author)

  3. Fire protection of safe shutdown capability at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Sullivan, K.

    1993-01-01

    The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the US are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and components important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50). Since 1983, various members of the Department of Nuclear Energy (DNE) at Brookhaven National Laboratory (BNL) have provided technical assistance to the Nuclear Regulatory Commission (NRC) in support of its evaluations of fire protection features implemented at commercial nuclear power stations operated in the US. This paper presents a discussion of the insights gained by the author during his active participation in this area

  4. International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

    International Nuclear Information System (INIS)

    The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

  5. An Expert System for Designing Fire Prescriptions

    Science.gov (United States)

    Elizabeth Reinhardt

    1987-01-01

    Managers use prescribed fire to accomplish a variety of resource objectives. The knowledge needed to design successful prescriptions is both quantitative and qualitative. Some of it is available through publications and computer programs, but much of the knowledge of expert practitioners has never been collected or published. An expert system being developed at the,...

  6. Human physiology as the determining factor in protective clothing design

    NARCIS (Netherlands)

    Daanen, Hein

    2014-01-01

    Protective clothing is designed to protect humans against risks like fire, chemicals or blunt impact. Although protect¡ve clothing diminishes the effects of external risks, it may hinder people in functioning and it may also introduce new (internal) risks. Manufacturers are often not aware of the

  7. The radiation protection units of the Austrian fire brigades

    International Nuclear Information System (INIS)

    Aspek, W.; Schoenhacker, S.

    2009-01-01

    Since the 1960s, Austrian fire brigades have been involved in radiation protection. With the preparations for the NPP Zwentendorf and the building of the research reactor in Seibersdorf, the first radiation protection units of the fire brigade were founded. 45 years later: The NPP Zwentendorf never saw its start-up, the use of nuclear energy for the production of electricity is prohibited by a constitutional law, and the research reactor is being decommissioned. What's left are the radiation protection units of the fire brigades. The contribution gives an overview of similarities and differences of the radiation protection units in the nine federal states of Austria, with a special focus on equipment, training and organisation. Nation-wide guidelines and regulations for the tactics of first responders at radiological emergencies are presented and a couple of incidents will be analysed. (orig.)

  8. 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

  9. Challenges to fire protection measures at Hamaoka Nuclear Power Station

    International Nuclear Information System (INIS)

    Narama, Takeshi

    2015-01-01

    New regulatory standards for fire protection at nuclear power plants have been established by the Nuclear Regulation Authority. This paper introduces the measures taken by the Hamaoka Nuclear Power Station for the following four items, which were especially big changes. (1) To install a combination of sensors of different types or instruments with equivalent functions so as to be able to emit unique signals to inform a fire in the early stage. (2) To conduct 'UL vertical burn test' as the demonstration test for self-extinguishing performance as the condition for flame-retardant cable. (3) To install automatic fire-extinguishers or fixed fire-extinguishing devices of manual type at the spots where fire-fighting is difficult due to the filling of smoke in a fire or the effect of radiation. (4) To separate the system for purpose of ensuring safety function to attain the high-temperature shutdown and cold-temperature shutdown of a reactor whatever fire may happen at the nuclear facilities. The examples of the installation of fire-extinguishers as the measures for the above Item (3) are as follows; (A) as for the devices containing oil, a foam-extinguishing agent is released against each target device from the nozzle, and (B) for large vertical pump motors indoors and relatively small pump motors, IA type automatic foam extinguishing systems are installed. (A.O.)

  10. Water Supply Systems For Aircraft Fire And Rescue Protection

    Science.gov (United States)

    1995-01-01

    This Advisory Circular (AC) provides guidance for the selection : of a water source and standards for the design of a distribution system to : support aircraft rescue and fire fighting (ARFF) service operations on : airports.

  11. The usage of phase change materials in fire fighter protective clothing: its effect on thermal protection

    Science.gov (United States)

    Zhao, Mengmeng

    2017-12-01

    The thermal protective performance of the fire fighter protective clothing is of vital importance for fire fighters. In the study fabrics treated by phase change materials (PCMs) were applied in the multi-layered fabrics of the fire fighter protective clothing ensemble. The PCM fabrics were placed at the different layers of the clothing and their thermal protective performance were measured by a TPP tester. Results show that with the application of the PCM fabrics the thermal protection of the multi-layered fabrics was greatly increased. The time to reach a second degree burn was largely reduced. The location of the PCM fabrics at the different layers did not affect much on the thermal protective performance. The higher amount of the PCM adds on, the higher thermal protection was brought. The fabrics with PCMs of a higher melting temperature could contribute to higher thermal protection.

  12. Improvement of flame resistance of non-flame retardant cables by applying fire protection measures

    International Nuclear Information System (INIS)

    Takemura, Yujiro; Segoshi, Yoshinori; Jinno, Susumu; Mii, Kazuki

    2017-01-01

    The new regulatory requirements, which were put in force after the Fukushima Daiichi accident, impose the use of flame retardant cables on the plant components having safety functions for the purpose of fire protection. However, some Japanese nuclear power plants built in the early days use non-flame retardant cables that do not pass the demonstration test to check for the flame resistance. To cope with the new regulatory requirements, a fire protection measure for non-flame retardant cables was introduced to assure flame resistance of non-flame retardant cables equivalent to or higher than that of flame retardant cables. To illustrate the fire protection measure, both non-flame retardant cables and its cable tray are covered with fire protection sheet fabricated from incombustible material to form an assembly. Considering the demonstration test results, it can be concluded that flame resistance performance of non-flame retardant cables equivalent to or higher than that of flame retardant cables can be assured by forming the assembly even if an external fire outside the assembly and internal cable fire inside the assembly are assumed. This paper introduces the design of the assembly consisting of a bundle of cables and a cable tray and summarizes the results of demonstration tests. (author)

  13. Optimization of investment economic in PCI using the methodology of benefits design in analysis of the spread of fires with FDS (Fire Dynamics Simulator) in areas of nuclear fire; Optimizacion de la inversion economica en PCI mediante la metodologia de diseo prestaional en el analisis de la propagacion de incendios con FDS (Fire Dynnamics Simulator) en areas de fuego de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Salellas, J.

    2015-07-01

    Fire simulation analysis allows knowing the evolution and spread fire in areas of interest within a NPP such as control room, cable room and multi zone comportment among others. fires are a main concern regarding safety analysis of NPP. IDOM has the capability to carry out fire simulations, taken in to account smoke control, fire spread, toxicity levels, ventilation and all physical phenomena. As a result, appropriate fire protection measures can be assessed in each scenario. CFD tools applied to fire simulations can determine with higher resolution all damages caused during the fire. Furthermore, such tools can reduce costs due to a lower impact of design modifications. (Author)

  14. Development of fire protection standards for the EPR project

    International Nuclear Information System (INIS)

    Frank, H.J.; Kaercher, M.; Wittmann, R.

    2000-01-01

    In 1989 Framatome and Siemens decided by setting up their joint subsidiary NPI (Nuclear Power International) to co-operate in designing a new European Pressurised Water Reactor, the EPR. French and German utilities decided to participate in this project. In parallel to the co-operation on supplier's and utility's side, the French and German safety authorities and safety experts wanted to work closely together in order to harmonise and further develop the outstanding safety standards in France and Germany. An organisation has been set up to elaborate common codes related to the EPR design, at the level of the French design and construction rules (RCC) of the German KTA safety standards and DIN standards for nuclear technology, the so-called EPR technical codes (ETC). In this context the decision was made to develop a new fire protection code, the ETC-F, which should be harmonised between France and Germany. The article gives an insight in the developing process of the ETC-F and an outlook on existing and perhaps further national activities. (orig.) [de

  15. Prove of structural fire design in nuclear power plants

    International Nuclear Information System (INIS)

    Schneider, U.; Hosser, D.; Max, U.

    1986-01-01

    Based on the application of comprehensive heat balance calculations the whole parameters like geometry, fire load, ventilation conditions etc. of a German PWR were covered. A practical design procedure based on diagrams was developed whereby separate diagrams for oil and cable fires were presented. A probabilistic safety concept was employed as to account for the specific variations of fire parameters as fire load and area, ventilation condition, rate of burning. With respect to the frequency of fire occurrences and the impact of fire fighting measures on the spread of fires latest statistical data of a special BMI investigation were used. (orig./HP) [de

  16. Monitoring of fire incidences in vegetation types and Protected ...

    Indian Academy of Sciences (India)

    two types of sensor data, i.e., AWiFS and MODIS, have found fires in 281 (out of 614) Protected Areas of India. .... 56 m resolution prepared as part of national car- bon project has ...... and its deficiency in India were pointed out as back- ground.

  17. Rules for preventing chemical risks: fire protection

    International Nuclear Information System (INIS)

    1985-02-01

    The Fundamental Safety Rules applicable to certain types of nuclear installation are intended to clarify the conditions of which observance, for the type of installation concerned and for the subject that they deal with, is considered as equivalent to compliance with regulatory French technical practice. These Rules should facilitate safety analysises and the clear understanding between persons interested in matters related to nuclear safety. They in no way reduce the operator's liability and pose no obstacle to statutory provisions in force. For any installation to which a Fundamental Safety Rule applies according to the foregoing paragraph, the operator may be relieved from application of the Rule if he shows proof that the safety objectives set by the Rule are attained by other means that he proposes within the framework of statutory procedures. Furthermore, the Central Service for the Safety of Nuclear Installations reserves the right at all times to alter any Fundamental Safety Rule, as required, should it deem, this necessary, while specifying the applicability conditions. The present rule defines the dispositions to take in account for avoid fire hazards in nuclear facilities (Power reactors and accelerators are excluded) [fr

  18. Fire protection: no fire without smoke. CCTV breakthrough in fire detection

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    A new CCTV-based fire detection system uses advanced software to detect and locate smoke and vapour from a fire before it becomes visible to the human eye, but is intelligent enough to avoid false alarms due to steam, moving machinery or operating staff in the monitored area. The starting point for the development effort was video motion detection software as used in the security industry. (author)

  19. Designing physical protection technology for insider protection

    International Nuclear Information System (INIS)

    Trujillo, A.A.; Waddoups, I.G.

    1986-01-01

    Since its inception, the nuclear industry has been engaged in providing protection against an insider threat. Although insider protection activities have been fairly successful in the past, present societal conditions require increased protection to further minimize the existence of an insider or the consequences of an insider-perpetrated incident. Integration of insider protection techniques into existing administrative and operational procedures has resulted in economic and operational impacts. Future increases in insider protection may result in even greater impacts, so we must proceed wisely as new approaches are developed. Increased emphasis on background investigations, security clearances, human reliability programs, security awareness activities, and the development of technology to address the insider threat are evidence of continuing concern in this area. Experience ranging from operational test and evaluation of developmental equipment to conceptual designs for new facilities has led to the development of general principles and conclusions for mitigating the insider threat while minimizing adverse impacts on site operations. Important principles include real-time monitoring of personnel and material and requiring that the physical protection and material control and accounting systems to be much more coordinated and integrated than in the past

  20. Dampers, fluidics and the failsafe fallacy [fire protection

    International Nuclear Information System (INIS)

    Dann, M.; Hodgson, T.

    1989-01-01

    The fire protection practices adopted at nuclear power stations generally follow the well established principles used throughout industry. Unfortunately, there is one particular area - the interaction with heating, ventilation and air conditioning (HVAC) services - where nuclear power stations pose a seemingly insoluble conflict: that between the need to contain and the need to ventilate. Now, however, solid state fire dampers using power fluidics may promise a solution. One of the key characteristics of a fluidic device is that it is 'solid state', i.e. it has no moving parts. Because of this, its inherent reliability is orders of magnitude greater than a mechanical device. (U.K.)

  1. Strategy and system of fire protection at Guangdong Daya Bay Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zhou Weihong

    1999-12-01

    The fire protection is an important safety issue of nuclear power utilities. The author depicts the strategy and management system of fire protection implemented successfully at Guangdong Daya Bay Nuclear Power Plant of China

  2. Mine shaft fire and smoke protection systems - an update on hardware development and in-mine testing

    International Nuclear Information System (INIS)

    Johnson, G.A.

    1982-01-01

    In 1976, The Bureau of Mines developed a prototype system to sense and extinguish fires in shafts and shaft stations in underground metal and nonmetal mines. Subsequent work modified this technology to include fueling areas, spontaneous combustion zones and coal mines. This paper updates IC-8783 ''In-mine Fire Tests of Mine Shaft Fire and Smoke Protection Systems'', which was published in 1978 and summarized the design and in-mine, actual fire testing of the first prototype mine shaft fire and smoke protection system. This paper also updates related work from IC-8775 ''Spontaneous Oxidation and Combustion of Sulfide Ores in Underground Mines, (also published in 1978) and IC-8808 ''In-mine Evaluation of Underground Fire and Smoke Detectors'', (published in early 1979)

  3. 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...

  4. Fire and the Design of Educational Buildings. Building Bulletin 7. Sixth Edition.

    Science.gov (United States)

    Department of Education and Science, London (England).

    This bulletin offers guidance on English school premises regulations applying to safety protection against fires in the following general areas: means of escape in case of fire; precautionary measures to prevent fire; fire warning systems and fire fighting; fire spreading speed; structures and materials resistant to fires; and damage control. It…

  5. The correspondence concerning fire protection regulation for operating reactors (separation flame test of unpurified cables)

    International Nuclear Information System (INIS)

    Hasegawa, Takayasu; Miyakoshi, Hirohisa; Goto, Masami

    2013-01-01

    Nuclear power plants are taking fire protection measures taking into account past findings about the effects of fire by the demonstration test in order to maintain the safety of nuclear power plant in the event of a fire. The objective of the demonstration test described in this paper is to obtain advanced knowledge about over current fire of unqualified cable to be applied to fire protection measures. (author)

  6. Probabilistic evaluation of fire protection features found in nuclear power plants

    International Nuclear Information System (INIS)

    Azarm, M.A.; Boccio, J.L.; Ruger, C.

    1985-01-01

    This paper describes a method which can be used to evaluate, on a relative basis, the NRC Fire Protection (FP) guidelines as found in Section 9.5.1 (Fire Protection) of the Standard Review Plan (SRP). The approach, a hybrid of existing physical models for fire propagation determinations and probabilistic models for fire-mitigation system reliability, can potentially be used as an adjunct to the present fire safety review process

  7. Radiation protection/shield design

    International Nuclear Information System (INIS)

    Disney, R.K.

    1977-01-01

    Radiation protection/shielding design of a nuclear facility requires a coordinated effort of many engineering disciplines to meet the requirements imposed by regulations. In the following discussion, the system approach to Clinch River Breeder Reactor Plant (CRBRP) radiation protection will be described, and the program developed to implement this approach will be defined. In addition, the principal shielding design problems of LMFBR nuclear reactor systems will be discussed in realtion to LWR nuclear reactor system shielding designs. The methodology used to analyze these problems in the U.S. LMFBR program, the resultant design solutions, and the experimental verification of these designs and/or methods will be discussed. (orig.) [de

  8. Fire protection assessment in a WANO peer review

    International Nuclear Information System (INIS)

    Vella, R.

    1998-01-01

    The peer review programme is becoming the key programme of WANO. The reviews are conducted to assess the performance of plant personnel, the conditions of systems and equipment, the quality of programmes and procedures, and the effectiveness of plant management. The review team consists of highly qualified staff from other WANO members throughout the world who have extensive practical experience in the area the review. At the request of Paris Centre Members, the fire protection area has been added to the scope of WANO peer reviews. Relevant performance objectives and criteria have been developed to cover this area, these are written guidances upon which review of plant performance can be based. They are supported by criteria, more narrow in scope, to help further define what attributes of the fire protection management area contribute to the achievement of the associated performance objective. (author)

  9. EDV supported dynamic fire protection concept adaptation during dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Mummert, Maxi; Traichel, Anke; Dilger, Matthias

    2013-01-01

    Fire protection concepts are supposed to be a decision guide for the definition of measures and priorities in fire fighting and fire prevention. In case of reactor dismantling a fire protection concept for the actual status is required. Following the fuel removal from the reactor the protection goals are reduced to the safe confinement of radioactive materials and the restriction of radiation exposure. A dynamic fire protection concept was developed to allow the compliance with the required protection measures with respect to the protection targets. The implementation of the dynamic fire protection concept simplifies the planning of the dismantling steps and to adjust the fire protection measured in the frame of changes in the plant.

  10. Corrosion protection pays off for coal-fired power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, T.

    2006-11-15

    Zinc has long been used to hot-dip galvanise steel to deliver protection in harsh environments. Powder River Basin or eastern coal-fired plants benefit from using galvanized steel for conveyors, vibratory feeders, coal hoppers, chutes, etc. because maintenance costs are essentially eliminated. When life cycle costs for this process are compared to an alternative three-coal paint system for corrosion protection, the latter costs 5-10 times more than hot-dip galvanizing. An AEP Power Plant in San Juan, Puerto Rico and the McDuffie Coal Terminal in Mobile, AL, USA have both used hot-dip galvanized steel. 1 fig., 1 tab.

  11. An evaluation of risk methods for prioritizing fire protection features: a procedure for fire barrier penetration seals

    International Nuclear Information System (INIS)

    Dey, M.K.

    2004-01-01

    This paper generally evaluates risk methods available for prioritizing fire protection features. Risk methods involving both the use of qualitative insights, and quantitative results from a fire probabilistic risk analysis are reviewed. The applicability of these methods to develop a prioritized list of fire barrier penetration seals in a plant based on risk significance is presented as a procedure to illustrate the benefits of the methods. The paper concludes that current fire risk assessment methods can be confidently used to prioritize plant fire protection features, specifically fire barrier penetration seals. Simple prioritization schemes, using qualitative assessments and insights from fire PRA methodology may be implemented without the need for quantitative results. More elaborate prioritization schemes that allow further refinements to the categorization process may be implemented using the quantitative results of the screening processes in good fire PRAs. The use of the quantitative results from good fire PRAs provide several benefits for risk prioritization of fire protection features at plants, mainly from the plant systems analyses conducted for a fire PRA

  12. The improvement of the fire protections system for nuclear cycle facilities. Formulation of a fire protection guideline for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    2012-04-01

    The private side Fire Protection Guideline was investigated with respect to the fire having taken place at the nuclear reactor site followed by the Chuetsu-Oki earthquake in Niigata Prefecture in 2007. To improve the fire protection system especially applicable to MOX fuel fabrication facilities, JNES (Japan Nuclear Energy Safety Organization) investigated private guidelines adopted in Japanese Light Water cooled Reactors, the standardized guidelines used in Nuclear Facilities in other countries including USA, and the standards in the chemical plants. The content of the guideline concerns the prevention of the fire breakout, the prevention of fire extension, the reduction of the fire effects, as well as the facility-characteristic protection countermeasures and the fire effect evaluations. (S. Ohno)

  13. Advanced analysis and design for fire safety of steel structures

    CERN Document Server

    Li, Guoqiang

    2013-01-01

    Advanced Analysis and Design for Fire Safety of Steel Structures systematically presents the latest findings on behaviours of steel structural components in a fire, such as the catenary actions of restrained steel beams, the design methods for restrained steel columns, and the membrane actions of concrete floor slabs with steel decks. Using a systematic description of structural fire safety engineering principles, the authors illustrate the important difference between behaviours of an isolated structural element and the restrained component in a complete structure under fire conditions. The book will be an essential resource for structural engineers who wish to improve their understanding of steel buildings exposed to fires. It is also an ideal textbook for introductory courses in fire safety for master’s degree programs in structural engineering, and is excellent reading material for final-year undergraduate students in civil engineering and fire safety engineering. Furthermore, it successfully bridges th...

  14. Fire protection at the Fast Flux Test Facility (a sodium cooled test reactor)

    International Nuclear Information System (INIS)

    Bell, J.R.

    1980-01-01

    For purposes of this presentation, fire protection at the FFTF is subdivided into two catagories; protection for non-sodium areas and protection for areas containing sodium. Fire protection systems and philosophies for non-sodium areas at the FFTF are very similar to those used at conventional power plants being constructed throughout the country. They follow, essentially, the NRC rules and guidelines and ANSI 59.4 Generic Requirements for Light Water Nuclear Power Plant Fire Protection. The FFTF with its support facilities have their own water system comprised of a looped 8'' and 10'' underground distribution system, three 1500 GPM fire pumps and three ground level storage tanks totaling 736,000 gallons with 420,000 reserved for fire protection. Fire hydrants are enclosed with hose houses outfitted for use by the Emergency Response Team (ERT). Fire prevention systems for sodium areas of the FFTF are also described

  15. Potentials and limitations of remote fire monitoring in protected areas.

    Science.gov (United States)

    Dos Santos, João Flávio Costa; Romeiro, Joyce Machado Nunes; de Assis, José Batuíra; Torres, Fillipe Tamiozzo Pereira; Gleriani, José Marinaldo

    2018-03-01

    Protected areas (PAs) play an important role in maintaining the biodiversity and ecological processes of the site. One of the greatest challenges for the PA management in several biomes in the world is wildfires. The objective of this work was to evaluate the potentialities and limitations of the use of data obtained by orbital remote sensing in the monitoring fire occurrence in PAs. Fire Occurrence Records (FORs) were analyzed in Serra do Brigadeiro State Park, Minas Gerais, Brazil, from 2007 to 2015, using photo interpreted data from TM, ETM + and OLI sensors of the Landsat series and the Hot Spot Database (HSD) from the Brazilian Institute of Space Research - INPE. It was also observed the time of permanence of the scar left by fire on the landscape, through the multitemporal analysis of the behavior of NDVI (Normalized Difference Vegetation Index) and NBR (Normalized Burn Ratio) indexes, before and after the occurrence. The greatest limitation found for the orbital remote monitoring was the presence of clouds in the passage of the sensor in dates close to the occurrence of the fires. The burned area identified by photo interpretation was 54.9% less than the area contained in the FOR. Although the HSD reported fire occurrences in the buffer zone (up to 10km from the Park), no FORs were found at a distance greater than 1100m from the boundaries of the PA. As the main potential of remote sensing, the possibility of identifying burned areas throughout the park and surroundings is highlighted, with low costs and greater accuracy. Copyright © 2017 Elsevier B.V. All rights reserved.

  16. SMART core protection system design

    International Nuclear Information System (INIS)

    Lee, J. K.; Park, H. Y.; Koo, I. S.; Park, H. S.; Kim, J. S.; Son, C. H.

    2003-01-01

    SMART COre Protection System(SCOPS) is designed with real-tims Digital Signal Processor(DSP) board and Network Interface Card(NIC) board. SCOPS has a Control Rod POSition (CRPOS) software module while Core Protection Calculator System(CPCS) consists of Core Protection Calculators(CPCs) and Control Element Assembly(CEA) Calculators(CEACs) in the commercial nuclear plant. It's not necessary to have a independent cabinets for SCOPS because SCOPS is physically very small. Then SCOPS is designed to share the cabinets with Plant Protection System(PPS) of SMART. Therefor it's very easy to maintain the system because CRPOS module is used instead of the computer with operating system

  17. An assessment of the fire protection requirements throughout a NPP life related to current IAEA regulations and American, Canadian and UE regulations

    International Nuclear Information System (INIS)

    Branzeu, N.; Necula, D.; Badea, M.; Teodorescu, D.; Peteu, M.

    2006-01-01

    Statistics on fires has surprisingly shown that the frequency of fires in a nuclear power plant are as high as in the conventional industrial units. The analyses on fires occurred in a NPP need to consider both their well-known severe damages and the nuclear consequences. In 1975 a severe fire occurred in BROWNS FERRY NPP due to the ignition of the polyurethane foam used in the electric cable penetration sealings. The fire propagated to the cable channels and damaged over 1600 cables. The fire event revealed important shortcomings in the fire protection design and procedures. The fire represented a crucial event that changed fundamentally the fire protection regulation in the United States nuclear industry. The fire protection programs, standards and guides currently applied, have been developed on basis of this fire analysis and gained conclusions/experience. The purpose of the article is to be a short presentation of the fire protection requirements for all NPP life stages (i.e. design, construction, commissioning, operation and decommissioning), including the most recent issues of the standards, codes, guides and regulations in US, Canada, IAEA and some European countries. Such documentation represented the main technical support in establishing the national fire protection standard design regarding all the stages of a CANDU-6 NPP life, all the types of operational NPPs, particularly for Cernavoda NPP Unit 1 and Unit 2 (now in an advanced stage of construction). In order to satisfy the requirements provided by this documentation, as practically as possible, a list of analyses and fire protection improvement measures for Cernavoda NPP is presented. (authors)

  18. Adsorber fires

    International Nuclear Information System (INIS)

    Holmes, W.

    1987-01-01

    The following conclusions are offered with respect to activated charcoal filter systems in nuclear power plants: (1) The use of activated charcoal in nuclear facilities presents a potential for deep-seated fires. (2) The defense-in-depth approach to nuclear fire safety requires that if an ignition should occur, fires must be detected quickly and subsequently suppressed. (3) Deep-seated fires in charcoal beds are difficult to extinguish. (4) Automatic water sprays can be used to extinguish fires rapidly and reliably when properly introduced into the burning medium. The second part of the conclusions offered are more like challenges: (1) The problem associated with inadvertent actuations of fire protection systems is not a major one, and it can be reduced further by proper design review, installation, testing, and maintenance. Eliminating automatic fire extinguishing systems for the protection of charcoal adsorbers is not justified. (2) Removal of automatic fire protection systems due to fear of inadvertent fire protection system operation is a case of treating the effect rather than the cause. On the other hand, properly maintaining automatic fire protection systems will preserve the risk of fire loss at acceptable levels while at the same time reducing the risk of damage presented by inadvertent operation of fire protection systems

  19. Fire protection programme during construction of the Chashma nuclear power plant

    International Nuclear Information System (INIS)

    Mian Umer, M.

    1998-01-01

    A clear view is given of several measures that have been taken with regard to fire prevention, protection and fire fighting during all phases of the construction, installation and commissioning of the Chasma nuclear power plant to protect personnel and equipment so that any delays in plant operation as a result of fire incident can be avoided. These measures include the precautions taken, the provisions made for fire extinguishers and hydrants, and the setting up of a fire brigade. An overview is also given of the fire incidents that have occurred. (author)

  20. Fire behavior sensor package remote trigger design

    Science.gov (United States)

    Dan Jimenez; Jason Forthofer; James Reardon; Bret Butler

    2007-01-01

    Fire behavior characteristics (such as temperature, radiant and total heat flux, 2- and 3-dimensional velocities, and air flow) are extremely difficult to measure insitu. Although insitu sensor packages are capable of such measurements in realtime, it is also essential to acquire video documentation as a means of better understanding the fire behavior data recorded by...

  1. Upgrading of fire protection arrangements at Magnox power stations in the United Kingdom

    International Nuclear Information System (INIS)

    Zhu, L.H.

    1998-01-01

    The methodology used in conducting fire hazard assessments at Magnox Reactor power stations operated by Magnox Electric plc is described. The assessments use a deterministic approach. This includes the identification of essential plant and the associated supporting systems required for the safe trip, shutdown and post-trip cooling of the reactor, assessment of the location of the essential plant and the vulnerability of these plant in the presence of a fire, assessment of essential functions against the effects of a fire and identification of improvements to the fire protection arrangements. Practical aspects of fire protection engineering on operating power stations are discussed and examples of improvements in protection described. (author)

  2. Thermal Radiation for Structural Fire Safety Design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2006-01-01

    The lecture notes give a short introduction of the theory of thermal radiation. The most elementary concepts and methods are presented in order to give a fundamental knowledge for calculation of the load bearing capacities of fire exposed building constructions....

  3. Design and Construction of Oil Fired Compact Crucible Furnace ...

    African Journals Online (AJOL)

    As a prelude to necessary industrialization, foundries are springing up in various parts of Nigeria and most of these foundries rely on oil fired furnaces in their operation. This study is aimed at developing an oil fired crucible furnace from locally sourced materials for foundries in Nigeria. In our design, a new system of fuel ...

  4. 30 CFR 77.1916 - Welding, cutting, and soldering; fire protection.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Welding, cutting, and soldering; fire... OF UNDERGROUND COAL MINES Slope and Shaft Sinking § 77.1916 Welding, cutting, and soldering; fire protection. (a) One portable fire extinguisher shall be provided where welding, cutting, or soldering with...

  5. 77 FR 74381 - Protection of Stratospheric Ozone: Listing of Substitutes for Ozone Depleting Substances-Fire...

    Science.gov (United States)

    2012-12-14

    ... Protection of Stratospheric Ozone: Listing of Substitutes for Ozone Depleting Substances--Fire Suppression... a companion proposed rule issuing listings for three fire suppressants under EPA's Significant New... companion proposed rule issuing listings for three fire suppressants under EPA's Significant New...

  6. Optimization of fire protection measures and quality controls in nuclear power plants

    International Nuclear Information System (INIS)

    Brenig, H.; Holtschmidt, H.; Liemersdorf, H.; Suetterlin, L.; Dobbernack, R.; Hahn, C.; Hosser, D.; Kordina, K.; Schneider, U.; Sprey, W.; Wesche, H.

    1985-09-01

    This study presents theoretical and experimental investigations on the evaluation of fire hazards and the optimization of fire protection measures in German nuclear power plants. Differences between the method presented here and the US ''Fire Hazard Analysis'' result from the inclusion of the stringent redundancy concept of German nuclear power plants and the emphasis placed on passive structural fire protection measures. The method includes a time-dependent quantification of fire-specific event sequences. Fire occurrence frequencies and the reliabilities of active fire protection measures were derived from German experiences and literature abroad. The reliability data of passive fire protection measures were obtained by an evaluation of experiments and probabilistic analyses. For the calculation of fire sequences fundamental experiments were taken into consideration. For the quantification of the time-dependent event trees a methodology was applied which permits an evaluation of the influence of the individual measures. The consequences of fire were investigated for ten fire events identified as decisive, and the fire sequence paths important in terms of safety were quantified. Their annual frequencies are within a range of 10 -3 to 8.10 -6 . (orig./HP) [de

  7. Japanese studies on sodium fires, design and testing

    International Nuclear Information System (INIS)

    Mitsutsuka, N.; Yoshida, N.

    1983-01-01

    Considerations of sodium fires are very important for the design and licensing of LMFBRs. Continuing effort has been made in the study of sodium fires and their consequences since the beginning of the Japanese fast breeder reactor development program. Recent effort is mainly focussed on studies related to Monju, especially on the design and testing of primary cell liners against large sodium spills. Experimental and analytical studies on sodium fires, water release from concrete and sodium concrete reactions are conducted as a part of this study. Some extinguishing agents are also tested against sodium fires. In addition, considerable effort is being made in the development of detection systems for the small sodium leaks before a pipe rupture. This paper briefly summarizes the Japanese status of these sodium fire related activities conducted by Fast Breeder Reactor Development Project of the Power Reactor and Nuclear Fuel Development Corporation (PNC)

  8. Fire protection at the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Molnarova, Zuzana; Zeman, Peter

    2009-01-01

    A succinct account is given of current situation in fire prevention at the Mochovce NPP and of past fire events. The fact is stressed that no fire ever occurred at any technological facility of the plant since the startup of the reactor units. Steps required to improve fire safety at a nuclear power plant are highlighted. (orig.)

  9. Designing Data Protection Safeguards Ethically

    Directory of Open Access Journals (Sweden)

    Ugo Pagallo

    2011-03-01

    Full Text Available Since the mid 1990s, lawmakers and scholars have worked on the idea of embedding data protection safeguards in information and communication technology (ICT with the aim to access and control personal data in compliance with current regulatory frameworks. This effort has been strengthened by the capacities of computers to draw upon the tools of artificial intelligence (AI and operations research. However, work on AI and the law entails crucial ethical issues concerning both values and modalities of design. On one hand, design choices might result in conflicts of values and, vice versa, values may affect design features. On the other hand, the modalities of design cannot only limit the impact of harm-generating behavior but also prevent such behavior from occurring via self-enforcement technologies. In order to address some of the most relevant issues of data protection today, the paper suggests we adopt a stricter, yet more effective version of “privacy by design.” The goal should be to reinforce people’s pre-existing autonomy, rather than having to build it from scratch.

  10. 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

  11. Study on aging management of fire protection system in nuclear power plant

    International Nuclear Information System (INIS)

    Fang Huasong; Du Yu; Li Jianwen; Shi Haining; Tu Fengsheng

    2010-01-01

    Fire prevention, fire fighting and fire automatic alarms are three aspects which be included in fire protection system in nuclear power plants. The fire protection system can protect personnel, equipment etc in the fire, so their performance will have a direct influence on the safe operation in nuclear power plants. The disabled accidents caused by aging have happened continuously with the extension of time in the fire protection system, which is the major security risk during the running time in nuclear power plants. In view of the importance of fire protection system and the severity of aging problems, the aging are highly valued by the plant operators and related organizations. Though the feedback of operating experience in nuclear power plant, the impact of the fire-fighting equipment aging on system performance and reliability be assessed, the aging sensitive equipment be selected to carry out the aging analysis and to guide the management and maintenance to guarantee the healthy operation in life time of fire protection system in nuclear power plant. (authors)

  12. Development of a Smart Residential Fire Protection System

    OpenAIRE

    Juhwan Oh; Zhongwei Jiang; Henry Panganiban

    2013-01-01

    Embedded system is applied for the development of smart residential fire detection and extinguishing system. Wireless communication capability is integrated into various fire sensors and alarm devices. The system activates the fire alarm to warn occupants, executes emergency and rescue calls to remote residents and fire-fighting facility in an intelligent way. The effective location of extra-sprinklers within the space of interest for the fire extinguishing system is also investigated. Actual...

  13. The principles for creation of fire-prevention forest belts with barriers of deciduous species for protection from crown fires

    Directory of Open Access Journals (Sweden)

    S. N. Sannikov

    2017-10-01

    Full Text Available The article discuss one of the priority security problems in Russia, which is elaboration of the strategic system of the forest and society safeguards from catastrophic forest crown fires in connection with rapid climate warming. It is postulated, that a most effective and reliable barrier for the dispersal of the intensive crown fire in a coniferous forest massive can be a sufficiently wide strip of deciduous tree species – «deciduous forest barrier», which has phytomass capable of absorbing crown fire energy and transforming them to surface fire, which may be extinguished by technical means. The actuality of the natural study of the transition parameters from the crown fire to surface fire has been noted, depending on climate, fire intensity and the deciduous barrier structure. The results of the quantitative natural investigation of the consequences of catastrophic crown fires of 2004 in the island pine forests of forest-steppe zone in Kurgan Oblast, which passed through the belt of 50–70 year-old birch stands of middle density, has been cited and formalized mathematically. It has been shown, that 150 m width of deciduous forest barrier is necessary as a minimum for the reliable transition of the high intensive front crown fire to surface fire in the forest-steppe conditions of the Western Siberia, but this width reduces with a decreasing heating effect. It has been proposed to create the complex fire-prevention forest belts of different construction for the protection of forests, industrial objects and settlements. Besides a basic deciduous barrier, their structure should include technologically necessary buffer zones and zones for the localization and extinguishing surface fire, which stop a crown fire. It has been recommended to use natural regeneration of deciduous tree species, as a most effective and non-deficient method for the creation of deciduous forest barriers in the predominant forest types, except the lichen pine forests

  14. PART I: Bioventing Pilot Test Work Plan for Fire Protection Training Area Site FY-03, Charleston AFB, South Carolina. PART II: Draft Interim Pilot Test Results Report for Fire Protection Training Area Site FT-03, Charleston AFB, South Carolina

    National Research Council Canada - National Science Library

    1993-01-01

    This site-specific work plan presents the scope of a bioventing pilot test for in situ treatment of fuel contaminated soils at the Fire Protection Training Area designated as Site FT-O3, Charleston Air Force Base (AFB), South Carolina...

  15. 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)

  16. 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

  17. Laboratory investigation of fire protection coatings for creosote-treated timber railroad bridges

    Science.gov (United States)

    Carol A. Clausen; Robert H. White; James P. Wacker; Stan T. Lebow; Mark A. Dietenberger; Samuel L. Zelinka; Nicole M. Stark

    2014-01-01

    As the incidence of timber railroad bridge fires increases, so has the need to develop protective measures to reduce the risk from accidental ignitions primarily caused by hot metal objects. Of the six barrier treatments evaluated in the laboratory for their ability to protect timbers from fires sourced with ignition from hot metal objects only one intumescent coating...

  18. 77 FR 58170 - Proposed Renewal of Existing Information Collection; Fire Protection (Underground Coal Mines)

    Science.gov (United States)

    2012-09-19

    ... Renewal of Existing Information Collection; Fire Protection (Underground Coal Mines) AGENCY: Mine Safety... INFORMATION: I. Background Fire protection standards for underground coal mines are based on section 311(a) of the Federal Mine Safety and Health Act of 1977 (Mine Act). 30 CFR 75.1100 requires that each coal mine...

  19. United States Department of Energy's reactor core protection evaluation methodology for fires at RBMK and VVER nuclear power plants. Revision 1

    International Nuclear Information System (INIS)

    1997-06-01

    This document provides operators of Soviet-designed RBMK (graphite moderated light water boiling water reactor) and VVER (pressurized light water reactor) nuclear power plants with a systematic Methodology to qualitatively evaluate plant response to fires and to identify remedies to protect the reactor core from fire-initiated damage

  20. Aircraft Instrument, Fire Protection, Warning, Communication, Navigation and Cabin Atmosphere Control System (Course Outline), Aviation Mechanics 3 (Air Frame): 9067.04.

    Science.gov (United States)

    Dade County Public Schools, Miami, FL.

    This document presents an outline for a 135-hour course designed to familiarize the student with manipulative skills and theoretical knowledge concerning aircraft instrument systems like major flight and engine instruments; fire protection and fire fighting systems; warning systems and navigation systems; aircraft cabin control systems, such as…

  1. 10 CFR Appendix R to Part 50 - Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979

    Science.gov (United States)

    2010-01-01

    ... service-water/fire-water uses the minimum volume for fire uses shall be ensured by means of dedicated... knowledge of his or her role in the fire fighting strategy for the area assumed to contain the fire... LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. R Appendix R to Part 50—Fire Protection...

  2. 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.

  3. 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.

  4. Fire protection program fiscal year 1995 site support program plan, Hanford Fire Department

    International Nuclear Information System (INIS)

    Good, D.E.

    1994-09-01

    The mission of the Hanford Fire Department (HFD) is to support the safe and timely cleanup of the Hanford site by providing fire suppression, fire prevention, emergency rescue, emergency medical service, and hazardous materials response; and to be capable of dealing with and terminating emergency situations which could threaten the operations, employees, or interest of the US Department of Energy operated Hanford Site. This includes response to surrounding fire departments/districts under a mutual aid agreement and contractual fire fighting, hazardous materials, and ambulance support to Washington Public Power Supply System (Supply System). The fire department also provides site fire marshal overview authority, fire system testing and maintenance, self-contained breathing apparatus maintenance, building tours and inspections, ignitable and reactive waste site inspections, prefire planning, and employee fire prevention education. This report describes the specific responsibilities and programs that the HFD must support and the estimated cost of this support for FY1995

  5. Fire Protection Program fiscal year 1996, site support program plan Hanford Fire Department. Revision 2

    International Nuclear Information System (INIS)

    Good, D.E.

    1995-09-01

    The mission of the Hanford Fire Department (HFD) is to support the safe and timely cleanup of the Hanford site by providing fire suppression, fire prevention, emergency rescue, emergency medical service, and hazardous materials response; and to be capable of dealing with and terminating emergency situations which could threaten the operations, employees, or interest of the US Department of Energy operated Hanford Site. This includes response to surrounding fire departments/districts under a mutual aid agreement and contractual fire fighting, hazardous materials, and ambulance support to Washington Public Power Supply System (Supply System). The fire department also provides site fire marshal overview authority, fire system testing and maintenance, self-contained breathing apparatus maintenance, building tours and inspections, ignitable and reactive waste site inspections, prefire planning, and employee fire prevention education. This report gives a program overview, technical program baselines, and cost and schedule baseline

  6. 33 CFR 149.419 - Can the water supply for the helicopter deck fire protection system be part of a fire water system?

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Can the water supply for the... § 149.419 Can the water supply for the helicopter deck fire protection system be part of a fire water system? (a) The water supply for the helicopter deck fire protection system required under § 149.420 or...

  7. Fire resistance of wood members with directly applied protection

    Science.gov (United States)

    Robert H. White

    2009-01-01

    Fire-resistive wood construction is achieved either by having the structural elements be part of fire-rated assemblies or by using elements of sufficient size that the elements themselves have the required fire-resistance ratings. For exposed structural wood elements, the ratings in the United States are calculated using either the T.T. Lie method or the National...

  8. Performance of a Protected Wireless Sensor Network in a Fire. Analysis of Fire Spread and Data Transmission

    Science.gov (United States)

    Antoine-Santoni, Thierry; Santucci, Jean-François; de Gentili, Emmanuelle; Silvani, Xavier; Morandini, Frederic

    2009-01-01

    The paper deals with a Wireless Sensor Network (WSN) as a reliable solution for capturing the kinematics of a fire front spreading over a fuel bed. To provide reliable information in fire studies and support fire fighting strategies, a Wireless Sensor Network must be able to perform three sequential actions: 1) sensing thermal data in the open as the gas temperature; 2) detecting a fire i.e., the spatial position of a flame; 3) tracking the fire spread during its spatial and temporal evolution. One of the great challenges in performing fire front tracking with a WSN is to avoid the destruction of motes by the fire. This paper therefore shows the performance of Wireless Sensor Network when the motes are protected with a thermal insulation dedicated to track a fire spreading across vegetative fuels on a field scale. The resulting experimental WSN is then used in series of wildfire experiments performed in the open in vegetation areas ranging in size from 50 to 1,000 m2. PMID:22454563

  9. 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

  10. 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

  11. Fire protection devices in the controlled region of GKN nuclear power station

    International Nuclear Information System (INIS)

    Bernhardt, S.; Grauf, E.

    1976-01-01

    In the GKN nuclear power station ('Neckar reactor'), an 805 MW PWR reactor whose start-up is scheduled for the near future, fire protection measures have been realized that go far beyond those realized in other German nuclear power stations until now. One of the main reasons is that the authorities have been sensibilized by a fire in the refuelling cavity during construction and by the Browns Ferry fire and are therefore extremely thorough in their examination. Further subsections have been added to the fire prevention sections in order to provide better quenching devices for potential fire sites. (orig./AK) [de

  12. Fire protection equipment in the area of control of the Neckar Community Nuclear Power Station

    International Nuclear Information System (INIS)

    Bernhardt, S.; Grauf, E.

    1976-01-01

    In the Neckar Community Nuclear Power Station - an 805 MW pressurised water reactor shortly to reach the stage of nuclear operation - fire protection measures have been realised to an extent hitherto uncommon in German nuclear power plants. The reason is to be sought from the authorities who have become more sensitive because of a fire in a reactor vessel during the construction stage and the fire at Browns Ferry and have consequently become extremely expert. Apart from the fire regulations hitherto normal further subregulations have been created in order to be able to make better provision of extinguishing devices against fire hazards. (orig.) [de

  13. Deformation and Heat Transfer on Three Sides Protected Beams under Fire Accident

    Science.gov (United States)

    Imran, M.; Liew, M. S.; Garcia, E. M.; Nasif, M. S.; Yassin, A. Y. M.; Niazi, U. M.

    2018-04-01

    Fire accidents are common in oil and gas industry. The application of passive fire protection (PFP) is a costly solution. The PFP is applied only on critical structural members to optimise project cost. In some cases, beams cannot be protected from the top flange in order to accommodate for the placement of pipe supports and grating. It is important to understand the thermal and mechanical response of beam under such condition. This paper discusses the response of steel beam under ISO 834 fire protected, unprotected and three sides protected beams. The model validated against an experimental study. The experimental study has shown good agreement with FE model. The study revealed that the beams protected from three sides heat-up faster compare to fully protected beam showing different temperature gradient. However, the affects load carrying capacity are insignificant under ISO 834 fire.

  14. Fire-Protection Research for Energy-Technology Projects: FY 1981 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska-Quinn, A.E.; Beason, D.G.; Foote, K.L.; Priante, S.J.

    1982-01-01

    This report summarizes research conducted in fiscal year 1981 for the DOE-supported project, Fire Protection Research for Energy Technology Projects. Initiated in 1977, this ongoing research program was conceived to advance fire protection strategies for Energy Technology Projects to keep abreast of the unique fire problems that are developing with the complexity of energy technology research. We are developing an analytical methodology through detailed study of fusion energy experiments at Lawrence Livermore National Laboratory (LLNL). Employing these facilities as models for methodology development, we are simultaneously advancing three major task areas: (1) determination of unique fire hazards of current fusion energy facilities; (2) evaluation of the ability of accepted fire management measures to meet and negate hazards; and (3) performance of unique research into problem areas we have identified to provide input into analytical fire-growth and damage-assessment models

  15. Fire-Protection Research for Energy-Technology Projects: FY 1981 year-end report

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, H.K.; Alvares, N.J.; Lipska-Quinn, A.E.; Beason, D.G.; Foote, K.L.; Priante, S.J.

    1982-07-20

    This report summarizes research conducted in fiscal year 1981 for the DOE-supported project, Fire Protection Research for Energy Technology Projects. Initiated in 1977, this ongoing research program was conceived to advance fire protection strategies for Energy Technology Projects to keep abreast of the unique fire problems that are developing with the complexity of energy technology research. We are developing an analytical methodology through detailed study of fusion energy experiments at Lawrence Livermore National Laboratory (LLNL). Employing these facilities as models for methodology development, we are simultaneously advancing three major task areas: (1) determination of unique fire hazards of current fusion energy facilities; (2) evaluation of the ability of accepted fire management measures to meet and negate hazards; and (3) performance of unique research into problem areas we have identified to provide input into analytical fire-growth and damage-assessment models.

  16. Fire protection research for DOE facilities: FY 83 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska-Quinn, A.E.; Beason, D.G.; Foote, K.L.; Priante, S.J.; Stagge, K.

    1984-01-01

    We summarize our research in FY 83 for the DOE-sponsored project, Fire Protection Research for DOE Facilities. This research program was initiated in 1977 to advance fire-protection strategies of energy technology facilities in order to keep abreast of the unique fire problems that develop along with energy technology research. Since 1977, the program has broadened its original scope, as reflected in previous year-end reports. We are developing an analytical methodology through detailed study of fusion energy experiments at Lawrence Livermore National Laboratory (LLNL). Using these experiments as models for methodology development, we are currently advancing three major task areas: (1) the identification of fire hazards unique to fusion energy facilities, (2) the evaluation of accepted fire-management measures to meet the negate hazards, and (3) the performance of unique research into problem areas we have identified to provide input into analytical fire-growth and damage-assessment models

  17. Fire-protection research for DOE facilities: FY 82 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska-Quinn, A.E.; Beason, D.G.; Priante, S.J.; Foote, K.L.

    1983-01-01

    We summarize our research in FY 82 for the DOE-sponsored project, Fire Protection Research for DOE Facilities. This research program was initiated in 1977 to advance fire-protection strategies for energy technology facilities to keep abreast of the unique fire problems that develop along with energy technology research. Since 1977, the program has broadened its original scope, as reflected in previous year-end reports. We are developing an analytical methodology through detailed study of fusion energy experiments at Lawrence Livermore National Laboratory (LLNL). Using these experiments as models for methodology development, we are concurrently advancing three major task areas: (1) the identification of fire hazards unique to current fusion energy facilities; (2) the evaluation of accepted fire-management measures to meet and negate hazards; and (3) the performance of unique research into problem areas we have identified to provide input into analytical fire-growth and damage-assessment models

  18. 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

  19. 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)

  20. Summary of fire protection programs of the United States Department of Energy

    International Nuclear Information System (INIS)

    1991-10-01

    This edition of the Annual Summary of DOE Fire Protection Programs continues the series started in 1972. Since May 1950, an annual report has been required from each field organization. The content has varied through the years and most of the accident data reporting requirements have been superseded by the Computerized Accident/Incident Reporting System administered by EG ampersand G, Idaho. However, this report is the sole source of information relating to fire protection programs, and to the actions of the field offices and to headquarters that are of general fire protection interest

  1. Ceramic fiber blanket wrap for fire protection of cable trays and conduits

    International Nuclear Information System (INIS)

    Chaille, C.E.; Reiman, R.J.

    1980-01-01

    In some areas of nuclear power plants, cables of redundant electrical systems, which are necessary for the safe shutdown of the reactor, are in close proximity. If a fire should occur in one of these areas, both electrical systems could be destroyed before the fire is extinguished and control of the reactor may be lost. A ceramic fiber blanket was evaluated as a fire protective wrap around cable trays and conduits. 2 refs

  2. 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

  3. 14 CFR 121.308 - Lavatory fire protection.

    Science.gov (United States)

    2010-01-01

    ... operate a passenger-carrying airplane unless each lavatory in the airplane is equipped with a smoke...-carrying airplane unless each lavatory in the airplane is equipped with a built-in fire extinguisher for each disposal receptacle for towels, paper, or waste located within the lavatory. The built-in fire...

  4. 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...

  5. Risk reduction in road and rail LPG transportation by passive fire protection

    NARCIS (Netherlands)

    Paltrinieri, N.; Landucci, G.; Molag, M.; Bonvicini, S.; Spadoni, G.; Cozzani, V.

    2009-01-01

    The potential reduction of risk in LPG (Liquefied Petroleum Gas) road transport due to the adoption of passive fire protections was investigated. Experimental data available for small scale vessels fully engulfed by a fire were extended to real scale road and rail tankers through a finite elements

  6. Recommendations for ionization chamber smoke detectors for commercial and industrial fire protection systems (1988)

    International Nuclear Information System (INIS)

    1989-01-01

    Ionization chamber smoke detectors (ICSDs) utilising a radioactive substance as the source of ionization are used to detect the presence of smoke and hence give early warning of a fire. These recommendations are intended to ensure that the use of ICSDs incorporating radium-226 and americium-241 in commercial/industrial fire protection systems does not give rise to any unnecessary radiation exposure

  7. Design and Implementation of Fire Extinguisher Robot with Robotic Arm

    Directory of Open Access Journals (Sweden)

    Memon Abdul Waris

    2018-01-01

    Full Text Available Robot is a device, which performs human task or behave like a human-being. It needs expertise skills and complex programming to design. For designing a fire fighter robot, many sensors and motors were used. User firstly send robot to an affected area, to get live image of the field with the help of mobile camera via Wi-Fi using IP camera application to laptop. If any signs of fire shown in image, user direct robot in that particular direction for confirmation. Fire sensor and temperature sensor detects and measures the reading, after confirmation robot sprinkle water on affected field. During extinguish process if any obstacle comes in between the prototype and the affected area the ultrasonic sensor detects the obstacle, in response the robotic arm moves to pick and place that obstacle to another location for clearing the path. Meanwhile if any poisonous gas is present, the gas sensor detects and indicates by making alarm.

  8. A New Design Method for Industrial Portal Frames in Fire

    Directory of Open Access Journals (Sweden)

    Y. Song

    2009-01-01

    Full Text Available Industrial portal frames near to other buildings must keep their vertical walls standing in fire in order to prevent fire spread.  A recently developed analysis, implemented in the program Vulcan, using a combination of static and dynamic solvers, has shown that the strong base connections recommended by the current design method may not always lead to conservative design. A second-phase failure mechanism observed in numerical modelling, and the critical temperature at which final run-away collapse occurs, may be higher than the temperature at which the roof frame initially loses its stability, because a re-stabilisation often happens.  A new method for estimating critical temperatures of portal frames in fire, using these two failure mechanisms, is presented. Numerical tests on typical industrial frames are used to calibrate this new method. 

  9. Use of numerical modeling in design for co-firing biomass in wall-fired burners

    DEFF Research Database (Denmark)

    Yin, Chungen; Rosendahl, Lasse Aistrup; Kær, Søren Knudsen

    2004-01-01

    modification to the motion and reaction due to their non-sphericity. The simulation results show a big difference between the two cases and indicate it is very significant to take into account the non-sphericity of biomass particles in order to model biomass combustion more accurately. Methods to improve...... of numerical modeling. The models currently used to predict solid fuel combustion rely on a spherical particle shape assumption, which may deviate a lot from reality for big biomass particles. A sphere gives a minimum in terms of the surface-area-to-volume ratio, which impacts significantly both motion...... and reaction of a particle. To better understand biomass combustion and thus improve the design for co-firing biomass in wall-fired burners, non-sphericity of biomass particles is considered. To ease comparison, two cases are numerically studied in a 10m long gas/biomass co-fired burner model. (1) The biomass...

  10. 76 FR 70413 - National Fire Protection Association (NFPA): Request for Comments on NFPA's Codes and Standards

    Science.gov (United States)

    2011-11-14

    ... Private Fire Protection. P NFPA 36 Standard for Solvent Extraction Plants P NFPA 52 Vehicular Gaseous Fuel Systems Code P NFPA 67 Guideline on Explosion Protection for Gaseous N Mixtures in Pipe Systems. NFPA 68 Standard on Explosion Protection by Deflagration P Venting. NFPA 70B Recommended Practice for Electrical...

  11. 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.

  12. Protection against fire and high temperature by using porous media and water

    International Nuclear Information System (INIS)

    Yano, T.; Ochi, M.; Snya, S.

    1991-01-01

    In this paper the protection method against the fire and high temperature under the disaster environments is developed and examined by utilizing the transpiration cooling to maintain the objectives at the room temperature. A room model installed by thermal protection panel for security heaven to which the people are able to escape from the fire in safety. The cooling structure is mainly composed of porous media which is made by thin ceramic paper, and the reinforced ceramic paper. The experimental verification of the room and cable models shows that the thermal protection by transpiration of water have good ability to keep inside at the room temperature even if in the violent fire. It is also clarified that the thermal protection technology by transpiration is expective to defend the room, building, cable, safety equipment, information system and etc., from the fire

  13. Modeling the protection afforded by burrows, cavities, and roosts during wildland surface fires

    Science.gov (United States)

    Anthony Bova; Matthew Dickinson

    2009-01-01

    Wildland surface fires produce many toxic and irritating compounds, such as formaldehyde and acrolein, and harmful gases such as carbon monoxide. Several factors influence the degree of protection offered by animal shelters against combustion products and heat.

  14. Probabilistic Evaluation of Eurocode 5 Fire Design Criteria of a ...

    African Journals Online (AJOL)

    Structural reliability analysis for a three-hinge timber portal frame subjected to fire was undertaken. Eight modes of failure were identified for the frame and limit state function was formulated for each failure mode. The limit state functions were based on the Eurocode 5 design criteria. Uncertainties in the timber material ...

  15. Physical protection system design and evaluation

    International Nuclear Information System (INIS)

    Williams, J.D.

    1997-01-01

    The design of an effective physical protection system includes the determination of physical protection system objectives, initial design of a physical protection system, design evaluation, and probably a redesign or refinement. To develop the objectives, the designer must begin by gathering information about facility operation and conditions, such as a comprehensive description of the facility, operating conditions, and the physical protection requirements. The designer then needs to define the threat. This involves considering factors about potential adversaries: class of adversary, adversary's capabilities, and range of adversary's tactics. Next, the designer should identify targets. Determination of whether or not the materials being protected are attractive targets is based mainly on the ease or difficulty of acquisition and desirability of the material. The designer now knows the objectives of the physical protection system, that is, open-quotes what to protect against whom.close quotes The next step is to design the system by determining how best to combine such elements as fences, vaults, sensors and assessment devices, entry control elements, procedures, communication devices, and protective forces personnel to meet the objectives of the system. Once a physical protection system is designed, it must be analyzed and evaluated to ensure it meets the physical protection objectives. Evaluation must allow for features working together to ensure protection rather than regarding each feature separately. Due to the complexity of the protection systems, an evaluation usually requires modeling techniques. If any vulnerabilities are found, the initial system must be redesigned to correct the vulnerabilities and a reevaluation conducted. This paper reviews the physical protection system design and methodology mentioned above. Examples of the steps required and a brief introduction to some of the technologies used in modem physical protections system are given

  16. 14 CFR 23.1359 - Electrical system fire protection.

    Science.gov (United States)

    2010-01-01

    ... procedures must be fire-resistant. (c) Insulation on electrical wire and electrical cable must be self... this part, or other approved equivalent methods. The average burn length must not exceed 3 inches (76...

  17. Protection against fire hazards in French nuclear power plants

    International Nuclear Information System (INIS)

    Chapus, J.

    2000-01-01

    The prevention of fire in French nuclear power plants has followed the evolution of safety regulations. Today fire hazards are no longer considered as classical industrial risks but as specific risks that deserve to be studied thoroughly and in a more formalized form. In the beginning of the eighties EDF was committed to the redaction of a technical referential against fire gathering all the directives applicable to the N4-type plant (1450 MW). In 1994 this technical referential was reconsidered and enlarged in order to involve 900 MW and 1300 MW units. In each nuclear power plant a PAI (plan against fire) has been elaborated so that the installation can be progressively upgraded according to the last standard defined by the technical referential. (A.C.)

  18. Fire protection research for energy technology projects; FY 79 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska, A.E.; Ford, H.; Beason, D.G.

    1981-01-01

    This report describes work performed in fiscal year 1979, on a DOE funded study entitled Fire Protection Research for Energy Technology Projects. The primary goal of this program is to ensure that fire protection measures for Fusion Energy Experiments (FEE) evolve concurrently with the complexity of FEE. Ultimately, it is planned that the detailed study of fusion experiments will provide an analytical methodology which can be applied to the full range of energy technology projects. We attempt to achieve this objective by coordinately advancing 3 (three) major task areas; (a) determine the fire hazards of current FEE facilities (b) assess the ability of accepted fire management strategies to meet and negate the hazard, (c) perform unique research into problem areas we have identified to provide input into analytical fire growth and damage assessment models

  19. Management impacts on fire occurrence: A comparison of fire regimes of African and South American tropical savannas in different protected areas.

    Science.gov (United States)

    Alvarado, Swanni T; Silva, Thiago Sanna Freire; Archibald, Sally

    2018-07-15

    Humans can alter fire dynamics in grassland systems by changing fire frequency, fire seasonality and fuel conditions. These changes have effects on vegetation structure and recovery, species composition, and ecosystem function. Understanding how human management can affect fire regimes is vital to detect potential changes in the resilience of plant communities, and to predict vegetation responses to human interventions. We evaluated the fire regimes of two recently protected areas in Madagascar (Ibity and Itremo NPA) and one in Brazil (Serra do Cipó NP) before and after livestock exclusion and fire suppression policies. We compare the pre- and post-management fire history in these areas and analyze differences in terms of total annual burned area, density of ignitions, burn scar size distribution, fire return period and seasonal fire distribution. More than 90% of total park areas were burned at least once during the studied period, for all parks. We observed a significant reduction in the number of ignitions for Ibity NPA and Serra do Cipó NP after livestock exclusion and active fire suppression, but no significant change in total burned area for each protected area. We also observed a seasonal shift in burning, with fires happening later in the fire season (October-November) after management intervention. However, the protected areas in Madagascar had shorter fire return intervals (3.23 and 1.82 years) than those in Brazil (7.91 years). Our results demonstrate that fire exclusion is unattainable, and probably unwarranted in tropical grassland conservation areas, but show how human intervention in fire and vegetation patterns can alter various aspects of the fire regimes. This information can help with formulating realistic and effective fire management policies in these valuable conservation areas. Copyright © 2018 Elsevier Ltd. All rights reserved.

  20. Efficacy of water spray protection against propane and butane jet fires impinging on LPG storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Shirvill, L.C. [Shell Global Solutions (UK), Chester (United Kingdom)

    2004-03-01

    Liquefied petroleum gas (LPG) storage tanks are often provided with water sprays to protect them in the event of a fire. This protection has been shown to be effective in a hydrocarbon pool fire but uncertainties remained regarding the degree of protection afforded in a jet fire resulting from a liquid or two-phase release of LPG. Two projects, sponsored by the Health and Safety Executive, have been undertaken to study, at full scale, the performance of a water spray system on an empty 13 tonne LPG vessel under conditions of jet fire impingement from nearby releases of liquid propane and butane. The results showed that a typical water deluge system found on an LPG storage vessel cannot be relied upon to maintain a water film over the whole vessel surface in an impinging propane or butane jet fire scenario. The deluge affects the fire itself, reducing the luminosity and smoke, resulting in a lower rate of wall temperature rise at the dry patches, when compared with the undeluged case. The results of these studies will be used by the HSE in assessing the risk of accidental fires on LPG installations leading to boiling liquid expanding vapour explosion (BLEVE) incidents. (Author)

  1. Methods and criteria for evaluation of nuclear reactor fire protection alternatives and modifications

    International Nuclear Information System (INIS)

    Levinson, S.H.

    1982-01-01

    The objective of this work is to develop a methodology for the evaluation of a fire protection system in a nuclear power plant and demonstrate the feasibility of encoding this method in a computer program. A Monte Carlo simulation has been developed; it is divided into the four phases of a fire scenario: ignition, detection, suppression and propagation. The ignition model consists of probabilistically determining at what location within the zone a fire will occur. The detection model is divided into two components. THe first is the automatic detection model, which calculates the fire's physical symptoms and compares them against the threshold values of the detectors specified for the zone to determine a time-to-detection. The second part is the human detection model; this evaluates the time required for a human to observe and report a fire. If detection is successful, the suppression mode determines if the fire is effectively extinguished, and if so, the time required to do so. This model is also divided into an automatic and human component. The propagation model is embedded in a deterministic, control-volume computer code which calculates the fire scenario history. A computer program, FIRES, is described which supports the developed models. FIRES is an interactive graphics package providing a simple means of establishing the many input parameters. In addition to allowing parameter values to be easily set or modified, the graphics provides a convenient display mode for the results of a simulation

  2. 30 CFR 77.1100 - Fire protection; training and organization.

    Science.gov (United States)

    2010-07-01

    ....1100 Section 77.1100 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF... facilities and equipment shall be provided commensurate with the potential fire hazards at each structure...

  3. 14 CFR 125.175 - Protection of other airplane components against fire.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Protection of other airplane components... CERTIFICATION AND OPERATIONS: AIRPLANES HAVING A SEATING CAPACITY OF 20 OR MORE PASSENGERS OR A MAXIMUM PAYLOAD... Requirements § 125.175 Protection of other airplane components against fire. (a) Except as provided in...

  4. 14 CFR 121.277 - Protection of other airplane components against fire.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Protection of other airplane components....277 Protection of other airplane components against fire. (a) Except as provided in paragraph (b) of this section, all airplane surfaces aft of the nacelles in the area of one nacelle diameter on both...

  5. Fire-protection research for energy technology: Fy 80 year end report

    Science.gov (United States)

    Hasegawa, H. K.; Alvares, N. J.; Lipska, A. E.; Ford, H.; Priante, S.; Beason, D. G.

    1981-05-01

    This continuing research program was initiated in order to advance fire protection strategies for Fusion Energy Experiments (FEE). The program expanded to encompass other forms of energy research. Accomplishments for fiscal year 1980 were: finalization of the fault-free analysis of the Shiva fire management system; development of a second-generation, fire-growth analysis using an alternate model and new LLNL combustion dynamics data; improvements of techniques for chemical smoke aerosol analysis; development and test of a simple method to assess the corrosive potential of smoke aerosols; development of an initial aerosol dilution system; completion of primary small-scale tests for measurements of the dynamics of cable fires; finalization of primary survey format for non-LLNL energy technology facilities; and studies of fire dynamics and aerosol production from electrical insulation and computer tape cassettes.

  6. Fire-protection research for energy technology: FY 80 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska, A.E.; Ford, H.; Priante, S.; Beason, D.G.

    1981-01-01

    This continuing research program was initiated in 1977 in order to advance fire protection strategies for Fusion Energy Experiments (FEE). The program has since been expanded to encompass other forms of energy research. Accomplishments for fiscal year 1980 were: finalization of the fault-tree analysis of the Shiva fire management system; development of a second-generation, fire-growth analysis using an alternate moel and new LLNL combustion dynamics data; improvements of techniques for chemical smoke aerosol analysis; development and test of a simple method to assess the corrosive potential of smoke aerosols; development of an initial aerosol dilution system; completion of primary small-scale tests for measurements of the dynamics of cable fires; finalization of primary survey format for non-LLNL energy technology facilities; and studies of fire dynamics and aerosol production from electrical insulation and computer tape cassettes

  7. 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

  8. A new approach to the Danish guidelines for fire protection of combustible insulation

    Directory of Open Access Journals (Sweden)

    Dragsted Anders

    2013-11-01

    Full Text Available The tendency to use thicker layers of insulation and a wider use of combustible insulation materials is identified to pose a potential risk to fire safety of buildings. A new approach to the current Danish prescriptive code on fire protection of combustible insulation is proposed as a way to meet the concern. The new approach uses the fire properties of the insulation material itself to point out the necessary protective measures. This is contrary to the most European countries were only a reaction to fire class of the façade construction as a whole is required. The basic principle is presented but more research is needed to complete the new approach.

  9. 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

  10. 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.

  11. Coal fly ash-containing sprayed mortar for passive fire protection of steel sections

    Directory of Open Access Journals (Sweden)

    Vilches, L. F.

    2005-09-01

    Full Text Available The present article addresses the possible use of coal fly ash as the chief component of sprayed mortars to fireproof steel structures. A pilot wet-mix gunning rig was specifically designed and built to spray different pastes on to sheet steel and sections with different surface/volume ratios. After gunning, the specimens were placed in a furnace and subjected to standard fire resistance testing. Product fire resistance was calculated from the test results. The mortar used in this study, with a high fly ash content, was found to have acceptable mechanical properties as well as afire resistance potential comparable to those of commercial passive fire protection products.

    En este artículo se estudia el posible uso de las cenizas volantes procedentes de la combustión del carbón como constituyente principal de morteros que pueden ser proyectados sobre estructuras metálicas, para protegerlas contra el fuego. Con objeto de estudiar el proceso de proyección, se ha construido una planta piloto de gunitado por vía húmeda. La pasta se ha proyectado sobre placas metálicas y perfiles metálicos con diferentes relaciones superficie/volumen. Tras el gunitado, las probetas proyectadas se colocan en un horno y se someten a un programa de calentamiento según la norma de resistencia al fuego. A partir de los datos obtenidos se ha podido realizar una estimación de la resistencia al fuego del producto. Los resultados muestran que el material proyectado usado en este estudio, que contiene una alta proporción de cenizas volantes, tiene unas propiedades mecánicas aceptables y unas características potenciales de resistencia al fuego comparables a las de otros productos comerciales utilizados en la protección pasiva contra el fuego.

  12. Pipelines cathodic protection design methodologies for impressed ...

    African Journals Online (AJOL)

    Several inadequate designs of cathodically polarized offshore and onshore pipelines have been reported in Nigeria owing to design complexity and application of the cathodic protection system. The present study focused on critical and detailed approach in impressed current and sacrificial anode design calculation ...

  13. Ecological fire use for ecological fire management: Managing large wildfires by design

    Science.gov (United States)

    Timothy Ingalsbee

    2015-01-01

    Past fire exclusion policies and fire suppression actions have led to a historic "fire deficit" on public wildlands. These sociocultural actions have led to unprecedented environmental changes that have created conditions conducive to more frequent large-scale wildfires. Politicians, the newsmedia, and agency officials portray large wildland fires as...

  14. 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

  15. Mechanical design and protection of superconducting magnets

    CERN Document Server

    Asner, Alfred M

    1978-01-01

    The principles of the mechanical design of superconducting magnets of concentric configuration, with iron low-temperature and room- temperature screening, are outlined. Measures for protection of such magnets against quench forces, are considered. (4 refs).

  16. Integrated system of occupational safety and health and fire protection of the fire rescue brigades members.

    Science.gov (United States)

    Božović, Marijola; Živković, Snežana; Mihajlović, Emina

    2018-06-01

    The objective of the conducted research is the identification and determination of requirements of members of fire rescue brigades during operations in the conditions of high risk in order to minimize the possibilities for injury incidence during the intervention. The research is focused on examination, determination and identification of factors affecting the increasing number of occupational injuries of members of fire rescue brigades during interventions. Hypothetical framework of the research problem consists of general hypothesis and six special hypotheses. Results suggest that almost all respondents believe that their skills and abilities are applicable in the intervention phase, but less than a half believe that their skills are applicable in prevention phase. Two-thirds of respondents stated that in their organization they have support for further education and upgrading while a half of respondents stated that they need education concerning identification, assessment and management of risks that can lead to emergency situations.

  17. Design of Fire/Gas Penetration Seals and fire exposure tests for Tokamak Fusion Test Reactor experimental areas

    International Nuclear Information System (INIS)

    Cavalluzzo, S.

    1983-01-01

    A Fire/Gas Penetration Seal is required in every penetration through the walls and ceilings into the Test Cell housing the Tokamak Fusion Test Reactor (TFTR), as well as other adjacent areas to protect the TFTR from fire damage. The penetrations are used for field coil lead stems, diagnostics systems, utilities, cables, trays, mechanical devices, electrical conduits, vacuum liner, air conditioning ducts, water pipes, and gas pipes. The function of the Fire/Gas Penetration Seals is to prevent the passage of fire and products of combustion through penetrations for a period of time up to three hours and remain structurally intact during fire exposure. The Penetration Seal must withstand, without rupture, a fire hose water stream directed at the hot surface. There are over 3000 penetrations ranging in size from several square inches to 100 square feet, and classified into 90 different types. The material used to construct the Fire/Gas Penetration Seals consist of a single and a two-component room temperature vulcanizing (RTV) silicone rubber compound. Miscellaneous materials such as alumina silica refractory fibers in board, blanket and fiber forms are also used in the construction and assembly of the Seals. This paper describes some of the penetration seals and the test procedures used to perform the three-hour fire exposure tests to demonstrate the adequacy of the seals

  18. FIRE PROTECTION OF TIMBER STRUCTURES STRENGTHENED WITH FRP MATERIALS

    Directory of Open Access Journals (Sweden)

    Radek Zigler

    2015-12-01

    Full Text Available Modern, progressive methods of structures’ strengthening based on the use of composite materials composed of high strength fibers (carbon, glass, aramid or basalt and matrices based on epoxy resins brings, among many indisputable advantages (low weight, high effectiveness, easy application etc. also some disadvantages. One of the major disadvantages is a low fire resistance of these materials due to the low glass transition temperature Tg of the resin used. Based on an extensive research of strengthening of historic structures with FRP materials [1], the article outlines possible approaches to this problem, especially while strengthening timber load- bearing structures of historic buildings.

  19. Fire Protection of Weapon Storage and Water Mist Redundancy Philosophies

    Science.gov (United States)

    2012-11-01

    criteria me system ged system ozzles dummy tor d, insulated titute of Swe stems pedo pipe Date 2012 den Refere -03-31 P90 nce 0038-04...test wit tion test wit ution test wi t system, 10 st system, 5 m, 5 bar, 50 , 10 bar, 50 ummy, free- edo dummy pedo dummy pedo dummy ummy, dren...systems usi lower volum pedo dumm temperature discharge d ion. h Institute ynamics dström Date 2012 den ater mist/wa ests indicate fire

  20. On the Legal Protection of Design

    DEFF Research Database (Denmark)

    Teilmann-Lock, Stina

    2011-01-01

    be judged. In 1839 the Designs Registration Act in the UK introduced a fundamental modernization of registration for designs. Paradigmatic of the modern way of registration is the use of 'representative registration'. According to the 1839 Act, applicants for a design registration were required either...... to deposit three samples of the design, or to submit a pictorial or written representation thereof. The latter system of 'representative registration' has since become virtually universal in intellectual property law relating to designs around the world. Today, the discursive representation of design is more...... not apply to any aspect which is dictated by its function. Accordingly, if a design is to qualify for legal protection, its description (or illustration) must make a clear distinction between form and function. According to the intellectual property laws of many nations today, designs may also be protected...

  1. Physical protection system design and evaluation

    International Nuclear Information System (INIS)

    Williams, J.D.

    1997-11-01

    The design of an effective physical protection system (PPS) includes the determination of the PPS objectives, the initial design of a PPS, the evaluation of the design, and probably, the redesign or refinement of the system. To develop the objectives, the designer must begin by gathering information about facility operation and conditions, such as a comprehensive description of the facility, operating conditions, and the physical protection requirements. The designer then needs to define the threat. This involves considering factors about potential adversaries: class of adversary, adversary's capabilities, and range of adversary's tactics. Next, the designer should identify targets. Determination of whether or not the materials being protected are attractive targets is based mainly on the ease or difficulty of acquisition and desirability of the material. The designer now knows the objectives of the PPS, that is, ''what to protect against whom.'' The next step is to design the system by determining how best to combine such elements as fences, vaults, sensors and assessment devices, entry control devices, communication devices, procedures, and protective force personnel to meet the objectives of the system. Once a PPS is designed, it must be analyzed and evaluated to ensure it meets the PPS objectives. Evaluation must allow for features working together to ensure protection rather than regarding each feature separately. Due to the complexity of the protection systems, an evaluation usually requires modeling techniques. If any vulnerabilities are found, the initial system must be redesigned to correct the vulnerabilities and a reevaluation conducted. After the system is installed, the threat and system parameters may change with time. If they do, the analysis must be performed periodically to ensure the system objectives are still being met

  2. Installation and operation of the Plantwide Fire Protection Systems and related Domestic Water Supply Systems

    International Nuclear Information System (INIS)

    1991-12-01

    A safe work environment is needed to support the Savannah River Site (SRS) mission of producing special nuclear material. This Environmental Assessment (EA) assesses the potential environmental impact(s) of adding to and upgrading the Plantwide Fire Protection System and selected related portions of the Domestic Water Supply System at SRS, Aiken, South Carolina. The following objectives are expected to be met by this action: Prevent undue threat to public health and welfare from fire at SRS; prevent undue hazard to employees at SRS from fire; prevent unacceptable delay to vital DOE programs as a result of fire at SRS; keep fire related property damage at SRS to a manageable level;, and provide an upgraded supply of domestic water for the Reactor Areas. The Reactor Areas' domestic water supplies do not meet current demand capacity due to the age and condition of the 30-year old iron piping. In addition, the water quality for these supplies is not consistent with current SCDHEC requirements. Therefore, DOE proposes to upgrade this Domestic Water Supply System to meet current demand and quality levels, as well as the needs of fire protection system improvement

  3. Review of national and international demands on fire protection in nuclear power plants and their application in the Swedish nuclear industry

    International Nuclear Information System (INIS)

    Fredholm, Lotta

    2010-02-01

    regarding fire safety at nuclear power plants that have been studied are regulation from USA, Finland, Great Britain, Canada, Germany and the international organisations IAEA and WENRA. The conclusion of this study is that the differences between the regulations mostly are differences in detailed fire safety design. Some differences can not easily be explained by national. Differences and the resulting effect on the overall fire safety is very difficult to evaluate. Regarding how to improve the Swedish regulations regarding fire safety at nuclear power plants there are different possibilities. One is to complement the regulations with acceptable solutions on how to design the fire protection. If this shall be done IAEAs Safety Guides seem to be the easiest of the more detailed fire requirements to adopt to Swedish conditions. Another way of improving the regulation is to give more guidance on how to proof that the rules are fulfilled. In this case the Canadian guidelines may be a good source of ideas and information

  4. Literature study regarding fire protection in nuclear power plants. Part I: Fire rated separations; Litteraturstudie angaaende brandskydd i kaernkraftverk. Del I: Brandteknisk separation

    Energy Technology Data Exchange (ETDEWEB)

    Isaksson, S [Swedish Testing and Research Inst., Boraas (Sweden)

    1995-06-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Conventional building codes can not give guidance on where to make fire rated separations in order to separate redundant trains of safety systems. The separation must originate in functional demands from the authorities on what functions are essential during and after a fire, and under what circumstances these functions shall be retained, i.e. the number of independent faults and initiating events. As a basic demand it is suggested to rate the strength of separations according to conventional building code, based on fire load. The whole separating construction shall have the same fire rating, including the ventilation system. Deviations from the basic demand can de done in case it can be proven that it is possible to compensate some or all of the fire rating with other measures. There is a general lack of statistical information regarding the reliability of fire separating constructions such as walls, fire doors, penetration seals and fire dampers. The amount of cables penetrating a seal is in many cases much higher in real installations than what has been tested for type approval. It would therefore be valuable to perform a furnace test with a more representative amount of cables passing through a penetration seal. Tests have shown that the 20 foot horizontal separation distance stipulated by NRC is not a guarantee against fire damage. Spatial separations based on general requirements shall not be allowed, but considered from case to case based on actual circumstances. For fire protection by isolation or coatings, it is of great importance to choose the method of protection carefully, to be compatible with the material it shall be applied on, and the environment and types of fire that may occur. 48 refs, 2 figs, 5 tabs.

  5. Fire protection in laboratories and factories. Guide for nuclear operator

    International Nuclear Information System (INIS)

    Savornin, J.; Hebrard, L.; Michard, J.; Muller, G.; Vasseur, C.

    1987-12-01

    Putting in place a nuclear industry is possible only if is taken into account the systematic risks connecting with the manipulation of radioactive matters. The measures taken are essentially the putting in place of static or dynamic barriers confinement. Therefore in case of fire their efficiencies can be reduced. The basic safety rule no. I-4.a serie U defines the objectives but do not give all the means to arrive. The present guide has for objective to propose the means which allow to satisfy these objectives. It permits to define the importance of precautions to take in terms of possible consequences. This document is not a rule. It has for objective to give advices [fr

  6. Fire protection program evaluation of Argonne National Laboratory, West for the Department of Energy

    International Nuclear Information System (INIS)

    1984-01-01

    A fire protection engineering survey was conducted of the Argonne National Laboratory, West Facility, near Idaho Falls, Idaho. This facility includes EBR-II, TREAT, ZPPR, and HFEF. The facility meets the improved risk criteria as set forth in DOE Order 5480.1, Chapter VII. Some recommendations are given

  7. 5 CFR 551.541 - Employees engaged in fire protection activities or law enforcement activities.

    Science.gov (United States)

    2010-01-01

    ... activities or law enforcement activities. 551.541 Section 551.541 Administrative Personnel OFFICE OF... activities or law enforcement activities. (a) An employee engaged in fire protection activities or law enforcement activities (as described in §§ 551.215 and 551.216, respectively) who receives compensation for...

  8. 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...

  9. 29 CFR 1915.507 - Land-side fire protection systems.

    Science.gov (United States)

    2010-07-01

    ... standard for employee safety or employee protection from fire hazards in land-side facilities, including... remains hazardous to employee safety or health, or provide safeguards to prevent employees from entering... hazardous to employee safety or health; and (6) Select, install, inspect, maintain, and test all automatic...

  10. 33 CFR 127.1507 - Water systems for fire protection.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) WATERFRONT FACILITIES WATERFRONT FACILITIES HANDLING LIQUEFIED NATURAL GAS AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Hazardous Gas Firefighting Equipment § 127.1507 Water... means for distributing and applying the water to protect personnel; to cool storage tanks, equipment...

  11. Design and Development of Fire Gridding Platform Based on Internet of Things

    Directory of Open Access Journals (Sweden)

    Wei San-Xi

    2016-01-01

    Full Text Available This article describes the construction background about fire gridding platform, reviews the research and progress in fire Internet of Things and fire gridding. The platform includes perception / execution layer, field control layer, network layer, center platform layer and application layer, which provide a good bonding about site control and remote monitoring. This article supplies a detail design for the main functions of application and task flow of fire hazard investigation. At the same time, a digital management platform was developed.

  12. Reliability data of fire protection equipment and features in German nuclear power plants

    International Nuclear Information System (INIS)

    Roewekamp, M.; Riekert, T.; Sehrbrock, W.

    1997-01-01

    In order to perform probabilistic fire safety analyses, a comprehensive data base is needed including physical characteristics of fire compartments and their inventory, fire occurrence frequencies, technical reliability data for all fire-related equipment, human actions and human error probabilities, etc. In order to provide updated and realistic reliability data, the operational behaviour of different fire protection features in two German nuclear power plants was analysed in the framework of the study presented here. The analyses are based on the examination of reported results of the regular inspection and maintenance programs for nuclear power plants. Besides a plant specific assessment of the reliability data a generic assessment for an application as input data for fault tree analyses in the framework of probabilistic risk studies for other German plants was carried out. The analyses of failures and unavailabilities gave the impression that most of them are single failures without relevance for the plant safety. The data gained from NPPs were compared to reliability data of the German insurance companies for the same protection features installed in non-nuclear installations and to older nuclear specific reliability data. This comparison showed up a higher reliability. (orig.) [de

  13. Passive fire protection in high density village (case study, Bustaman Semarang)

    Science.gov (United States)

    Sukawi, Sukawi; Wahyu Firmandhani, Satriya; Hardiman, Gagoek

    2017-12-01

    Fire hazard is the disaster that always has an unpredictable process of coming. When it comes, its level scope and the magnitude of the effects cannot be predicted. Dense settlements especially in big cities, among others Bustaman Kampong Semarang never escape from physical problems such as flooding and wildfire. If both are compared in dense settlements scope, so that, wild fire is the most potentially catastrophic. It is necessary to do a research on passive fire protection in a village of high density city such as Bustaman. Qualitative research was conducted using descriptive method to conduct observations and interviews in the Bustaman. Bustaman as a high density village, with narrow roads and dense rows of houses. The terraced buildings are also encountered, and found many buildings use combustible material. That environmental conditions can facilitate the propagation of flames in case of fire. To improve the established Bustaman's environment, in terms of the application of passive fire protection systems, it is recommended to utilize the road as the dividing buildings. Need to build the separation wall fireproof in every each series in several units of too long buildings and attempted open space procurement that separates rows of buildings that are too long, and also the replacement of combustible material with a material that is more incombustible.

  14. Active and passive fire protection system in academic building KH. Mas Mansur, Islamic University of Indonesia

    Directory of Open Access Journals (Sweden)

    Suryoputro M. Ragil

    2018-01-01

    Full Text Available According to the theory of fire triangle, the existence of combustible materials, heat, and oxygen can cause fire disaster. KH. Mas Mansur building, Islamic University of Indonesia has a fire protection, but rarely to be checked regularly and the number of equipment is less standard as well as the lack of an evacuation route map to facilitate the evacuation process. Inside the building also does not provide safety signs such as the evacuation directions, exit, and warning in case of fire. Therefore, researchers analysed the infrastructure of prevention and control in the building KH. Mas Mansur. Researchers used the method of observation, interviews, and checklist to know the condition directly, and compare with the standard regulations. Results concordance rate of existing infrastructure is 67% fire extinguisher, hydrant box 56%, 71% alarms, sprinkler 0%, 40% detectors, emergency doors 71%, 50% emergency stairs, assembly point 0% and directions 0%. The current results were below the standard of at least 80%. As for recommendations, researchers create a new evacuation map then put the existing infrastructure according to standard regulations, and it had consulted with the specialist of Occupational Safety and Health in the field of fire.

  15. Forest fire occurrence and silvicultural-economic prerequisites for protection improvement in forest regions of Krasnoyarsk Krai

    Directory of Open Access Journals (Sweden)

    V. V. Furyaev

    2017-10-01

    Full Text Available The territory of the Krasnoyarsk Krai is substantially diverse in terms of climatic, silvicultural and economic conditions owing to its sufficient spread from the North to the South. These differences were to some extent taken into account when the forest fund of the Krasnoyarsk Krai was divided into seven forest regions: forest tundra of Central Siberia, highland taiga of Central Siberia, plain taiga of West Siberia, Angara region, subtaiga forest steppe of Central Siberia, Altai-Sayanskiy highland, Altai-Sayanskiy highland forest steppe. The regions show different levels of fire occurrence and different fire effects that require different levels of protection from forest fires. Optimization of the protection is based on activities that combine prevention and timely detection of fires depending on development of forest regions and intensity of forest management. The main focus of the paper is on possibility or inadvisability of prescribed fires, fire-use fires (fires that started naturally but were then managed for their beneficial effects and the system of activities increasing fire resistance of the most valuable forests. It is justified that taking into account the effects of forest fires, selective protection of forests is expedient in forest-tundra Middle Siberia and highland taiga of Middle Siberia regions. The whole area of plain taiga of West Siberia region should be subject to protection but with various levels of intensity in different parts of it. The forest fund of Angara, subtaiga forest steppe of Middle Siberia, Altai-Sayanskiy highland, Altai-Sayanskiy highland forest steppe regions should be protected on the whole area. Application of prescribed fires is relevant in the subzone of South taiga, in the forest steppe zone as well as in the submontane and lowland taiga belts. Fire-use fires are admissible on limited areas in the subzones of Middle and North taiga.

  16. Significance analysis of the regional differences on icing time of water onto fire protective clothing

    Science.gov (United States)

    Zhao, L. Z.; Jing, L. S.; Zhang, X. Z.; Xia, J. J.; Chen, Y.; Chen, T.; Hu, C.; Bao, Z. M.; Fu, X. C.; Wang, R. J.; Wang, Y.; Wang, Y. J.

    2017-09-01

    The object of this work was to determine the icing temperature in icing experiment. Firstly, a questionnaire investigation was carried out on 38 fire detachments in different regions. These Statistical percentage results were divided into northern east group and northern west group. Secondly, a significance analysis between these two results was made using Mann-Whitney U test. Then the icing temperature was determined in different regions. Thirdly, the icing experiment was made in the environment of -20°C in Daxing’an Mountain. The anti-icing effect of new fire protective clothing was verified in this icing.

  17. 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.

  18. 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

  19. Design of fire resistant concrete structures, using validated Fem models

    NARCIS (Netherlands)

    Erich, S.J.F.; Overbeek, van A.B.M.; Heijden, van der G.H.A.; Pel, L.; Huinink, H.P.; Vervuurt, A.H.J.M.; Schlangen, E.; Schlutter, de G.

    2008-01-01

    Fire safety of buildings and structures is an important issue, and has a great impact on human life and economy. One of the processes negatively affecting the strength of a concrete building or structure during fire is spalling. Many examples exists in which spalling of concrete during fire has

  20. Mission and design of the Fusion Ignition Research Experiment (FIRE)

    International Nuclear Information System (INIS)

    Meade, D.M.; Jardin, S.C.; Schmidt, J.

    2001-01-01

    Experiments are needed to test and extend present understanding of confinement, macroscopic stability, alpha-driven instabilities, and particle/power exhaust in plasmas dominated by alpha heating. A key issue is to what extent pressure profile evolution driven by strong alpha heating will act to self-organize advanced configurations with large bootstrap current fractions and internal transport barriers. A design study of a Fusion Ignition Research Experiment (FIRE) is underway to assess near term opportunities for advancing the scientific understanding of self-heated fusion plasmas. The emphasis is on understanding the behavior of fusion plasmas dominated by alpha heating (Q≥5) that are sustained for durations comparable to the characteristic plasma time scales (≥20 τ E and ∼τ skin , where τ skin is the time for the plasma current profile to redistribute at fixed current). The programmatic mission of FIRE is to attain, explore, understand and optimize alpha-dominated plasmas to provide knowledge for the design of attractive magnetic fusion energy systems. The programmatic strategy is to access the alpha-heating-dominated regime with confidence using the present advanced tokamak data base (e.g., Elmy-H-mode, ≤0.75 Greenwald density) while maintaining the flexibility for accessing and exploring other advanced tokamak modes (e. g., reversed shear, pellet enhanced performance) at lower magnetic fields and fusion power for longer durations in later stages of the experimental program. A major goal is to develop a design concept that could meet these physics objectives with a construction cost in the range of $1B. (author)

  1. An effective and practical fire-protection system. [for aircraft fuel storage and transport

    Science.gov (United States)

    Mansfield, J. A.; Riccitiello, S. R.; Fewell, L. L.

    1975-01-01

    A high-performance sandwich-type fire protection system comprising a steel outer sheath and insulation combined in various configurations is described. An inherent advantage of the sheath system over coatings is that it eliminates problems of weatherability, materials strength, adhesion, and chemical attack. An experimental comparison between the protection performance of state-of-the-art coatings and the sheath system is presented, with emphasis on the protection of certain types of steel tanks for fuel storage and transport. Sheath systems are thought to be more expensive than coatings in initial implementation, although they are less expensive per year for sufficiently long applications.

  2. A parametric study on the use of passive fire protection in FPSO topside module

    Directory of Open Access Journals (Sweden)

    Martin Friebe

    2014-12-01

    Full Text Available Fire is a continuous threat to FPSO topside modules as large amounts of oil and gas are passing through the modules. As a conventional measure to mitigate structural failure under fire, passive fire protection (PFP coatings are widely used on main structural members. However, an excessive use of PFP coatings can cause considerable cost for material purchase, installation, inspection and maintenance. Long installation time can be a risk since the work should be done nearly at the last fabrication stage. Thus, the minimal use of PFP can be beneficial to the reduction of construction cost and the avoidance of schedule delay. This paper presents a few case studies on how different applications of PFP have influence on collapse time of a FPSO module structure. A series of heat analysis and thermal elasto-plastic FE analysis are performed for different PFP coatings and the resultant collapse time and the amount of PFP coatings are compared with each other.

  3. Fire protection upgrading of four Russian 440/230 VVER units

    International Nuclear Information System (INIS)

    Corsini, G.; Yelfimov, S.

    1995-01-01

    The main goal of TACIS 3.6 a project funded by the Commission of the European Communities (CEC), was the front-end engineering for upgrading the Fire Protection System (FPS) of the safety-related equipment of Novovoronezh, Units 3 and 4, and Kola, Units 1 and 2, VVER 440/230 nuclear power plants. As a first step, all the safety-related equipment had to be identified, evaluation criteria had to be established and the existing FPS reviewed against the criteria. In the second step, the selection of the upgrading measures, depending on feasibility and cost estimate, has been accomplished, room by room. The third step, carried out on schedule and completed end July 95, has been essentially the preparation of the Technical Specifications for procurement of the needed equipment including remaining detail engineering. The Russian sub-contactor Atom Energo Project (AEP), who have been the designers of these older NPP s, have done the work with the Italian Ansaldo as the consultants of their Russian colleagues. Practical aspects of the engineering work are discussed and examples of improvements selected for retrofitting described. (author)

  4. 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

  5. Fire protection concepts for Timber-Glass Composite façades

    Directory of Open Access Journals (Sweden)

    Schleicher Andreas

    2016-01-01

    The main objectives can be summarized as follows: Growth and densification in urban areas require the development of intelligent and resource-efficient building systems for “Smart Cities” of the future. By using timber-glass composites (TGC the primary energy demand of buildings can be reduced substantially. This research project examines the feasibility of applications of this new technology in multi-story and high-rise buildings. Critical aspects concerning fire protection such as flammability of timber elements, fire spread and failure of façade elements with bracing capacity will be analyzed. Different strategies will be developed in case studies and validated by structural analysis. Large scale mock ups of TGC façade elements will be checked on their suitability in fire tests. The findings of this research will lead to innovative fire safety concepts for building systems with TGC façades. Compliance with the high safety standards for multi-story buildings in urban areas like Vienna is one of the main objectives of this work. The adaptation of these fire safety concepts to the national standards of the neighboring countries will be continued subsequently. The gained knowledge should lead to further cooperation with companies for serial productions with TGC technology.

  6. Planning for risk-informed/performance-based fire protection at nuclear power plants. Final report

    International Nuclear Information System (INIS)

    Najafi, B.; Parkinson, W.J.; Lee, J.A.

    1997-12-01

    This document presents a framework for discussing issues and building consensus towards use of fire modeling and risk technology in nuclear power plant fire protection program implementation. The plan describes a three-phase approach: development of core technologies, implementation of methods, and finally, case studies and pilot applications to verify viability of such methods. The core technologies are defined as fire modeling, fire and system tests, use of operational data, and system and risk techniques. The implementation phase addresses the programmatic issues involved in implementing a risk-informed/performance-based approach in an integrated approach with risk/performance measures. The programmatic elements include: (1) a relationship with fire codes and standards development as defined by the ongoing effort of NFPA for development of performance-based standards; (2) the ability for NRC to undertake inspection and enforcement; and (3) the benefit to utilities in terms of cost versus safety. The case studies are intended to demonstrate applicability of single issue resolution while pilot applications are intended to check the applicability of the integrated program as a whole

  7. Remotely-sensed active fire data for protected area management: eight-year patterns in the Manas National Park, India.

    Science.gov (United States)

    Takahata, Chihiro; Amin, Rajan; Sarma, Pranjit; Banerjee, Gitanjali; Oliver, William; Fa, John E

    2010-02-01

    The Terai-Duar savanna and grasslands, which once extended along most of the Himalayan foothills, now only remain in a number of protected areas. Within these localities, grassland burning is a major issue, but data on frequency and distribution of fires are limited. Here, we analysed the incidence of active fires, which only occur during the dry season (Nov.-Mar.), within a significant area of Terai grasslands: the Manas National Park (MNP), India. We obtained locations of 781 fires during the 2000-2008 dry seasons, from the Fire Information for Resource Management System (FIRMS) that delivers global MODIS hotspot/fire locations using remote sensing and GIS technologies. Annual number of fires rose significantly from around 20 at the start of the study period to over 90 after 2002, with most (85%) detected between December and January. Over half of the fires occurred in tall grasslands, but fire density was highest in wetland and riverine vegetation, dry at the time. Most burning took place near rivers, roads and the park boundary, suggesting anthropogenic origins. A kernel density map of all recorded fires indicated three heavily burnt areas in the MNP, all within the tall grasslands. Our study demonstrates, despite some technical caveats linked to fire detection technology, which is improving, that remote fire data can be a practical tool in understanding fire concentration and burning temporal patterns in highly vulnerable habitats, useful in guiding management.

  8. Fire protection system management in nuclear facilities: strengthening factor of integrated management system - a case study

    International Nuclear Information System (INIS)

    Santos, Joao Regis dos

    2005-01-01

    The present study investigated and analyzed the importance of a system of integrated safety manage, environment and health in a nuclear installation, having as perspective, the fire protection manage. The inquiry was made using a qualitative research involving a case study, where the considered environment was the Reconversion and UO 2 Plant of the Industrias Nucleares do Brasil (INB), located in Resende, Rio de Janeiro and the studied population, the managers and the staff directly involved with the aspects related to the safety of the industrial complex of the related company. The motivation for the research was the search of a bigger interaction of the questions related to the safety, environment and health in the nuclear industry having, as axle of the investigation, the fire protection. As a result, it was observed that in a nuclear installation, although dealing with diversified safety processes, integration is possible and necessary, since there are more reasons for integration than otherwise. (author)

  9. Tunnel fire dynamics

    CERN Document Server

    Ingason, Haukur; Lönnermark, Anders

    2015-01-01

    This book covers a wide range of issues in fire safety engineering in tunnels, describes the phenomena related to tunnel fire dynamics, presents state-of-the-art research, and gives detailed solutions to these major issues. Examples for calculations are provided. The aim is to significantly improve the understanding of fire safety engineering in tunnels. Chapters on fuel and ventilation control, combustion products, gas temperatures, heat fluxes, smoke stratification, visibility, tenability, design fire curves, heat release, fire suppression and detection, CFD modeling, and scaling techniques all equip readers to create their own fire safety plans for tunnels. This book should be purchased by any engineer or public official with responsibility for tunnels. It would also be of interest to many fire protection engineers as an application of evolving technical principles of fire safety.

  10. New concept of microprocessor protective devices design

    Directory of Open Access Journals (Sweden)

    Gurevich Vladimir

    2010-01-01

    Full Text Available Transition from electromechanical to digital protective relays is accompanied with serious technical problems. The author offers a new approach in designing the digital relays capable of solving these problems. It is proposed to construct digital relays in the form of standard modules from which it would be possible to assemble the digital relay in the same way as now a personal computer.

  11. Protection of High Ceiling Nuclear Facilities Using Photoelectric Sensors and Infrared Fire Detectors

    International Nuclear Information System (INIS)

    Wadoud, A.A.; El Eissawi, H.M.; Saleh, A.A.

    2017-01-01

    A variety of different security systems and components are commercially available and widely used. Before implementing a security system, it is important to understand the characteristics and requirements of the facility area to be protected. Technology and manufacturers of security devices are rapidly changing. It is necessary to use optimal security equipment suitable for the surrounding environment of the facility to be protected. Several security sensors can be used to protect the nuclear facilities, such as passive infrared detectors and glass breakage sensors, vibration detectors, and microwave sensors. This work introduces technical specifications, operation and method of installation for these detectors in nuclear facilities. Also a comparative study of different security sensors or equipment is provided. The photoelectric detectors and infrared fire beam smoke detectors are reliable, suitable and advanced security equipment. They can be used in special cases because of their advantages, this includes their long ranges and accuracy in performance. This paper presents a new concept for adapting the use infrared optical fire beam smoke detector as intrusion detection equipment in high ceiling buildings or towering height facilities. This is in addition to their main function, namely fire detection.The paper also provides a study for their types and installation method. Focus is made on the installation and operation method for two advanced security systems, and wireless control circuit for the overall system operation

  12. Developing biomedical devices design, innovation and protection

    CERN Document Server

    Andreoni, Giuseppe; Colombo, Barbara

    2013-01-01

    During the past two decades incredible progress has been achieved in the instruments and devices used in the biomedical field. This progress stems from continuous scientific research that has taken advantage of many findings and advances in technology made available by universities and industry. Innovation is the key word, and in this context legal protection and intellectual property rights (IPR) are of crucial importance. This book provides students and practitioners with the fundamentals for designing biomedical devices and explains basic design principles. Furthermore, as an aid to the dev

  13. Design principles for radiological protection instrumentation systems

    International Nuclear Information System (INIS)

    Wells, F.H.; Powell, R.G.

    1981-02-01

    This Code of Practice takes the form of recommendations intended for designers and installers of Radiological Protection Instrumentation, and should also be of value to the newcomer to the R.P.I. field. Topics are discussed under the following headings: outline of R.P.I. requirements, specifying the requirement, satisfying the requirements, (overall design, availability and reliability, information display, human factors, power supplies, manufacture, quality assurance, testing, and cost analysis), supply, location and operation of the equipment, importance of documentation. (U.K.)

  14. Model assessment of protective barrier designs

    International Nuclear Information System (INIS)

    Fayer, M.J.; Conbere, W.; Heller, P.R.; Gee, G.W.

    1985-11-01

    A protective barrier is being considered for use at the Hanford site to enhance the isolation of previously disposed radioactive wastes from infiltrating water, and plant and animal intrusion. This study is part of a research and development effort to design barriers and evaluate their performance in preventing drainage. A fine-textured soil (the Composite) was located on the Hanford site in sufficient quantity for use as the top layer of the protective barrier. A number of simulations were performed by Pacific Northwest Laboratory to analyze different designs of the barrier using the Composite soil as well as the finer-textured Ritzville silt loam and a slightly coarser soil (Coarse). Design variations included two rainfall rates (16.0 and 30.1 cm/y), the presence of plants, gravel mixed into the surface of the topsoil, an impermeable boundary under the topsoil, and moving the waste form from 10 to 20 m from the barrier edge. The final decision to use barriers for enhanced isolation of previously disposed wastes will be subject to decisions resulting from the completion of the Hanford Defense Waste Environmental Impact Statement, which addresses disposal of Hanford defense high-level and transuranic wastes. The one-dimensional simulation results indicate that each of the three soils, when used as the top layer of the protective barrier, can prevent drainage provided plants are present. Gravel amendments to the upper 30 cm of soil (without plants) reduced evaporation and allowed more water to drain

  15. Analysis of design strategies for mitigating the consequences of lithium fire within containment of controlled thermonuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Dube, D A; Kazimi, M S

    1978-07-01

    A lithium combustion model (LITFIRE) was developed to describe the physical and chemical processes which occur during a hypothetical lithium spill and fire. The model was used to study the effectiveness of various design strategies for mitigating the consequences of lithium fire, using the UWMAK-III features as a reference design. Calculations show that without any special fire protection measures, the containment may reach pressures of up to 32 psig when one coolant loop is spilled inside the reactor building. Temperatures as high as 2000/sup 0/F would also be experienced by some of the containment structures. These consequences were found to diminish greatly by the incorporation of a number of design strategies including initially subatmospheric containment pressures, enhanced structural surface heat removal capability, initially low oxygen concentrations, and active post-accident cooling of the containment gas. The EBTR modular design was found to limit the consequences of a lithium spill, and hence offers a potential safety advantage. Calculations of the maximum flame temperature resulting from lithium fire indicate that none of the radioactive first wall materials under consideration would vaporize, and only a few could possibly melt.

  16. Analysis of design strategies for mitigating the consequences of lithium fire within containment of controlled thermonuclear reactors

    International Nuclear Information System (INIS)

    Dube, D.A.; Kazimi, M.S.

    1978-07-01

    A lithium combustion model (LITFIRE) was developed to describe the physical and chemical processes which occur during a hypothetical lithium spill and fire. The model was used to study the effectiveness of various design strategies for mitigating the consequences of lithium fire, using the UWMAK-III features as a reference design. Calculations show that without any special fire protection measures, the containment may reach pressures of up to 32 psig when one coolant loop is spilled inside the reactor building. Temperatures as high as 2000 0 F would also be experienced by some of the containment structures. These consequences were found to diminish greatly by the incorporation of a number of design strategies including initially subatmospheric containment pressures, enhanced structural surface heat removal capability, initially low oxygen concentrations, and active post-accident cooling of the containment gas. The EBTR modular design was found to limit the consequences of a lithium spill, and hence offers a potential safety advantage. Calculations of the maximum flame temperature resulting from lithium fire indicate that none of the radioactive first wall materials under consideration would vaporize, and only a few could possibly melt

  17. French position paper on sodium fires, design and testing

    International Nuclear Information System (INIS)

    Malet, J.C.; Casselman, C.; Charpenel, J.; Duverger de Cuy, G.; Rzekiecki, R.; Dufresne, J.; Lo Pinto, P.; Montaignac de; Herault, A.

    1983-01-01

    This document gives an up-to-date account of studies carried out in France in the fields of sodium fires, extinction, filtration and prefiltration of aerosols originating from a sodium fire, and of sodium concrete reactions. It also indicates how the CEA, in collaboration with the CNEN, intends to deal with scale effects. (author)

  18. Linking management effectiveness indicators to observed effects of protected areas on fire occurrence in the Amazon rainforest.

    Science.gov (United States)

    Nolte, Christoph; Agrawal, Arun

    2013-02-01

    Management-effectiveness scores are used widely by donors and implementers of conservation projects to prioritize, track, and evaluate investments in protected areas. However, there is little evidence that these scores actually reflect the capacity of protected areas to deliver conservation outcomes. We examined the relation between indicators of management effectiveness in protected areas and the effectiveness of protected areas in reducing fire occurrence in the Amazon rainforest. We used data collected with the Management Effectiveness Tracking Tool (METT) scorecard, adopted by some of the world's largest conservation organizations to track management characteristics believed to be crucial for protected-area effectiveness. We used the occurrence of forest fires from 2000 through 2010 as a measure of the effect of protected areas on undesired land-cover change in the Amazon basin. We used matching to compare the estimated effect of protected areas with low versus high METT scores on fire occurrence. We also estimated effects of individual protected areas on fire occurrence and explored the relation between these effects and METT scores. The relations between METT scores and effects of protected areas on fire occurrence were weak. Protected areas with higher METT scores in 2005 did not seem to have performed better than protected areas with lower METT scores at reducing fire occurrence over the last 10 years. Further research into the relations between management-effectiveness indicators and conservation outcomes in protected areas seems necessary, and our results show that the careful application of matching methods can be a suitable method for that purpose. ©2012 Society for Conservation Biology.

  19. 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

  20. Oriented clay nanopaper from biobased components--mechanisms for superior fire protection properties.

    Science.gov (United States)

    Carosio, F; Kochumalayil, J; Cuttica, F; Camino, G; Berglund, L

    2015-03-18

    The toxicity of the most efficient fire retardant additives is a major problem for polymeric materials. Cellulose nanofiber (CNF)/clay nanocomposites, with unique brick-and-mortar structure and prepared by simple filtration, are characterized from the morphological point of view by scanning electron microscopy and X-ray diffraction. These nanocomposites have superior fire protection properties to other clay nanocomposites and fiber composites. The corresponding mechanisms are evaluated in terms of flammability (reaction to a flame) and cone calorimetry (exposure to heat flux). These two tests provide a wide spectrum characterization of fire protection properties in CNF/montmorrilonite (MTM) materials. The morphology of the collected residues after flammability testing is investigated. In addition, thermal and thermo-oxidative stability are evaluated by thermogravimetric analyses performed in inert (nitrogen) and oxidative (air) atmospheres. Physical and chemical mechanisms are identified and related to the unique nanostructure and its low thermal conductivity, high gas barrier properties and CNF/MTM interactions for char formation.

  1. Fire safety engineering

    International Nuclear Information System (INIS)

    Smith, D.N.

    1989-01-01

    The periodic occurrence of large-scale, potentially disastrous industrial accidents involving fire in hazardous environments such as oilwell blowouts, petrochemical explosions and nuclear installations highlights the need for an integrated approach to fire safety engineering. Risk reduction 'by design' and rapid response are of equal importance in the saving of life and property in such situations. This volume of papers covers the subject thoroughly, touching on such topics as hazard analysis, safety design and testing, fire detection and control, and includes studies of fire hazard in the context of environment protection. (author)

  2. Computer code structure for evaluation of fire protection measures and fighting capability at nuclear plants

    International Nuclear Information System (INIS)

    Anton, V.

    1997-01-01

    In this work a computer code structure for Fire Protection Measures (FPM) and Fire Fighting Capability (FFC) at Nuclear Power Plants (NPP) is presented. It allows to evaluate the category (satisfactory (s), needs for further evaluation (n), unsatisfactory (u)) to which belongs the given NPP for a self-control in view of an IAEA inspection. This possibility of a self assessment resulted from IAEA documents. Our approach is based on international experience gained in this field and stated in IAEA recommendations. As an illustration we used the FORTRAN programming language statement to make clear the structure of the computer code for the problem taken into account. This computer programme can be conceived so that some literal message in English and Romanian languages be displayed beside the percentage assessments. (author)

  3. 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.

  4. Analysis of Architectural Building Design Influences on Fire Spread in Densely Urban Settlement using Cellular Automata

    Science.gov (United States)

    Tambunan, L.; Salamah, H.; Asriana, N.

    2017-03-01

    This study aims to determine the influence of architectural design on the risk of fire spread in densely urban settlement area. Cellular Automata (CA) is used to analyse the fire spread pattern, speed, and the extent of damage. Four cells represent buildings, streets, and fields characteristic in the simulated area, as well as their flammability level and fire spread capabilities. Two fire scenarios are used to model the spread of fire: (1) fire origin in a building with concrete and wood material majority, and (2) fire origin in building with wood material majority. Building shape, building distance, road width, and total area of wall openings are considered constant, while wind is ignored. The result shows that fire spread faster in the building area with wood majority than with concrete majority. Significant amount of combustible building material, absence of distance between buildings, narrow streets and limited fields are factors which influence fire spread speed and pattern as well as extent of damage when fire occurs in the densely urban settlement area.

  5. 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...

  6. Protective containment behaviour under exceeded design loads

    International Nuclear Information System (INIS)

    Holub, I.; Stepan, J.; Maly, J.; Schererova, K.

    2003-01-01

    The contribution describes the calculation results of the behaviour of containment structure if loaded in excess of its design load. The Temelin NPP comprises two WWER 1000 blocks and containment consists of a pre-stressed reinforced concrete structure with a system of unbonded cables. The objective of the calculations was to determine the level of load caused by the internal pressure and temperature at which the containment protective function would fail. In the first step, the maximum overpressure was determined, which may be transferred by the containment structure. In further steps analyses were made of various combinations of simultaneous pressure and temperature loads. The contribution presents relevant calculation results, including the evaluation of containment structure behaviour including liner under loads that exceed its design parameters. (author)

  7. GIS Fuzzy Expert System for the assessment of ecosystems vulnerability to fire in managing Mediterranean natural protected areas.

    Science.gov (United States)

    Semeraro, Teodoro; Mastroleo, Giovanni; Aretano, Roberta; Facchinetti, Gisella; Zurlini, Giovanni; Petrosillo, Irene

    2016-03-01

    A significant threat to the natural and cultural heritage of Mediterranean natural protected areas (NPAs) is related to uncontrolled fires that can cause potential damages related to the loss or a reduction of ecosystems. The assessment and mapping of the vulnerability to fire can be useful to reduce landscape damages and to establish priority areas where it is necessary to plan measures to reduce the fire vulnerability. To this aim, a methodology based on an interactive computer-based system has been proposed in order to support NPA's management authority for the identification of vulnerable hotspots to fire through the selection of suitable indicators that allow discriminating different levels of sensitivity (e.g. Habitat relevance, Fragmentation, Fire behavior, Ecosystem Services, Vegetation recovery after fire) and stresses (agriculture, tourism, urbanization). In particular, a multi-criteria analysis based on Fuzzy Expert System (FES) integrated in a GIS environment has been developed in order to identify and map potential "hotspots" of fire vulnerability, where fire protection measures can be undertaken in advance. In order to test the effectiveness of this approach, this approach has been applied to the NPA of Torre Guaceto (Apulia Region, southern Italy). The most fire vulnerable areas are the patch of century-old forest characterized by high sensitivity and stress, and the wetlands and century-old olive groves due to their high sensitivity. The GIS fuzzy expert system provides evidence of its potential usefulness for the effective management of natural protected areas and can help conservation managers to plan and intervene in order to mitigate the fire vulnerability in accordance with conservation goals. Copyright © 2015 Elsevier Ltd. All rights reserved.

  8. Plasma-aided surface technology for modification of materials referred to fire protection

    International Nuclear Information System (INIS)

    Dineff, P.; Gospodinova, D.; Kostova, L.; Vladkova, T.; Chen, E.

    2008-01-01

    There has been considerable interest in dielectric barrier air discharge at atmospheric pressure and room temperature over the past decade due to the increased number of industrial applications. New plasma-aided capillary impregnation technology for flame spreading stop and fire protection of porous materials was developed. Research, based on thermogravimetric analysis (TGA), differential thermal analysis (DTA), and differential scanning calorimetry (DSC), proves that plasma-chemical surface pre-treatment exert material change on chemical interaction between phosphorus containing flame retardant and wood matrix (Pinus sylvestris, Bulgaria; Pseudotsuga, Canada)

  9. Radiative and conductive heat transfer in a nongrey semitransparent medium. Application to fire protection curtains

    Energy Technology Data Exchange (ETDEWEB)

    Berour, Nacer; Lacroix, David E-mail: david.lacroix@lemta.uhp-nancy.fr; Boulet, Pascal; Jeandel, Gerard

    2004-06-01

    This paper deals with heat transfer in nongrey media which scatter, absorb and emit radiation. Considering a two dimensional geometry, radiative and conductive phenomena through the medium have been taken into account. The radiative part of the problem was solved using the discrete ordinate method with classical S{sub n} quadratures. The absorption and scattering coefficients involved in the radiative transfer equation (RTE) were obtained from the Mie theory. Conduction inside the medium was linked to the RTE through the energy conservation. Validation of the model has been achieved with several simulation of water spray curtains used as fire protection walls.

  10. Design an online course of radiological protection

    International Nuclear Information System (INIS)

    Garcia S, R.; Del Sol F, S.; Rivera M, T.; Sanchez G, D.

    2015-10-01

    Currently there is a vast research about the harmful effects of the use of ionizing radiation in medical procedures and in recent years struck by the rapid innovation in imaging equipment, considerably increasing the radiation dose received both patients and professionals in the radiodiagnosis area, service having the greatest demand in our country. The main strategy that has so far is education, that is, to inform all those involved in managing ionizing radiation about the applications and risks associated with them. Generally it requires that all personnel occupationally exposed attesting a course of radiation protection. However, the high demand for this type of medical services and poorly trained staff, makes taking a classroom course for personnel occupationally exposed is complicated. So that in the Instituto Politecnico Nacional (IPN) we are designing a course in radiation protection to be implemented online, through the virtual platform Moodle in a first stage, and a massive open online course as the second stage so that can be carried by anyone interested in the subject, without having to appear in person. This will allows to reach the largest possible number of personnel occupationally exposed to just have a computer with internet access. (Author)

  11. Design Constraints for Liquid-Protected Divertors

    International Nuclear Information System (INIS)

    Shin, S.; Abdel-Khalik, S.I.; Yoda, M.

    2005-01-01

    Recent work on liquid-surface-protected plasma facing components has resulted in the establishment of operating windows for candidate liquids, as well as limits on the maximum allowable liquid surface temperature in order to limit plasma impurities from liquid evaporation. In this study, an additional constraint on the maximum allowable surface temperature gradient (i.e., heat flux gradient) has been quantified. Spatial variations in the wall and liquid surface temperatures are expected due to variations in the incident radiation and particle fluxes. Thermocapillary forces created by such temperature gradients can lead to film rupture and dry spot formation in regions of elevated local temperatures. Here, attention has been focused on ''non-flowing'' thin liquid films similar to those formed on the surface of porous wettedwall components. Future analyses will include the effects of macroscopic fluid motion, and MHD forces.A numerical model using the level contour reconstruction method was used to follow the evolution of the liquid free surface above a non-isothermal solid surface. The model was used to develop generalized charts for the maximum allowable spatial temperature gradients (i.e., the critical Marangoni number) as a function of the governing non-dimensional variables, viz. the Weber, Froude, and Prandtl numbers, and aspect ratio. Attention was focused on the asymptotic limit for thin liquid films (i.e., low aspect ratio) which provides a lower bound for the maximum allowable temperature gradients. Specific examples for lithium, Flibe, lithium-lead, tin, and gallium are presented. The generalized charts developed in this investigation will allow reactor designers to identify design windows for successful operation of liquid-protected plasma facing components for various coolants, film thicknesses, and operating conditions

  12. The Design of a Fire Source in Scale-Model Experiments with Smoke Ventilation

    DEFF Research Database (Denmark)

    Nielsen, Peter Vilhelm; Brohus, Henrik; la Cour-Harbo, H.

    2004-01-01

    The paper describes the design of a fire and a smoke source for scale-model experiments with smoke ventilation. It is only possible to work with scale-model experiments where the Reynolds number is reduced compared to full scale, and it is demonstrated that special attention to the fire source...... (heat and smoke source) may improve the possibility of obtaining Reynolds number independent solutions with a fully developed flow. The paper shows scale-model experiments for the Ofenegg tunnel case. Design of a fire source for experiments with smoke ventilation in a large room and smoke movement...

  13. Standard on fire protection for self-propelled and mobile surface mining equipment. 2001 ed.

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    Safeguard life and property against fire and related hazards in mines with the latest requirements in NFPA 121. This 2001 edition covers fire detection, suppression, ignition sources, fire risk assessment and maintenance of mining equipment systems. 4 apps.

  14. 'Passive fire protection in nuclear power plants' - German technologies of the company svt Brandschutz in future as well in Korean NPPs? -

    International Nuclear Information System (INIS)

    Bremer, Joerg; Kim, Duill; Wendt, Ruediger

    2002-01-01

    Fires in NPPs are unfortunately not avoidable and to consider during the planning and operation period of the plants. The multitude of combustible materials which are used especially cables, oils and other building materials describe a potential source of danger. In Germany recently a new planning guideline for the fire protection field in NPPs has been adopted: the nuclear guideline KTA 1401. This document certainly is one of the most progressive guidelines for the fire protection field and has united · structural engineering elements of fire protection · electrotechnical and machine components · as well as questions of fire alarm and organisation measures. Passive and active fire protection measures are explained and layed down in their complexity within this document. Our group of companies has realised quit a lot of fire protection projects in Europe during the last years, especially within retrofitting measures for NPPs in Germany, Switzerland, Russia, the Ukraine and Lithuania, the Czech and Slovak Republic as well as within decommissioning projects of NPPs. We have carried out international fire protection projects of the EBRD, London, and within the framework of TACIS projects of the European Commission, i. a. linked with the working out of fire protection analyses for NPPs realised in close co-operation with the Germanischer Lloyd, Hamburg. We especially have wide experiences in improving the fire protection of cable installations where a 100% separation of the different safety systems is not any longer possible

  15. 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

  16. Protecting count queries in study design.

    Science.gov (United States)

    Vinterbo, Staal A; Sarwate, Anand D; Boxwala, Aziz A

    2012-01-01

    Today's clinical research institutions provide tools for researchers to query their data warehouses for counts of patients. To protect patient privacy, counts are perturbed before reporting; this compromises their utility for increased privacy. The goal of this study is to extend current query answer systems to guarantee a quantifiable level of privacy and allow users to tailor perturbations to maximize the usefulness according to their needs. A perturbation mechanism was designed in which users are given options with respect to scale and direction of the perturbation. The mechanism translates the true count, user preferences, and a privacy level within administrator-specified bounds into a probability distribution from which the perturbed count is drawn. Users can significantly impact the scale and direction of the count perturbation and can receive more accurate final cohort estimates. Strong and semantically meaningful differential privacy is guaranteed, providing for a unified privacy accounting system that can support role-based trust levels. This study provides an open source web-enabled tool to investigate visually and numerically the interaction between system parameters, including required privacy level and user preference settings. Quantifying privacy allows system administrators to provide users with a privacy budget and to monitor its expenditure, enabling users to control the inevitable loss of utility. While current measures of privacy are conservative, this system can take advantage of future advances in privacy measurement. The system provides new ways of trading off privacy and utility that are not provided in current study design systems.

  17. 36 CFR 2.13 - Fires.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Fires. 2.13 Section 2.13... PROTECTION, PUBLIC USE AND RECREATION § 2.13 Fires. (a) The following are prohibited: (1) Lighting or maintaining a fire, except in designated areas or receptacles and under conditions that may be established by...

  18. Studying the Post-Fire Response of Vegetation in California Protected Areas with NDVI-based Pheno-Metrics

    Science.gov (United States)

    Jia, S.; Gillespie, T. W.

    2016-12-01

    Post-fire response from vegetation is determined by the intensity and timing of fires as well as the nature of local biomes. Though the field-based studies focusing on selected study sites helped to understand the mechanisms of post-fire response, there is a need to extend the analysis to a broader spatial extent with the assistance of remotely sensed imagery of fires and vegetation. Pheno-metrics, a series of variables on the growing cycle extracted from basic satellite measurements of vegetation coverage, translate the basic remote sensing measurements such as NDVI to the language of phenology and fire ecology in a quantitative form. In this study, we analyzed the rate of biomass removal after ignition and the speed of post-fire recovery in California protected areas from 2000 to 2014 with USGS MTBS fire data and USGS eMODIS pheno-metrics. NDVI drop caused by fire showed the aboveground biomass of evergreen forest was removed much slower than shrubland because of higher moisture level and greater density of fuel. In addition, the above two major land cover types experienced a greatly weakened immediate post-fire growing season, featuring a later start and peak of season, a shorter length of season, and a lower start and peak of NDVI. Such weakening was highly correlated with burn severity, and also influenced by the season of fire and the land cover type, according to our modeling between the anomalies of pheno-metrics and the difference of normalized burn ratio (dNBR). The influence generally decayed over time, but can remain high within the first 5 years after fire, mostly because of the introduction of exotic species when the native species were missing. Local-specific variables are necessary to better address the variance within the same fire and improve the outcomes of models. This study can help ecologists in validating the theories of post-fire vegetation response mechanisms and assist local fire managers in post-fire vegetation recovery.

  19. Effects of weathering on performance of intumescent coatings for structure fire protection in the wildland-urban interface

    Science.gov (United States)

    Bahrani, Babak

    The objective of this study was to investigate the effects of weathering on the performance of intumescent fire-retardant coatings on wooden products. The weathering effects included primary (solar irradiation, moisture, and temperature) and secondary (environmental contaminants) parameters at various time intervals. Wildland urban interface (WUI) fires have been an increasing threat to lives and properties. Existing solutions to mitigate the damages caused by WUI fires include protecting the structures from ignition and minimizing the fire spread from one structure to another. These solutions can be divided into two general categories: active fire protection systems and passive fire protection systems. Passive systems are either using pre-applied wetting agents (water, gel, or foam) or adding an extra layer (composite wraps or coatings). Fire-retardant coating treatment methods can be divided into impregnated (penetrant) and intumescent categories. Intumescent coatings are easy to apply, economical, and have a better appearance in comparison to other passive fire protection methods, and are the main focus of this study. There have been limited studies conducted on the application of intumescent coatings on wooden structures and their performance after long-term weathering exposure. The main concerns of weathering effects are: 1) the reduction of ignition resistance of the coating layer after weathering; and 2) the fire properties of coatings after weathering since coatings might contribute as a combustible fuel and assist the fire growth after ignition. Three intumescent coatings were selected and exposed to natural weathering conditions in three different time intervals. Two types of tests were performed on the specimens: a combustibility test consisted of a bench-scale performance evaluation using a Cone Calorimeter, and a thermal decomposition test using Simultaneous Differential Scanning Calorimetry (DSC) and Thermogravimetric Analysis (TGA) method (also known

  20. Methodology for Designing Fault-Protection Software

    Science.gov (United States)

    Barltrop, Kevin; Levison, Jeffrey; Kan, Edwin

    2006-01-01

    A document describes a methodology for designing fault-protection (FP) software for autonomous spacecraft. The methodology embodies and extends established engineering practices in the technical discipline of Fault Detection, Diagnosis, Mitigation, and Recovery; and has been successfully implemented in the Deep Impact Spacecraft, a NASA Discovery mission. Based on established concepts of Fault Monitors and Responses, this FP methodology extends the notion of Opinion, Symptom, Alarm (aka Fault), and Response with numerous new notions, sub-notions, software constructs, and logic and timing gates. For example, Monitor generates a RawOpinion, which graduates into Opinion, categorized into no-opinion, acceptable, or unacceptable opinion. RaiseSymptom, ForceSymptom, and ClearSymptom govern the establishment and then mapping to an Alarm (aka Fault). Local Response is distinguished from FP System Response. A 1-to-n and n-to- 1 mapping is established among Monitors, Symptoms, and Responses. Responses are categorized by device versus by function. Responses operate in tiers, where the early tiers attempt to resolve the Fault in a localized step-by-step fashion, relegating more system-level response to later tier(s). Recovery actions are gated by epoch recovery timing, enabling strategy, urgency, MaxRetry gate, hardware availability, hazardous versus ordinary fault, and many other priority gates. This methodology is systematic, logical, and uses multiple linked tables, parameter files, and recovery command sequences. The credibility of the FP design is proven via a fault-tree analysis "top-down" approach, and a functional fault-mode-effects-and-analysis via "bottoms-up" approach. Via this process, the mitigation and recovery strategy(s) per Fault Containment Region scope (width versus depth) the FP architecture.

  1. Design and Realization of Ship Fire Simulation Training System Based on Unity3D

    Science.gov (United States)

    Ting, Ye; Feng, Chen; Wenqiang, Wang; Kai, Yang

    2018-01-01

    Ship fire training is a very important training to ensure the safety of the ship, but limited by the characteristics of the ship itself, it is difficult to carry out fire training on the ship. This paper proposes to introduce a virtual reality technology to build a set of ship fire simulation training system, used to improve the quality of training, reduce training costs. First, the system design ideas are elaborated, and the system architecture diagram is given. Then, the key technologies in the process of system implementation are analyzed. Finally, the system examples are built and tested.

  2. Design Of Photovoltaic Powered Cathodic Protection System

    Directory of Open Access Journals (Sweden)

    Golina Samir Adly

    2017-07-01

    Full Text Available The corrosion caused by chemical reaction between metallic structures and surrounding mediums such as soil or water .the CP cathodic protection system is used to protect metallic structure against corrosion. Cathodic protection CP used to minimize corrosion by utilizing an external source of electrical current which forces the entire structure to become a cathode. There are two Types of cathodic protection system Galvanic current Impressed current.the Galvanic current is called a sacrificial anode is connected to the protected structure cathode through a DC power supply. In Galvanic current system a current passes from the sacrificing anode to the protected structure .the sacrificial anode is corroded rather than causing the protected structure corrosion .protected structure requires a constant current to stop the corrosion which determined by area structure metal and the surrounding medium. The rains humidity are decrease soil resistivity and increase the DC current .The corrosion and over protection resulting from increase in the DC current is harmful for the metallic structure. This problem can be solved by conventional cathodic protection system by manual adjustment of DC voltage periodically to obtain a constant current .the manual adjustment of DC voltage depends on experience of the technician and using the accuracy of the measuring equipment. The errors of measuring current depend on error from the technician or error from the measuring equipment. the corrosion of structure may occur when the interval between two successive adjustment is long .An automatically regulated cathodic protection system is used to overcome problems from conventional cathodic protection system .the regulated cathodic protection system adjust the DC voltage of the system automatically when it senses the variations of surrounding medium resistivity so the DC current is constant at the required level.

  3. 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)

  4. Planetary Protection Considerations in EVA System Design

    Science.gov (United States)

    Eppler, Dean B.; Kosmo, Joseph J.

    2011-01-01

    very little expression of these anomalies. hardware from the human-occupied area may limit (although not likely eliminate) external materials in the human habitat. Definition of design-to requirements is critical to understanding technical feasibility and costs. The definition of Planetary Protection needs in relation to EVA mission and system element development cost impacts should be considered and interpreted in terms of Plausible Protection criteria. Since EVA operations will have the most direct physical interaction with the Martian surface, PP needs should be considered in the terms of mitigating hardware and operations impacts and costs.

  5. Evaluation of mechanical design fire brick at test section on the HeaTiNG-02

    International Nuclear Information System (INIS)

    Dedy Haryanto; Riswan Djambiar; Sagino; Edy Sumarno

    2013-01-01

    The activity was carried out due to the modification of the heating in the HeaTiNG-02 test section. Modification of the heater needs to be done to overcome the obstacles that arise as part of the test section is used. Constraint that often arises is the fall of the heating source with super khantal material when it reaches a certain temperature. To mitigate the super khantal position is initially converted into a vertical position horizontal. The change from vertical to horizontal position on super khantal cause any deformities in refractory fire brick which serves as a support super khantal. Manufacture of refractory design fire brick formation and mechanical strength evaluation performed using CATIA V5 R20 software. Evaluation of fireproof rock mechanics to be based on the mechanical properties of alumina as a refractory material of fire brick. The results of the analysis have a fire brick design stress greater than the bend strength alumina materials, so that the necessary checks before and after the experiment as well as the replacement of refractory fire brick if something is broken. Translational greatest displacement 0.453 mm at a temperature of 1575 K did not give any meaningful form. Thus the refractory fire brick design can be used as heating source support in the HeaTiNG-02 test section with checks before and after the operation. (author)

  6. Guidelines of the Design of Electropyrotechnic Firing Circuit for Unmanned Flight and Ground Test Projects

    Science.gov (United States)

    Gonzalez, Guillermo A.; Lucy, Melvin H.; Massie, Jeffrey J.

    2013-01-01

    The NASA Langley Research Center, Engineering Directorate, Electronic System Branch, is responsible for providing pyrotechnic support capabilities to Langley Research Center unmanned flight and ground test projects. These capabilities include device selection, procurement, testing, problem solving, firing system design, fabrication and testing; ground support equipment design, fabrication and testing; checkout procedures and procedure?s training to pyro technicians. This technical memorandum will serve as a guideline for the design, fabrication and testing of electropyrotechnic firing systems. The guidelines will discuss the entire process beginning with requirements definition and ending with development and execution.

  7. Improving Reliability of a fire-fighting pump set with Axiomatic Design

    Directory of Open Access Journals (Sweden)

    Arcidiacono Gabriele

    2017-01-01

    Full Text Available This paper introduces a case study featuring Axiomatic Design and Multi-Level Hierarchical model (MLH applied to redesign a fire-fighting pump set. In particular, two different design concepts are presented to be applied to the supporting frame of the system to limit a vibration problem that can arise during potential malfunctioning of the fire-fighting pump. The selection of the best design has been carried out through reliability evaluation process and through the cost of failure based on the MLH model.

  8. Review of national and international demands on fire protection in nuclear power plants and their application in the Swedish nuclear industry; Oeversikt av nationell och internationell kravbild avseende brandskydd paa kaernkraftverk och hur dessa tillaempas i svensk kaernkraftindustri

    Energy Technology Data Exchange (ETDEWEB)

    Fredholm, Lotta (Tyrens AB, Malmoe (Sweden))

    2010-02-15

    regarding fire safety at nuclear power plants that have been studied are regulation from USA, Finland, Great Britain, Canada, Germany and the international organisations IAEA and WENRA. The conclusion of this study is that the differences between the regulations mostly are differences in detailed fire safety design. Some differences can not easily be explained by national. Differences and the resulting effect on the overall fire safety is very difficult to evaluate. Regarding how to improve the Swedish regulations regarding fire safety at nuclear power plants there are different possibilities. One is to complement the regulations with acceptable solutions on how to design the fire protection. If this shall be done IAEAs Safety Guides seem to be the easiest of the more detailed fire requirements to adopt to Swedish conditions. Another way of improving the regulation is to give more guidance on how to proof that the rules are fulfilled. In this case the Canadian guidelines may be a good source of ideas and information

  9. Cable tray fire tests

    International Nuclear Information System (INIS)

    Klamerus, L.J.

    1978-01-01

    Funds were authorized by the Nuclear Regulatory Commission to provide data needed for confirmation of the suitability of current design standards and regulatory guides for fire protection and control in water reactor power plants. The activities of this program through August 1978 are summarized. A survey of industry to determine current design practices and a screening test to select two cable constructions which were used in small scale and full scale testing are described. Both small and full scale tests to assess the adequacy of fire retardant coatings and full scale tests on fire shields to determine their effectiveness are outlined

  10. Analysis of Moisture Evaporation from Underwear Designed for Fire-Fighters

    Directory of Open Access Journals (Sweden)

    Elena Onofrei

    2015-03-01

    Full Text Available In this study we analysed the effect of moisture on the thermal protective performance of fire-fighter clothing in case of routine fire-fighting conditions. In the first stage of this research we investigated simultaneous heat and moisture transfer through a single-layer fabric, used as underwear for fire-fighters, at different moisture conditions. In the second stage of the study, the underwear in dry and wet state was tested together with protective clothing systems for fire-fighter consisting of three or four layers. It was found that during the evaporation of the moisture, a temperature plateau appeared during which temperatures hardly rose. The energy consumption used for the phase change of moisture located in the assembly dominated the heat transfer process as long as there was moisture present. As soon as all water had evaporated, the temperatures approached the temperatures measured for dry samples. The moisture within the clothing assembly did not lead to increased temperatures compared with the measurements with dry samples. This research has confirmed that moisture can positively affect the thermal protection of a clothing system.

  11. Design of 500kW grate fired test facility using CFD

    DEFF Research Database (Denmark)

    Rosendahl, Lasse Aistrup; Kær, Søren Knudsen; Jørgensen, K.

    2005-01-01

    A 500kW vibrating grate fired test facility for solid biomass fuels has been designed using numerical models including CFD. The CFD modelling has focussed on the nozzle layout and flowpatterns in the lower part of the furnace, and the results have established confidence in the chosen design...

  12. Research on design and firing performance of Si-based detonator

    Directory of Open Access Journals (Sweden)

    Rui-zhen Xie

    2014-03-01

    Full Text Available For the chip integration of MEMS (micro-electromechanical system safety and arming device, a miniature detonator needs to be developed to reduce the weight and volume of explosive train. A Si-based micro-detonator is designed and fabricated, which meets the requirement of MEMS safety and arming device. The firing sensitivity of micro-detonator is tested according to GJB/z377A-94 sensitivity test methods: Langlie. The function time of micro-detonator is measured using wire probe and photoelectric transducer. The result shows the average firing voltage is 6.4 V when the discharge capacitance of firing electro-circuit is 33 μF. And the average function time is 5.48 μs. The firing energy actually utilized by Si-based micro-detonator is explored.

  13. 29 CFR 553.213 - Public agency employees engaged in both fire protection and law enforcement activities.

    Science.gov (United States)

    2010-07-01

    ... regardless of how the employee's time is divided between the two activities. However, all time spent in... spends the majority of work time during the work period. ... 29 Labor 3 2010-07-01 2010-07-01 false Public agency employees engaged in both fire protection and...

  14. FireProt: web server for automated design of thermostable proteins

    Science.gov (United States)

    Musil, Milos; Stourac, Jan; Brezovsky, Jan; Prokop, Zbynek; Zendulka, Jaroslav; Martinek, Tomas

    2017-01-01

    Abstract There is a continuous interest in increasing proteins stability to enhance their usability in numerous biomedical and biotechnological applications. A number of in silico tools for the prediction of the effect of mutations on protein stability have been developed recently. However, only single-point mutations with a small effect on protein stability are typically predicted with the existing tools and have to be followed by laborious protein expression, purification, and characterization. Here, we present FireProt, a web server for the automated design of multiple-point thermostable mutant proteins that combines structural and evolutionary information in its calculation core. FireProt utilizes sixteen tools and three protein engineering strategies for making reliable protein designs. The server is complemented with interactive, easy-to-use interface that allows users to directly analyze and optionally modify designed thermostable mutants. FireProt is freely available at http://loschmidt.chemi.muni.cz/fireprot. PMID:28449074

  15. Design and fabrication of a 50 MWt prototypical MHD coal-fired combustor

    International Nuclear Information System (INIS)

    Albright, J.; Braswell, R.; Listvinsky, G.; McAllister, M.; Myrick, S.; Ono, D.; Thom, H.

    1992-01-01

    A prototypical 50 MWt coal-fired combustor has been designed and fabricated as part of the Magnetohydrodynamic (MHD) Integrated Topping Cycle (ITC) Program. This is a DOE-funded program to develop a prototypical MHD power train to be tested at the Component Development and Integration Facility (CDIF) in Butte, Montana. The prototypical combustor is an outgrowth of the 50 MWt workhorse combustor which has previously been tested at the CDIF. In addition to meeting established performance criteria of the existing 50 MWt workhorse combustor, the prototypical combustor design is required to be scaleable for use at the 250 MWt retrofit level. This paper presents an overview of the mechanical design of the prototypical combustor and a description of its fabrication. Fabrication of the 50 MWt prototypical coal-fired combustor was completed in February 1992 and hot-fire testing is scheduled to begin in May 1992

  16. The Nuclear Safety Council's Instruction IS-30 on program requirements of fire protection at nuclear power plants; La instruccion IS-30 del consejo de Seguridad Nuclear sobre requisitos del programa de proteccion contraincendios en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

    The Nuclear Safety Councils Instrumentation IS-30 is the standard that establishes the fire protection program requirements for the Spanish nuclear power plants with operating license in order to satisfy the two fire protection objectives, which are the adoption of the defense-in-depth principle for fire protection and, by fire area confinement, to ensure that one train of components needed to achieve and maintain the safe shutdown conditions is free of fire damage, and that radioactive liberation is minimized. (Author)

  17. 29 CFR Appendix C to Subpart L of... - Fire Protection References For Further Information

    Science.gov (United States)

    2010-07-01

    ..., Batterymarch Park, Quincy, MA 02269 . 3. Fire Fighter Professional Qualifications, NFPA 1001; National Fire... of Equipment for the Removal of Smoke and Grease-Laden Vapor from Commercial Cooking Equipment, NFPA...

  18. 309 Building fire protection analysis and justification for deactivation of sprinkler system. Revision 1

    International Nuclear Information System (INIS)

    Conner, R.P.

    1997-01-01

    Provide a 'graded approach' fire evaluation in preparation for turnover to Environmental Restoration Contractor for D and D. Scope includes revising 309 Building book value and evaluating fire hazards, radiological and toxicological releases, and life safety issues

  19. Development of Human Factors Engineering Requirements for Fire Fighting Protective Equipment

    National Research Council Canada - National Science Library

    Hopmeier, Michael; Christen, Hank T; Malone, Michael V

    2005-01-01

    This report is the result of an effort to develop an understanding of fire fighter needs through an assessment of relevant research and fire fighter-related literature, forums, conferences, and symposia...

  20. Current trends towards a new regulation and evolution of fire protection systems technologies in nuclear power plants

    International Nuclear Information System (INIS)

    Rodriguez Sanjuan, G.

    1996-01-01

    For some time now, the field of Fire Protection in Nuclear Power Plants has, with its own peculiarities in an otherwise general process, been the centre of some controversy caused by tendencies to reduce regulatory inflexibility by transforming what was originally a prescriptive, pro grammatical and deterministic regulatory system into a system based on risk assessment and operating experience. Such tendencies include: Cost Beneficial Licensing Actions (CBLA) Use of the Probabilistic Safety Analysis (PSA) as a tool for evaluating the impact of postulated fires in nuclear safety Improvement of communications between the regulatory body and the industry These trends have coincided with the arduous process of requalifying passive fire-resistant protection materials, such as Thermo lag and others, which are used to separate redundant Safe Shutdown trains with fire-resistance ranges of one (1) hour or three (3) hours, in compliance with some of the alternatives that Appendix R to 10 CFR 50 offers. The process has involved a lot of effort and financial cost in requalification and in employing compensatory measures until operability of the fire-resistant materials is reestablished. A new test methodology has been created for these barriers (GL 86-10, Supplement 1) and new materials have become available and are currently undergoing qualification. (Author)

  1. 76 FR 70414 - National Fire Protection Association (NFPA) Proposes To Revise Codes and Standards

    Science.gov (United States)

    2011-11-14

    ... Commercial Cooking Operations. NFPA 99--2012 Health Care Facilities Code 6/22/2012 NFPA 99B--2010 Standard... Explosion Investigations..... 1/4/2012 NFPA 1005--2007 Standard for Professional Qualifications for 1/4/2012 Marine Fire Fighting for Land-Based Fire Fighters. NFPA 1021--2009 Standard for Fire Officer Professional...

  2. Updates of the fire protection system of the Juzbado Nuclear Fuel Fabrication Plant; Actualizaciones del Sistema de Proteccion Contra Incendios de la Fabrica de Combustible Nuclear de Juzbado

    Energy Technology Data Exchange (ETDEWEB)

    Dorado, P.; Palomo, J. J.; Romano, A.

    2015-07-01

    The Juzbado Nuclear Fuel Fabrication Plant fire protection system is one of the most important safety system of the plant. Every year, a large part of the annual investment is employed to improve this system, to update its technology, in order to improve detection and extinction capability to minimize fire risk. Over the last few years, several improvement projects have been carried out that focused on fire detection technology update and on optimization of local detectors integration with a centralized control system, as well as on an advanced public address system, which used clear and unambiguous messages improving personnel response to a plant evacuation. Planned projects and those, which are currently under development, focus on improving passive fire protection means as well as fire protection of key emergency response equipment s such as emergency diesel generators and fire extinguishing bombs. (Author)

  3. Mathematical Foundation Based Inter-Connectivity modelling of Thermal Image processing technique for Fire Protection

    Directory of Open Access Journals (Sweden)

    Sayantan Nath

    2015-09-01

    Full Text Available In this paper, integration between multiple functions of image processing and its statistical parameters for intelligent alarming series based fire detection system is presented. The proper inter-connectivity mapping between processing elements of imagery based on classification factor for temperature monitoring and multilevel intelligent alarm sequence is introduced by abstractive canonical approach. The flow of image processing components between core implementation of intelligent alarming system with temperature wise area segmentation as well as boundary detection technique is not yet fully explored in the present era of thermal imaging. In the light of analytical perspective of convolutive functionalism in thermal imaging, the abstract algebra based inter-mapping model between event-calculus supported DAGSVM classification for step-by-step generation of alarm series with gradual monitoring technique and segmentation of regions with its affected boundaries in thermographic image of coal with respect to temperature distinctions is discussed. The connectedness of the multifunctional operations of image processing based compatible fire protection system with proper monitoring sequence is presently investigated here. The mathematical models representing the relation between the temperature affected areas and its boundary in the obtained thermal image defined in partial derivative fashion is the core contribution of this study. The thermal image of coal sample is obtained in real-life scenario by self-assembled thermographic camera in this study. The amalgamation between area segmentation, boundary detection and alarm series are described in abstract algebra. The principal objective of this paper is to understand the dependency pattern and the principles of working of image processing components and structure an inter-connected modelling technique also for those components with the help of mathematical foundation.

  4. 75 FR 66725 - National Fire Protection Association (NFPA) Proposes To Revise Codes and Standards

    Science.gov (United States)

    2010-10-29

    ... for Solvent 5/23/2011 Extraction Plants. NFPA 51--2007 Standard for the Design and 11/23/2010... Practice for a 5/23/2011 Field Flame Test for Textiles and Films. NFPA 909--2010 Code for the Protection of...

  5. Preliminary report on fire protection research program (July 6, 1977 test)

    International Nuclear Information System (INIS)

    Klamerus, L.J.

    1977-10-01

    This preliminary report describes a fire test performed at Sandia Laboratories on an array of cable trays filled with fire retardant (IEEE 383 qualified) electrical cable. The cable trays were arranged in an open-space horizontal configuration with the separation distances of Regulatory Guide 1.75 between those trays representing redundant safety divisions. Propane burners were used to produce a fully developed cable fire in one tray which then was allowed to interact with other trays. From this test it appears that it is possible for a fire to propagate across the vertical separation distance between safety divisions, if a fully developed cable fire is the initiating event

  6. Fire-safety engineering and performance-based codes

    DEFF Research Database (Denmark)

    Sørensen, Lars Schiøtt

    project administrators, etc. The book deals with the following topics: • Historical presentation on the subject of fire • Legislation and building project administration • European fire standardization • Passive and active fire protection • Performance-based Codes • Fire-safety Engineering • Fundamental......Fire-safety Engineering is written as a textbook for Engineering students at universities and other institutions of higher education that teach in the area of fire. The book can also be used as a work of reference for consulting engineers, Building product manufacturers, contractors, building...... thermodynamics • Heat exchange during the fire process • Skin burns • Burning rate, energy release rate and design fires • Proposal to Risk-based design fires • Proposal to a Fire scale • Material ignition and flame spread • Fire dynamics in buildings • Combustion products and toxic gases • Smoke inhalation...

  7. Conceptual Design of the LHC Beam Dumping Protection Elements TCDS and TCDQ

    CERN Document Server

    Goddard, B; Sans-Merce, M; Weterings, W

    2004-01-01

    The Beam Dumping System for the Large Hadron Collider, presently under construction at CERN, consists, per ring, of a set of horizontally deflecting extraction kicker magnets, vertically deflecting steel septa, dilution kickers and finally, a couple of hundred metres further downstream, an absorber block. A fixed diluter (TCDS) will protect the septa in the event of a beam dump that is not synchronised with the particle free gap or a spontaneous firing of the extraction kickers which will cause the beam to sweep over the septum. Another, mobile, diluter block (TCDQ) will protect the superconducting quadrupole immediate downstream of the extraction as well as the arc at injection energy and the triplet aperture at top energy from bunches with small impact parameters. This paper describes the conceptual design of the protection elements.

  8. Different approaches of European regulations for fire design of steel structural elements

    DEFF Research Database (Denmark)

    Giuliani, Luisa; Budny, Iwona

    2010-01-01

    how both safety issues (avoid people injuries and preserve integrity of constructions) are addressed in the framework of European structural fire safety design of steel constructions. Some relevant differences can be found both in the procedures and in the philosophy of national and community...

  9. pipelines cathodic protection design methodologies for impressed

    African Journals Online (AJOL)

    HOD

    oil and gas pipelines corrosion in the United State of. American alone ... or preventing external corrosion of pipeline steels and other metallic .... 2.1 Materials and Impressed Current Design. Carbon steel ..... Research Analysis, Vol. 2, pp 2277 ...

  10. Safety design guide for pipe rupture 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 for pipe rupture protection identifies high-energy systems in which pipe ruptures must be postulated to occur, as well as systems that must be protected from the dynamic effects of such ruptures. Dynamic effects considered in this SDG consist of pipe whip (including missiles generated by pipe ruptures, if any) and jet impingement, Requirements for protection against the dynamic effects of a postulated pipe rupture and method of protection of essential structures, systems and components are specified for these effects. The change status for the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 2 tabs., 5 refs. (Author) .new

  11. Safe design of protective structures of tunnels

    International Nuclear Information System (INIS)

    Farahat, M.A.Z.

    2011-01-01

    This research aims to explain how to use a tunnel, constructed from reinforced concrete, passes under a river to protect some people. The computer code is used (MCNP) (the transfer photon and neutron) at this model for such tunnel which passes under a river to account attenuation of both neutrons and gamma rays passing through the river water, clay, soil and reinforced concrete wall layers ,the last one (thickness 40 cm)constructed the tunnel construction. And to account the dose inside the tunnel, and to account neutron dose, gamma dose, prompt gamma dose, total gamma dose and total (neutron + gamma) dose estimated by μSv/h. At different depths from the earth surface layer depths 100 cm, 250 cm, 500 cm, 750 cm , 1000 cm, 1300 cm, 1700 cm, 1900 cm, 2020 cm, 2500 cm). And then account these doses for three cases which are a nuclear bomb its intensity 20 kt, another bomb its intensity 100 kt, and the last one its intensity is 1000 kt. This research aims to account the required safe depth to protect some people in this tunnel, passing under a river from the dangerous effects of neutron and gamma rays, emitted from the nuclear bomb.

  12. Measuring the extent of overlaps in protected area designations.

    Science.gov (United States)

    Deguignet, Marine; Arnell, Andy; Juffe-Bignoli, Diego; Shi, Yichuan; Bingham, Heather; MacSharry, Brian; Kingston, Naomi

    2017-01-01

    Over the past decades, a number of national policies and international conventions have been implemented to promote the expansion of the world's protected area network, leading to a diversification of protected area strategies, types and designations. As a result, many areas are protected by more than one convention, legal instrument, or other effective means which may result in a lack of clarity around the governance and management regimes of particular locations. We assess the degree to which different designations overlap at global, regional and national levels to understand the extent of this phenomenon at different scales. We then compare the distribution and coverage of these multi-designated areas in the terrestrial and marine realms at the global level and among different regions, and we present the percentage of each county's protected area extent that is under more than one designation. Our findings show that almost a quarter of the world's protected area network is protected through more than one designation. In fact, we have documented up to eight overlapping designations. These overlaps in protected area designations occur in every region of the world, both in the terrestrial and marine realms, but are more common in the terrestrial realm and in some regions, notably Europe. In the terrestrial realm, the most common overlap is between one national and one international designation. In the marine realm, the most common overlap is between any two national designations. Multi-designations are therefore a widespread phenomenon but its implications are not well understood. This analysis identifies, for the first time, multi-designated areas across all designation types. This is a key step to understand how these areas are managed and governed to then move towards integrated and collaborative approaches that consider the different management and conservation objectives of each designation.

  13. Design and performance of a skid-mounted portable compartment fire gas furnace and monitoring system

    Directory of Open Access Journals (Sweden)

    Mueller K.

    2013-09-01

    Full Text Available A custom, portable natural gas fire furnace was designed and constructed for use at the University of Notre Dame to experimentally investigate the out-of-plane behavior of full-scale reinforced concrete (RC bearing walls under fire. The unique aspects of this furnace allowed the application of large mechanical loads and non-contact optical response monitoring to be done while subjecting the wall to elevated temperatures. The performance of the experimental furnace, mechanical loading, and response monitoring system is reported using the results from the first two RC wall test specimens.

  14. Thermal Spray Coatings for High-Temperature Corrosion Protection in Biomass Co-Fired Boilers

    Science.gov (United States)

    Oksa, M.; Metsäjoki, J.; Kärki, J.

    2015-01-01

    There are over 1000 biomass boilers and about 500 plants using waste as fuel in Europe, and the numbers are increasing. Many of them encounter serious problems with high-temperature corrosion due to detrimental elements such as chlorides, alkali metals, and heavy metals. By HVOF spraying, it is possible to produce very dense and well-adhered coatings, which can be applied for corrosion protection of heat exchanger surfaces in biomass and waste-to-energy power plant boilers. Four HVOF coatings and one arc sprayed coating were exposed to actual biomass co-fired boiler conditions in superheater area with a probe measurement installation for 5900 h at 550 and 750 °C. The coating materials were Ni-Cr, IN625, Fe-Cr-W-Nb-Mo, and Ni-Cr-Ti. CJS and DJ Hybrid spray guns were used for HVOF spraying to compare the corrosion resistance of Ni-Cr coating structures. Reference materials were ferritic steel T92 and nickel super alloy A263. The circulating fluidized bed boiler burnt a mixture of wood, peat and coal. The coatings showed excellent corrosion resistance at 550 °C compared to the ferritic steel. At higher temperature, NiCr sprayed with CJS had the best corrosion resistance. IN625 was consumed almost completely during the exposure at 750 °C.

  15. Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

    International Nuclear Information System (INIS)

    Klein, A.R.; Bloom, C.W.

    1989-07-01

    This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

  16. Design and evaluation of physical protection systems of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    An, Jin Soo; Lee, Hyun Chul; Hwang, In Koo; Kwack, Eun Ho; Choi, Yung Myung

    2001-06-01

    Nuclear material and safety equipment of nuclear facilities are required to be protected against any kind of theft or sabotage. Physical protection is one of the measures to prevent such illegally potential threats for public security. It should cover all the cases of use, storage, and transportation of nuclear material. A physical protection system of a facility consists of exterior intrusion sensors, interior intrusion sensors, an alarm assessment and communication system, entry control systems, access delay equipment, etc. The design of an effective physical protection system requires a comprehensive approach in which the designers define the objective of the system, establish an initial design, and evaluate the proposed design. The evaluation results are used to determine whether or not the initial design should be modified and improved. Some modelling techniques are commonly used to analyse and evaluate the performance of a physical protection system. Korea Atomic Energy Research Institute(KAERI) has developed a prototype of software as a part of a full computer model for effectiveness evaluation for physical protection systems. The input data elements for the prototype, contain the type of adversary, tactics, protection equipment, and the attributes of each protection component. This report contains the functional and structural requirements defined in the development of the evaluation computer model.

  17. A New Physical Protection System Design and Evaluation Process

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Heoksoon; Kim, Myungsu; Bae, Yeongkyoung; Na, Janghwan [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    International Atomic Energy Agency(IAEA) had established security-related department and has been strengthening security measures against possible sabotage. IAEA enforces the recommendations for the physical protection of NPPs in the INFCIRC/ 225/Rev.5 to the member states and U.S. NRC also enforces the similar requirements in 10 CFR 73.55. Thus, in order to let Korean NPPs meet the new requirements in INFCIRC/225/Rev.5 or U.S. NRC requirements, Korea nuclear licensee should develop or establish appropriate physical protection system (PPS) design methods for the physical protection of the operating NPPs and new NPPs. KHNP is doing the project of 'Development of APR1400 Physical Protection System Design (2012- 2015, KHNP/KAERI /KEPCO E-C)'. This paper describes overview of a physical protection system (PPS) design and evaluation for an advanced nuclear power plant. It found that a new physical protection system (PPS)design and evaluation. KHNP is doing the project of Physical Protection System design according to U.S. NRC requirements and IAEA requirements in INFCIRC /225 /Rev.5 and will complete by 7.31, 2015 for development of APR1400 Physical Protection System. After completing this project, the results of project are expected to apply new NPPs.

  18. Overview of internal fire hazards aspects of ABWR design for United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Kawai, Hiroki [Hitachi-GE Nuclear Energy, Ltd., Ibaraki (Japan)

    2015-12-15

    The ABWR (Advanced Boiling Water Reactor) is a generation III+ reactor, the most modern operational generation of nuclear power plants. The UK ABWR design is proposed for development and construction in the United Kingdom (UK), and under review by the Office for Nuclear Regulation (ONR) through Generic Design Assessment (GDA). The UK ABWR design has mainly two types of the safety system: ''preventing'' and ''mitigating'' a fault and their consequences. The prevention of internal hazards starts with design processes and procedures. These processes lead to limiting the sources of potential hazards. The mitigative safety systems are required to ensure the fundamental safety functions (FSFs): control of reactivity, Fuel cooling, long term heat removal, confinement/containment of radioactive materials, and others. Implementation of the safety philosophy is based upon redundant and diverse safety systems that deliver the FSFs. Three mechanical divisions are provided, each of which contains redundant systems, structures, and components (SSCs) capable of carrying out all the FSFs. The safety divisions are separated by robust barriers which act to contain a hazard in an affected division and prevent the spread of the hazard to a different division. The deterministic assessments and the hazard schedule argue that the rooms containing SSCs providing the FSFs are located in different fire safety divisions. The approach to maintaining the FSFs during and after internal fires is to ensure fires do not spread beyond that division to affect redundant equipment in other divisions. During the GDA process, it is demonstrated that generally barrier compartmentation (the divisional barrier walls, ceilings and floors) is sufficient to contain the postulated fires. The UK ABWR design has sufficient capability of withstanding the postulated internal fire hazard to achieve the FSFs. Further development is being undertaken with feedback in the GDA

  19. [Protecting Safety During Dust Fires and Dust Explosions - The Example of the Formosa Fun Coast Water Park Accident].

    Science.gov (United States)

    Hsieh, Ming-Hong; Wu, Jia-Wun; Li, Ya-Cing; Tang, Jia-Suei; Hsieh, Chun-Chien

    2016-02-01

    This paper will explore the fire and explosion characteristics of cornstarch powder as well as strategies for protecting the safety of people who are involved a dust fire or dust explosion. We discuss the 5 elements of dust explosions and conduct tests to analyze the fire and explosion characteristics of differently colored powders (yellow, golden yellow, pink, purple, orange and green). The results show that, while all of the tested powders were difficult to ignite, low moisture content was associated with significantly greater risks of ignition and flame spread. We found the auto-ignition temperature (AIT) of air-borne cornstarch powder to be between 385°C and 405°C, with yellow-colored cornstarch powder showing the highest AIT and pink-colored cornstarch powder showing the lowest AIT. The volume resistivity of all powder samples was approximately 108 Ω.m, indicating that they were nonconductive. Lighters and cigarettes are effective ignition sources, as their lit temperatures are higher than the AIT of cornstarch powder. In order to better protect the safety of individuals at venues where cornstarch powder is released, explosion control measures such as explosion containment facilities, vents, and explosion suppression and isolation devices should be installed. Furthermore, employees that work at these venues should be better trained in explosion prevention and control measures. We hope this article is a reminder to the public to recognize the fire and explosion characteristics of flammable powders as well as the preventive and control measures for dust explosions.

  20. Modeling the Pyrolysis and Combustion Behaviors of Non-Charring and Intumescent-Protected Polymers Using “FiresCone”

    Directory of Open Access Journals (Sweden)

    Long Shi

    2015-10-01

    Full Text Available A mathematical model, named FiresCone, was developed to simulate the pyrolysis and combustion processes of different types of combustible materials, which also took into account both gas and solid phases. In the present study, some non-charring and intumescent-protected polymer samples were investigated regarding their combustion behaviors in response to pre-determined external heat fluxes. The modeling results were validated against the experimental outcomes obtained from a cone calorimeter. The predicted mass loss rates of the samples were found to fit reasonably well with the experimental data collected under various levels of external irradiation. Both the experimental and modeling results showed that the peak mass loss rate of the non-charring polymer material occurred near the end of burning, whereas for the intumescent-protected polymer it happed shortly after the start of the experiment. “FiresCone” is expected to act as a practical tool for the investigation of fire behavior of combustible materials. It is also expected to model fire scenarios under complicated conditions.

  1. Radiation protection and shielding design - Strengthening the link

    International Nuclear Information System (INIS)

    Hobson, J.; Cooper, A.

    2005-01-01

    The improvement in quality and flexibility of shielding methods and data has been progressive and beneficial in opening up new opportunities for optimising radiation protection in design. The paper describes how these opportunities can best be seized by taking a holistic view of radiation protection, with shielding design being an important component part. This view is best achieved by enhancing the role of 'shielding assessors' so that they truly become 'radiation protection designers'. The increase in speed and efficiency of shielding calculations has been enormous over the past decades. This has raised the issue of how the assessor's time now can be best utilised; pursuing ever greater precision and accuracy in shielding/dose assessments, or improving the contribution that shielding assessment makes to radiological protection and cost-effective design. It is argued in this paper that the latter option is of great importance and will give considerable benefits. Shielding design needs to form part of a larger radiation protection perspective based on a deep understanding/appreciation of the opportunities and constraints of operators and designers, enabling minimal design iterations, cost optimisation of alternative designs (with a 'lifetime' perspective) and improved realisation of design intent in operations. The future of shielding design development is argued to be not in improving the 'tool-kit', but in enhanced understanding of the 'product' and the 'process' for achieving it. The holistic processes being developed in BNFL to realise these benefits are described in the paper and will be illustrated by case studies. (authors)

  2. Design of an actively cooled plate calorimeter for the investigation of pool fire heat fluxes

    International Nuclear Information System (INIS)

    Koski, J.A.; Keltner, N.R.; Nicolette, V.F.; Wix, S.D.

    1992-01-01

    For final qualification of shipping containers for transport of hazardous materials, thermal testing in accordance with regulations such as 10CFR71 must be completed. Such tests typically consist of 30 minute exposures with the container fully engulfed in flames from a large, open pool of JP4 jet engine fuel. Despite careful engineering analyses of the container, testing often reveals design problems that must be solved by modification and expensive retesting of the container. One source of this problem is the wide variation in surface heat flux to the container that occurs in pool fires. Average beat fluxes of 50 to 60 kW/m 2 are typical and close the values implied by the radiation model in 10CFR71, but peak fluxes up to 150 kW/m 2 are routinely observed in fires (Keltner, et al,1990). Heat fluxes in pool fires have been shown to be a function of surface temperature of the container, height above the pool, surface orientation, wind, and other variables. If local variations in the surface heat flux to the container can be better predicted, design analyses will become more accurate, and fewer problems will be uncovered during testing. The objective of the calorimeter design described in this paper is to measure accurately pool fire heat fluxes under controlled conditions, and to provide data for calibration of improved analytical models of local flame-surface interactions

  3. Design of an actively cooled plate calorimeter for the investigation of pool fire heat fluxes

    International Nuclear Information System (INIS)

    Koski, J.A.; Keltner, N.R.; Nicolette, V.F.; Wix, S.D.

    1992-01-01

    For final qualification of shipping containers for transport of hazardous materials, thermal testing in accordance with regulations such as 10CFR71 must be completed. Such tests typically consist of 30 minute exposures with the container fully engulfed in flames from a large, open pool of JP4 jet engine fuel. Despite careful engineering analyses of the container, testing often reveals design problems that must be solved by modification and expensive retesting of the container. One source of this problem is the wide variation in surface heat flux to the container that occurs in pool fires. Average heat fluxes of 50 to 60 kW/m 2 are typical and close the values implied by the radiation model in 10CFR71, but peak fluxes up to 150 kW/m 2 are routinely observed in fires. Heat fluxes in pool fires have been shown to be a function of surface temperature of the container, height above the pool, surface orientation, wind, and other variables. If local variations in the surface heat flux to the container could be better predicted, design analyses would become more accurate, and fewer problems will be uncovered during testing. The objective of the calorimeter design described in this paper is to measure accurately pool fire heat fluxes under controlled conditions, and to provide data for calibration of improved analytical models of local flame-surface interactions

  4. Design and analysis of the federal aviation administration next generation fire test burner

    Science.gov (United States)

    Ochs, Robert Ian

    The United States Federal Aviation Administration makes use of threat-based fire test methods for the certification of aircraft cabin materials to enhance the level of safety in the event of an in-flight or post-crash fire on a transport airplane. The global nature of the aviation industry results in these test methods being performed at hundreds of laboratories around the world; in some cases testing identical materials at multiple labs but yielding different results. Maintenance of this standard for an elevated level of safety requires that the test methods be as well defined as possible, necessitating a comprehensive understanding of critical test method parameters. The tests have evolved from simple Bunsen burner material tests to larger, more complicated apparatuses, requiring greater understanding of the device for proper application. The FAA specifies a modified home heating oil burner to simulate the effects of large, intense fires for testing of aircraft seat cushions, cargo compartment liners, power plant components, and thermal acoustic insulation. Recently, the FAA has developed a Next Generation (NexGen) Fire Test burner to replace the original oil burner that has become commercially unavailable. The NexGen burner design is based on the original oil burner but with more precise control of the air and fuel flow rates with the addition of a sonic nozzle and a pressurized fuel system. Knowledge of the fundamental flow properties created by various burner configurations is desired to develop an updated and standardized burner configuration for use around the world for aircraft materials fire testing and airplane certification. To that end, the NexGen fire test burner was analyzed with Particle Image Velocimetry (PIV) to resolve the non-reacting exit flow field and determine the influence of the configuration of burner components. The correlation between the measured flow fields and the standard burner performance metrics of flame temperature and

  5. Guide design study for the high-resolution backscattering spectrometer FIRES

    Energy Technology Data Exchange (ETDEWEB)

    Pelley, C; Kargl, F; Sakai, V Garcia; Telling, M T F; Fernandez-Alonso, F; Demmel, F, E-mail: franz.demmel@stfc.ac.uk

    2010-11-01

    Different options are considered to transport cold neutrons along 90 m for the proposed new spectrometer FIRES at the ISIS facility. Monte Carlo simulations using the McStas programme package are used to assess the performance of various guide designs from the biological shield to the sample position. By employing a curved geometry, to avoid the direct line of sight, a hybrid design which combines a curved ballistic guide and an elliptic focusing section appears to be the best solution.

  6. Radar Design to Protect Against Surprise

    Energy Technology Data Exchange (ETDEWEB)

    Doerry, Armin W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    Technological and doctrinal surprise is about rendering preparations for conflict as irrelevant or ineffective . For a sensor, this means essentially rendering the sensor as irrelevant or ineffective in its ability to help determine truth. Recovery from this sort of surprise is facilitated by flexibility in our own technology and doctrine. For a sensor, this mean s flexibility in its architecture, design, tactics, and the designing organizations ' processes. - 4 - Acknowledgements This report is the result of a n unfunded research and development activity . Sandia National Laboratories is a multi - program laboratory manage d and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE - AC04 - 94AL85000.

  7. Aircraft-crash-protected roof design for the European SBWR

    International Nuclear Information System (INIS)

    Posta, B.A.; Kadar, I.; Rao, A.S.

    1995-01-01

    The European utility requirement document (EURD) places significant emphasis on aircraft crash protection of the reactor building - Alternative concepts were evaluated for protecting the dry-well head and the fuel pool from the effect of the spalling concrete for the General Electric Company's European simplified boiling water reactor (ESBWR) designs

  8. Model assessment of protective barrier designs: Part 2

    International Nuclear Information System (INIS)

    Fayer, M.J.

    1987-11-01

    Protective barriers are being considered for use at the Hanford Site to enhance the isolation of radioactive wastes from water, plant, and animal intrusion. This study assesses the effectiveness of protective barriers for isolation of wastes from water. In this report, barrier designs are reviewed and several barrier modeling assumptions are tested. 20 refs., 16 figs., 6 tabs

  9. Risk reduction in road and rail LPG transportation bij passive fire protection

    NARCIS (Netherlands)

    Molag e.a., M. (Menso)

    2009-01-01

    The potential reduction of risk in LPG (Liquified Petroleum Gas) road transport due to the adoption of passive fire protectionswas investigated. Experimental data available for small scale vessels fully engulfed by a fire were extended to real scale road and rail tankers through a finite elements

  10. Technologies for Protection and Resistance Enhancement of Critical Infrastructures againstExtreme Fire

    Science.gov (United States)

    2014-05-01

    involving hydrocarbon fires, such as gasoline or crude oil carried in a tanker truck/train, or any other fuel fire of equivalent intensity. Examples of...and impact of weather exposure on the insulation, as well as possible health risk by inhalation (mainly concern for interior application), application

  11. Fire ants protect mealybugs against their natural enemies by utilizing the leaf shelters constructed by the leaf roller Sylepta derogata.

    Directory of Open Access Journals (Sweden)

    Aiming Zhou

    Full Text Available The importance of mutualism is receiving more attention in community ecology. In this study, the fire ant Solenopsis invicta was found to take advantage of the shelters constructed by the leaf roller Sylepta derogata to protect mealybugs (Phenacoccus solenopsis against their natural enemies. This protective effect of fire ant tending on the survival of mealybugs in shelters was observed when enemies and leaf rollers were simultaneously present. Specifically, fire ants moved the mealybugs inside the shelters produced by S. derogata on enemy-infested plants. Compared with that in plants without ants, the survival of mealybugs in shelters in the presence of natural enemies in plants with ants markedly improved. Both the protection of ants and the shelters provided by leaf rollers did not affect the survival of mealybugs in the absence of enemies in plants. Ants and leaf rollers significantly improved the survival of mealybugs in predator-infested plants, whereas no such improvement was observed in parasitoid-infested ones.

  12. Dual protection of wood surface treated with melamine-modified urea-formaldehyde resin mixed with ammonium polyphosphate against both fire and decay

    Science.gov (United States)

    Xing-xia Ma; Grant T. Kirker; Ming-liang Jiang; Yu-zhang Wu

    2016-01-01

    Surface coatings of melamine-modified urea-formaldehyde resins (MUFs) containing ammonium polyphosphate (APP) have been shown to significantly improve the fire retardancy of wood by prolonging the ignition time and reducing the heat release rate, total heat released, and mass loss rate. Dual protection of wood against both decay and fire has been proposed for remedial...

  13. Unites States position paper on sodium fires. Design basis and testing

    International Nuclear Information System (INIS)

    Lancet, R.T.; Johnson, R.P.; Matlin, E.; Vaughan, E.U.; Fields, D.E.; Glueckler, E.; McCormack, J.D.; Miller, C.W.; Pedersen, D.R.

    1989-01-01

    This paper focuses on designs, analyses, and tests performed since the last Sodium Fires Meeting of the IAEA International Working Group on Fast Reactors in May 1982. Since the U.S. Liquid Metal Reactor (LMR) program is focused on the two advanced LMRs, SAFR and PRISM, the paper relates this work to these designs. First, the design philosophy and approach taken by these advanced pool reactors are described. This includes methods of leak detection, the design basis leaks, and passive accommodation of sodium fires. Then the small- and large-scale sodium fire tests performed in support of the Clinch River Breeder Reactor Plant (CRBRP) program, including post-accident cleanup, are presented and related to the advanced LMR designs. Next, the assessment and behavior of the aerosols generated are discussed including generation rate, behavior within structures, release and dispersal, and deposition on safety-grade equipment. Finally, the impact of these aerosols on the performance of safety-grade decay heat removal heat exchange surfaces is discussed including some test results as well as planned tests. (author)

  14. Reactor protection system design using micro-computers

    International Nuclear Information System (INIS)

    Fairbrother, D.B.

    1976-01-01

    Reactor protection systems for nuclear power plants have traditionally been built using analog hardware. This hardware works quite well for single parameter trip functions; however, optimum protection against DNBR and KW/ft limits requires more complex trip functions than can easily be handled with analog hardware. For this reason, Babcock and Wilcox has introduced a Reactor Protection System, called the RPS-II, that utilizes a micro-computer to handle the more complex trip functions. The paper describes the design of the RPS-II and the operation of the micro-computer within the Reactor Protection System

  15. Reactor protection system design using micro-computers

    International Nuclear Information System (INIS)

    Fairbrother, D.B.

    1977-01-01

    Reactor Protection Systems for Nuclear Power Plants have traditionally been built using analog hardware. This hardware works quite well for single parameter trip functions; however, optimum protection against DNBR and KW/ft limits requires more complex trip functions than can easily be handled with analog hardware. For this reason, Babcock and Wilcox has introduced a Reactor Protection System, called the RPS-II, that utilizes a micro-computer to handle the more complex trip functions. This paper describes the design of the RPS-II and the operation of the micro-computer within the Reactor Protection System

  16. The radiation protection design of CSR

    Energy Technology Data Exchange (ETDEWEB)

    Su Youwu; Zheng Huazhi; Zhu Xiaolong; Li Shuwei [Institute of modern physics, the Chinese academy of Sciences, Lanzhou (China)

    2000-05-01

    The construction of CSR (Cooling Storage Ring) which include a main ring (CSRm) and an experimental ring (CSRe) will be started in this year. Heavy ions of carbon to uranium will be accelerated up to 900MeV/u and 400MeV/u at intensity of 10{sup 8} pps. For the shielding design of CSR, the secondary neutron yields due to ion beam loss and their spectra, angular distributions were estimated based on the experimental results for 400 MeV/u {sup 12}C+Cu reaction by K. Nakamura et.al.. The equivalent dose at the shield surface and in the surrounding environment, skyshine neutron dose equivalent and air-induced radioactivity were also estimated in this study. It is found that the most important environmental radiation impact component of CSR is the skyshine neutrons, and the environmental impact due to air and cooling water induced radioactivity were lesser. (author)

  17. The radiation protection design of CSR

    International Nuclear Information System (INIS)

    Su Youwu; Zheng Huazhi; Zhu Xiaolong; Li Shuwei

    2000-01-01

    The construction of CSR (Cooling Storage Ring) which include a main ring (CSRm) and an experimental ring (CSRe) will be started in this year. Heavy ions of carbon to uranium will be accelerated up to 900MeV/u and 400MeV/u at intensity of 10 8 pps. For the shielding design of CSR, the secondary neutron yields due to ion beam loss and their spectra, angular distributions were estimated based on the experimental results for 400 MeV/u 12 C+Cu reaction by K. Nakamura et.al.. The equivalent dose at the shield surface and in the surrounding environment, skyshine neutron dose equivalent and air-induced radioactivity were also estimated in this study. It is found that the most important environmental radiation impact component of CSR is the skyshine neutrons, and the environmental impact due to air and cooling water induced radioactivity were lesser. (author)

  18. Potential effects of the fire protection system sprays at Browns Ferry on fission product transport

    International Nuclear Information System (INIS)

    Niemczyk, S.J.

    1983-01-01

    The fire protection system (FPS) sprays within any nuclear plant are not intended to mitigate radioactive releases to the environment resulting from severe core-damage accidents. However, it has been shown here that during certain postulated severe accident scenarios at the Browns Ferry Nuclear Plant, the functioning of FPS sprays could have a significant impact on the radioactive releases. Thus the effects of those sprays need to be taken into account for realistic estimation of source terms for some accident scenarios. The effects would include direct ones such as cooling of the reactor building atmosphere and scrubbing of radioactivity from it, as well as indirect effects such as an altered likelihood of hydrogen burning and flooding of various safety-related pumps in the reactor building basement. Thus some of the impacts of the sprays would be beneficial with respect to mitigating releases to the environment but some others might not be. The effects of the FPS would be very scenario dependent with a wide range of potential effects often existing for a given accident sequence. Any generalization of the specific results presented here for Browns Ferry to other nuclear plants must be done cautiously, as it appears from a preliminary investigation that the relevant physical and operational characteristics of FPS spray systems differ widely among even otherwise apparently similar plants. Likewise the standby gas treatment systems, which substantially impact the effects of the FPS, differ significantly among plants. More work for both Mark I plants and other plants, BWRs and PWRs alike, is indicated so the potential effects of FPS spray systems during severe accidents can be at least ball-parked for more realistic accident analyses

  19. Monitoring of cloudiness in the function of the forests fire protection

    Directory of Open Access Journals (Sweden)

    Živanović Stanimir

    2016-01-01

    Full Text Available Fires in forests are seasonal in nature, conditioned by the moisture content of the fuel material. The emergence of these fires in Serbia is becoming more common and depending on the intensity and duration, fires have a major impact on the state of vegetation. The aim of this study was to determine the correlation between dynamics of cloudiness occurrence and forest fires. To study the correlation of these elements, Pearson correlation coefficients were used. The analysis is based on the meteorological data obtained from meteorological station Negotin for the period from 1991 to 2010. Among the tested influences, the degree of cloudiness showed positive correlative interdependence with the dynamics of fire occurrence in nature. The annual number of fires correlates positively with the average number of clear days (p = 0.25. Also, it was found that the annual number of fires with medium intensity, correlated negatively with the average number of cloudy days (p= -0.26, but not statistically significant (p> 0.05.

  20. Empirical Design of Scour Protections around Monopile Foundations

    DEFF Research Database (Denmark)

    De Vos, L.; De Rouck, J.; Troch, P.

    2012-01-01

    combined wave and current loading. In part 1 (De Vos et al., 2011), preceding this paper, a static design guideline for a scour protection around a monopile is suggested, based on a combined wave and current flow field. By allowing some movement of the top layer stones of the scour protection, a more...... economical design is obtained. This paper describes the derivation of a dynamic design formula to calculate the required stone size for a scour protection around a monopile foundation in a combined wave and current climate. The formula is based on the results of an experimental model study, described...... in this paper. The formula gives an expected damage level to the scour protection, based on the wave orbital velocity, wave period, steady current velocity, water depth, relative stone density and stone size. When applying the formula for a typical situation in the North Sea, a reduction of 20% to 80...

  1. 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.)

  2. A Survey of a System of Methods for Fire Safety Design of Traditional Concrete Constructions

    DEFF Research Database (Denmark)

    Hertz, Kristian

    2000-01-01

    constructions DS411. And the bases for many of the methods have been distributed by CIB W14 reports. But a survey of all the methods in coherence has never been presented, and much of this documentation and the additional documentation produced for the work with the codes needs still to be printed in papers......During the years since 1978 the author has been developing a series of calculation methods and sup-porting test methods for the fire safety design of concrete constructions. The basic methods have been adopted in the fire chapters of the Eurocode ENV1992-1-2 and the Danish code for concrete.......It is the aim of this paper to give a coherent presentation of the design methods, their degree of documentation and the available references in order to facilitate the application of them....

  3. Design aspects of radiation protection for nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

    This Safety Guide deals with the provisions to be made in the design of thermal neutron reactor power plants to protect site personnel and the public from undue exposure to ionizing radiation during operational states and accident conditions. The effective radiation protection is a combination of good design, high quality construction and proper operation. The document gives guidance on how to satisfy the objectives contained in Subsection 2.2 and Section 9 of the Code of Practice on Design for Safety of Nuclear Power Plants

  4. 46 CFR 28.330 - Galley hood and other fire protection equipment.

    Science.gov (United States)

    2010-10-01

    ... Stage of Construction on or After or Which Undergo a Major Conversion Completed on or After September 15... pre-engineered dry or wet chemical fire extinguishing system meeting the applicable sections of NFPA...

  5. Aircraft Carrier Flight and Hangar Deck Fire Protection: History and Current Status

    National Research Council Canada - National Science Library

    Darwin, Robert L; Bowman, Howard L; Hunstad, Mary; Leach, William B; Williams, Frederick W

    2005-01-01

    .... Next, a review of firefighting systems, including the firefighting agents currently in use, as well as the current tactics for fighting fires on the flight deck and the hangar deck, is provided...

  6. Fire and lightning: what are the risks and how to be protected?

    International Nuclear Information System (INIS)

    Rigal, F.

    2011-01-01

    This article reviews the risks of fire and lightning on photovoltaic panels installed on roofs. It appears that the risk of lighting must be taken into account since the direct impact of lightning on photovoltaic panels can be disastrous. The installation of lightning rods or lightning protector is recommended. Concerning fire risks, technical failures or the presence of electric arcs can put fire on solar panels but their occurrence is very low (only about 20 cases reported in Europe for the last 10 years). Tests have shown that standard photovoltaic panels play a low part in the progressing of a fire. There is an electrocution hazard for firemen intervening on a roof bearing solar panels. A device cutting the continuous current generating by the panels is being studied. (A.C.)

  7. Cathodic Protection Design Algorithms for Refineries Aboveground Storage Tanks

    Directory of Open Access Journals (Sweden)

    Kosay Abdul sattar Majbor

    2017-12-01

    Full Text Available Storage tanks condition and integrity is maintained by joint application of coating and cathodic protection. Iraq southern region rich in oil and petroleum product refineries need and use plenty of aboveground storage tanks. Iraq went through conflicts over the past thirty five years resulting in holding the oil industry infrastructure behind regarding maintenance and modernization. The primary concern in this work is the design and implementation of cathodic protection systems for the aboveground storage tanks farm in the oil industry. Storage tank external base area and tank internal surface area are to be protected against corrosion using impressed current and sacrificial anode cathodic protection systems. Interactive versatile computer programs are developed to provide the necessary system parameters data including the anode requirements, composition, rating, configuration, etc. Microsoft-Excel datasheet and Visual Basic.Net developed software were used throughout the study in the design of both cathodic protection systems. The case study considered in this work is the eleven aboveground storage tanks farm situated in al-Shauiba refinery in southern IRAQ. The designed cathodic protection systems are to be installed and monitored realistically in the near future. Both systems were designed for a life span of (15-30 years, and all their parameters were within the internationally accepted standards.

  8. Perspective pulse devices and automatic systems fire explosive protection of the radioactive infected objects

    International Nuclear Information System (INIS)

    Zakhmatov, V.D.; Kozhemyakin, A.S.; Pyatova, A.V.

    1999-01-01

    The suppression of fires in Chernobyl zone has shown complete unprofitable of traditional fire engineering to work on is radioactive of the infected district. In this connection as effective ways extinguishive in object 'Shelter' alongside with known traditional means and the systems offer to apply more perspective pulse systems, based on use energy small practically safe charges of gunpowder or explosive substances, in particular. Pulse explosive cone extinguishive of the device various sizes

  9. Design and testing of integrated circuits for reactor protection channels

    International Nuclear Information System (INIS)

    Battle, R.E.; Vandermolen, R.I.; Jagadish, U.; Swail, B.K.; Naser, J.

    1995-01-01

    Custom and semicustom application-specific integrated circuit design and testing methods are investigated for use in research and commercial nuclear reactor safety systems. The Electric Power Research Institute and Oak Ridge National Laboratory are working together through a cooperative research and development agreement to apply modern technology to a nuclear reactor protection system. The purpose of this project is to demonstrate to the nuclear industry an alternative approach for new or upgrade reactor protection and safety system signal processing and voting logic. Motivation for this project stems from (1) the difficulty of proving that software-based protection systems are adequately reliable, (2) the obsolescence of the original equipment, and (3) the improved performance of digital processing. A demonstration model for protection system of PWR reactor has been designed and built

  10. PLAY HANDS PROTECTIVE GLOVES: TECHNICAL NOTE ON DESIGN AND CONCEPT.

    Science.gov (United States)

    Houston-Hicks, Michele; Lura, Derek J; Highsmith, M Jason

    2016-09-01

    Cerebral Palsy (CP) is the leading cause of childhood motor disability, with a global incidence of 1.6 to 2.5/1,000 live births. Approximately 23% of children with CP are dependent upon assistive technologies. Some children with developmental disabilities have self-injurious behaviors such as finger biting but also have therapeutic needs. The purpose of this technical note is to describe design considerations for a protective glove and finger covering that maintains finger dexterity for children who exhibit finger and hand chewing (dermatophagia) and require therapeutic range of motion and may benefit from sensory stimulation resulting from constant contact between glove and skin. Protecting Little and Adolescent Youth (PLAY) Hands are protective gloves for children with developmental disorders such as CP who injure themselves by biting their hands due to pain or sensory issues. PLAY Hands will be cosmetically appealing gloves that provide therapeutic warmth, tactile sensory feedback, range of motion for donning/ doffing, and protection to maximize function and quality of life for families of children with developmental disorders. The technology is either a per-finger protective orthosis or an entire glove solution designed from durable 3D-printed biodegradable/bioabsorbable materials such as thermoplastics. PLAY Hands represent a series of protective hand wear interventions in the areas of self-mutilating behavior, kinematics, and sensation. They will be made available in a range of protective iterations from single- or multi-digit finger orthoses to a basic glove design to a more structurally robust and protective iteration. To improve the quality of life for patients and caregivers, they are conceptualized to be cosmetically appealing, protective, and therapeutic.

  11. Forest fires

    International Nuclear Information System (INIS)

    Fuller, M.

    1991-01-01

    This book examines the many complex and sensitive issues relating to wildland fires. Beginning with an overview of the fires of 1980s, the book discusses the implications of continued drought and considers the behavior of wildland fires, from ignition and spread to spotting and firestorms. Topics include the effects of weather, forest fuels, fire ecology, and the effects of fire on plants and animals. In addition, the book examines firefighting methods and equipment, including new minimum impact techniques and compressed air foam; prescribed burning; and steps that can be taken to protect individuals and human structures. A history of forest fire policies in the U.S. and a discussion of solutions to fire problems around the world completes the coverage. With one percent of the earth's surface burning every year in the last decade, this is a penetrating book on a subject of undeniable importance

  12. Empirical Design of Scour Protections around Monopile Foundations

    DEFF Research Database (Denmark)

    De Vos, L.; De Rouck, J.; Troch, P.

    2011-01-01

    in a current alone situation), at present, little design guidelines exist for the specific case of a scour protection around a monopile foundation subjected to a combined wave and current loading. This paper describes the derivation of a static design formula to calculate the required stone size for a scour......Together with new opportunities, offshore wind farms raise new engineering challenges. An important aspect relates to the erosion of bottom material around the foundation of the wind turbines, caused by the local increase of the wave and current induced flow velocities by the pile's presence....... Typically, the expected scour has a considerable impact on the stability and dynamic behavior of the wind turbine and a scour protection is placed to avoid erosion of the soil close to the foundation. Although much experience exists on the design of scour protections around bridge piers (which are placed...

  13. Recommendation of federal protected area designation for Sable Island

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-04-15

    A report by the Canada - Nova Scotia Sable Island Task Group (TG) and its partners recommends the appropriate federal protected area designation for Sable Island as being either that of a national wildlife area or of a national park, and includes objectives and a synopsis of the analyses of the designation options. It was found that both protected area designations are feasible and would ensure equivalent and comprehensive conservation of the ecology and wildlife on the Island, including the horses, but the TG's preferred recommendation is the designation of Sable Island as a National Park under the Canada National Parks Act. The next steps include consultations and a review of the issues identified during these consultations to facilitate the designation.

  14. Verification of fire and explosion accident analysis codes (facility design and preliminary results)

    International Nuclear Information System (INIS)

    Gregory, W.S.; Nichols, B.D.; Talbott, D.V.; Smith, P.R.; Fenton, D.L.

    1985-01-01

    For several years, the US Nuclear Regulatory Commission has sponsored the development of methods for improving capabilities to analyze the effects of postulated accidents in nuclear facilities; the accidents of interest are those that could occur during nuclear materials handling. At the Los Alamos National Laboratory, this program has resulted in three computer codes: FIRAC, EXPAC, and TORAC. These codes are designed to predict the effects of fires, explosions, and tornadoes in nuclear facilities. Particular emphasis is placed on the movement of airborne radioactive material through the gaseous effluent treatment system of a nuclear installation. The design, construction, and calibration of an experimental ventilation system to verify the fire and explosion accident analysis codes are described. The facility features a large industrial heater and several aerosol smoke generators that are used to simulate fires. Both injected thermal energy and aerosol mass can be controlled using this equipment. Explosions are simulated with H 2 /O 2 balloons and small explosive charges. Experimental measurements of temperature, energy, aerosol release rates, smoke concentration, and mass accumulation on HEPA filters can be made. Volumetric flow rate and differential pressures also are monitored. The initial experiments involve varying parameters such as thermal and aerosol rate and ventilation flow rate. FIRAC prediction results are presented. 10 figs

  15. CONCEPTUAL DESIGN ASSESSMENT FOR THE CO-FIRING OF BIO-REFINERY SUPPLIED LIGNIN PROJECT

    International Nuclear Information System (INIS)

    Ted Berglund; Jeffrey T. Ranney; Carol L. Babb; Jacqueline G. Broder

    2001-01-01

    The major aspects of this project are proceeding toward completion. Prior to this quarter, design criteria, tentative site selection, facility layout, and preliminary facility cost estimates have been completed and issued for review. Processing of bio-solids was completed, providing material for the pilot operations. Pilot facility design, equipment selection, and modification were completed during the fourth quarter of 2000. Initial pilot facility shakedown was completed during the fourth quarter. After some unavoidable delays, a suitable representative supply of municipal solid waste (MSW) feed material was procured. During this quarter (first quarter of 2001), shredding of the feed material was completed and final feed conditioning was completed. Pilot facility hydrolysis production was completed to produce lignin for co-fire testing. Pilot facility modifications continued to improve facility operations and performance during the first quarter of 2001. Samples of the co-fire fuel material were sent to the co-fire facility for evaluation. The TVA-Colbert facility has neared completion of the task to evaluate the co-location of the Masada facility on the operation of the power generation facility. The TVA-Colbert fossil plant is fully capable of providing a reliable steam supply. The preferred steam supply connection points and steam pipeline routing have been identified. The environmental review of the pipeline routing has been completed and no major impacts have been identified. Detailed assessment of steam export impacts on the Colbert boiler system have been completed and a cost estimate for steam supply system is being developed

  16. Conceptual designs of pressurized fluidized bed and pulverized coal fired power plants

    International Nuclear Information System (INIS)

    Doss, H.S.; Bezella, W.A.; Hamm, J.R.; Pietruszkiewicz, J.

    1984-01-01

    This paper presents the major technical and economic characteristics of steam and air-cooled pressurized fluidized bed (PFB) power plant concepts, along with the characteristics of a pulverized coal fired power plant equipped with an adipic acid enhanced wet-limestone flue gas desulfurization system. Conceptual designs for the three plants were prepared to satisfy a set of common groundrules developed for the study. Grassroots plants, located on a generic plant site were assumed. The designs incorporate technologies projected to be commercial in the 1990 time frame. Power outputs, heat rates, and costs are presented

  17. Architecture, design and protection of power distribution networks; Architecture, conception et protection des reseaux de distribution

    Energy Technology Data Exchange (ETDEWEB)

    Sorrel, J.P. [Schneider Electric SA, 92 - Boulogne-Billancourt (France)

    2000-10-01

    The design of all-electric ships calls for high power levels in the propulsion systems. Merchant ships and especially naval vessels demand rugged, reliable propulsion systems with high availability, low maintenance and ease of operation. These constraints imply the choice of an optimized single winding system. The design of the network topology and protection system, and the choice of operating voltage and HT neutral configuration are the main steps in the design. (author)

  18. Design of an actively cooled plate calorimeter for the investigation of pool fire heat fluxes

    International Nuclear Information System (INIS)

    Koski, J.A.; Keltner, N.R.; Nicolette, V.F.; Wix, S.D.

    1993-01-01

    In order to better measure local heat fluxes in open pool fires, an actively cooled calorimeter has been designed and analyzed. As this paper is being prepared, the calorimeter is in fabrication. Following fabrication, testing in a radiant heat facility is planned to assure proper performance before introduction into the pool fire environment. Initially, testing in the SMERF facility will assure reproducibility of tests by removing wind effects. As the program progresses, tests in open facilities, and with different geometries are anticipated. Experimental data from the initial tests will be compared continuously to the gray gas model, and as experiments proceed, the gray gas analytical model will be refined with the goal of improving finite element code analysis of shipping containers. (J.P.N.)

  19. Fire hazard analysis of the radioactive mixed waste trenchs

    International Nuclear Information System (INIS)

    McDonald, K.M.

    1995-01-01

    This Fire Hazards Analysis (FHA) is intended to assess comprehensively the risk from fire associated with the disposal of low level radioactive mixed waste in trenches within the lined landfills, provided by Project W-025, designated Trench 31 and 34 of the Burial Ground 218-W-5. Elements within the FHA make recommendations for minimizing risk to workers, the public, and the environment from fire during the course of the operation's activity. Transient flammables and combustibles present that support the operation's activity are considered and included in the analysis. The graded FHA contains the following elements: description of construction, protection of essential safety class equipment, fire protection features, description of fire hazards, life safety considerations, critical process equipment, high value property, damage potential--maximum credible fire loss (MCFL) and maximum possible fire loss (MPFL), fire department/brigade response, recovery potential, potential for a toxic, biological and/or radiation incident due to a fire, emergency planning, security considerations related to fire protection, natural hazards (earthquake, flood, wind) impact on fire safety, and exposure fire potential, including the potential for fire spread between fire areas. Recommendations for limiting risk are made in the text of this report and printed in bold type. All recommendations are repeated in a list in Section 18.0

  20. Learning fire-fighting lessons after Chernobyl

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Fire protection measures in Soviet nuclear power plants were set out in November 1987, in the Nuclear Power Plant Design Fire Protection Standards (VSN 01-87, USSR Ministry of Atomic Energy). The most important of these measures are. Avoiding as far as possible the use of combustible materials in plant structures and equipment. Dividing buildings and areas into suitable fire-fighting zones. Ensuring reliable fire protection of the control and safety systems. Protecting technical personnel from the dangers of a fire while they are performing essential accident-repair work and facilitating evacuation procedures (providing at least two evacuation routes and exits, anti-smoke protection of evacuation routes and control panel areas etc). Installing automatic fire-extinguishing and fire alarm systems. Providing various stationary facilities and equipment to assist the use of mobile fire-fighting appliances. In addition, a special fire-fighting division is being set up in every nuclear power plant while the first unit is still being constructed. These divisions work in close co-operation with the technical personnel management of the plant and with the bodies responsible for monitoring nuclear safety. (author)

  1. A Westinghouse designed distributed mircroprocessor based protection and control system

    International Nuclear Information System (INIS)

    Bruno, J.; Reid, J.B.

    1980-01-01

    For approximately five years, Westinghouse has been involved in the design and licensing of a distributed microprocessor based system for the protection and control of a pressurized water reactor nuclear steam supply system. A 'top-down' design methodology was used, in which the system global performance objectives were specified, followed by increasingly more detailed design specifications which ultimately decomposed the system into its basic hardware and software elements. The design process and design decisions were influenced by the recognition that the final product would have to be verified to ensure its capability to perform the safety-related functions of a class 1E protection system. The verification process mirrored the design process except that it was 'bottom-up' and thus started with the basic elements and worked upwards through the system in increasingly complex blocks. A number of areas which are of interest in a distributed system are disucssed, with emphasis on two systems. The first, the Integrated Protection System is primarily responsible for processing signals from field mounted sensors to provide for reactor trips and the initiation of the Engineered Safety Features. The Integrated Control System, which is organized in a parallel manner, processes other sensor signals and generates the necessary analog and on-off signals to maintain the plant parameters within specified limits. Points covered include system structure, systems partitioning strategies, communications techniques, software design concepts, reliability and maintainability, commercial component availability, interference susceptibility, licensing issues, and applicability. (LL)

  2. Protective design of critical infrastructure with high performance concretes

    International Nuclear Information System (INIS)

    Riedel, W.; Nöldgen, M.; Stolz, A.; Roller, C.

    2012-01-01

    Conclusions: High performance concrete constructions will allow innovative design solutions for critical infrastructures. Validation of engineering methods can reside on large and model scale experiments conducted on conventional concrete structures. New consistent impact experiments show extreme protection potential for UHPC. Modern FEM with concrete models and explicit rebar can model HPC and UHPC penetration resistance. SDOF and TDOF approaches are valuable design tools on local and global level. Combination of at least 2 out of 3 design methods FEM – XDOF- EXP allow reliable prediction and efficient innovative designs

  3. Fire fighting precautions at Bohunice Atomic Power Plants

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Some shortcomings are discussed of the project design of fire protection at the V-1 and V-2 nuclear power plants. The basic shortcoming of the system is insufficient division of the units for fire protection. Fire fighting measures are described for cable areas, switch houses and outside transformers, primary and secondary circuits and auxiliary units. Measures are presented for increasing fire safety in Jaslovske Bohunice proceedi.ng from experience gained with a fire which had occurred at a nuclear power plant in Armenia. (E.S.)

  4. Atmospheric electricity. [lightning protection criteria in spacecraft design

    Science.gov (United States)

    Daniels, G. E.

    1973-01-01

    Atmospheric electricity must be considered in the design, transportation, and operation of aerospace vehicles. The effect of the atmosphere as an insulator and conductor of high voltage electricity, at various atmospheric pressures, must also be considered. The vehicle can be protected as follows: (1) By insuring that all metallic sections are connected by electrical bonding so that the current flow from a lightning stroke is conducted over the skin without any gaps where sparking would occur or current would be carried inside; (2) by protecting buildings and other structures on the ground with a system of lightning rods and wires over the outside to carry the lightning stroke into the ground; (3) by providing a zone of protection for launch complexes; (4) by providing protection devices in critical circuits; (5) by using systems which have no single failure mode; and (6) by appropriate shielding of units sensitive to electromagnetic radiation.

  5. GRA prospectus: optimizing design and management of protected areas

    Science.gov (United States)

    Bernknopf, Richard; Halsing, David

    2001-01-01

    Protected areas comprise one major type of global conservation effort that has been in the form of parks, easements, or conservation concessions. Though protected areas are increasing in number and size throughout tropical ecosystems, there is no systematic method for optimally targeting specific local areas for protection, designing the protected area, and monitoring it, or for guiding follow-up actions to manage it or its surroundings over the long run. Without such a system, conservation projects often cost more than necessary and/or risk protecting ecosystems and biodiversity less efficiently than desired. Correcting these failures requires tools and strategies for improving the placement, design, and long-term management of protected areas. The objective of this project is to develop a set of spatially based analytical tools to improve the selection, design, and management of protected areas. In this project, several conservation concessions will be compared using an economic optimization technique. The forest land use portfolio model is an integrated assessment that measures investment in different land uses in a forest. The case studies of individual tropical ecosystems are developed as forest (land) use and preservation portfolios in a geographic information system (GIS). Conservation concessions involve a private organization purchasing development and resource access rights in a certain area and retiring them. Forests are put into conservation, and those people who would otherwise have benefited from extracting resources or selling the right to do so are compensated. Concessions are legal agreements wherein the exact amount and nature of the compensation result from a negotiated agreement between an agent of the conservation community and the local community. Funds are placed in a trust fund, and annual payments are made to local communities and regional/national governments. The payments are made pending third-party verification that the forest expanse

  6. CONCEPTUAL DESIGN ASSESSMENT FOR THE CO-FIRING OF BIO-REFINERY SUPPLIED LIGNIN PROJECT

    International Nuclear Information System (INIS)

    Ted Berglund; Jeffrey T. Ranney; Carol L. Babb; Jacqueline G. Broder

    2002-01-01

    The major aspects of this project are proceeding toward completion. Prior to this quarter, design criteria, tentative site selection, facility layout, and preliminary facility cost estimates were completed and issued. Processing of bio-solids was completed, providing material for the pilot operations. Pilot facility hydrolysis production has been completed to produce lignin for co-fire testing and the lignin fuel was washed and dewatered. Both the lignin and bio-solids fuel materials for co-fire testing were sent to the co-fire facility (EERC) for evaluation and co-firing. EERC has received coal typical of the fuel to the TVA-Colbert boilers. This material was used at EERC as baseline material and for mixing with the bio-fuel for combustion testing. All the combustion and fuel handling tests at EERC have been completed. During fuel preparation EERC reported no difficulties in fuel blending and handling. Preliminary co-fire test results indicate that the blending of lignin and bio-solids with the Colbert coal blend generally reduces NO(sub x) emissions, increases the reactivity of the coal, and increases the ash deposition rate on superheater surfaces. Deposits produced from the fuel blends, however, are more friable and hence easier to remove from tube surfaces relative to those produced from the baseline Colbert coal blend. The final co-fire testing report is being prepared at EERC and will be completed by the end of the second quarter of 2002. The TVA-Colbert facility has neared completion of the task to evaluate co-location of the Masada facility on the operation of the power generation facility. The TVA-Colbert fossil plant is fully capable of providing a reliable steam supply. The preferred steam supply connection points and steam pipeline routing have been identified. The environmental review of the pipeline routing has been completed and no major impacts have been identified. Detailed assessment of steam export impacts on the Colbert boiler system have been

  7. Designing concept on lightning protection of overhead power distribution line

    Energy Technology Data Exchange (ETDEWEB)

    Yokoyama, Shigeru [Central Research Institute of Electric Power Industry, Kanagawa-ken (Japan)], E-mail: yokoyama@criepi.denken.or.jp

    2007-07-01

    The principle is shown for lightning protection of power distribution lines taking the effects of surge arresters, overhead ground wires and their combined use into consideration. Moreover an outline of a rational design method targeting direct lightning hits, induced over voltages and back flow currents from high structures. (author)

  8. 75 FR 66735 - National Fire Protection Association (NFPA): Request for Comments on NFPA's Codes and Standards

    Science.gov (United States)

    2010-10-29

    ... 59A Standard for the P Production, Storage, and Handling of Liquefied Natural Gas (LNG). NFPA 75... Horizontally in Fire Resistance-Rated Floor Systems. NFPA 385 Standard for Tank P Vehicles for Flammable and Combustible Liquids. NFPA 497 Recommended Practice P for the Classification of Flammable Liquids, Gases, or...

  9. Fire test database

    International Nuclear Information System (INIS)

    Lee, J.A.

    1989-01-01

    This paper describes a project recently completed for EPRI by Impell. The purpose of the project was to develop a reference database of fire tests performed on non-typical fire rated assemblies. The database is designed for use by utility fire protection engineers to locate test reports for power plant fire rated assemblies. As utilities prepare to respond to Information Notice 88-04, the database will identify utilities, vendors or manufacturers who have specific fire test data. The database contains fire test report summaries for 729 tested configurations. For each summary, a contact is identified from whom a copy of the complete fire test report can be obtained. Five types of configurations are included: doors, dampers, seals, wraps and walls. The database is computerized. One version for IBM; one for Mac. Each database is accessed through user-friendly software which allows adding, deleting, browsing, etc. through the database. There are five major database files. One each for the five types of tested configurations. The contents of each provides significant information regarding the test method and the physical attributes of the tested configuration. 3 figs

  10. Measurements and simulation for design optimization for low NOx coal-firing system

    Energy Technology Data Exchange (ETDEWEB)

    E. Bar-Ziv; Y. Yasur; B. Chudnovsky; L. Levin; A. Talanker [Ben-Gurion University of Negev, Beer-Sheva (Israel)

    2003-07-01

    The information required to design a utility steam generator is the heat balance, fuel analysis and emission. These establish the furnace wall configuration, the heat release rates, and the firing technology. The furnace must be sized for (1) residence time for complete combustion with low NOx, and (2) reduction of flue gas temperature to minimize ash deposition. To meet these, computational fluid dynamics (CFD) of the combustion process in the furnace were performed and proven to be a powerful tool for this purpose. Still, reliable numerical simulations require careful interpretation and comparison with measurements. We report numerical results and measurements for a 575 MW pulverized coal tangential firing boiler of the Hadera power plant of Israel Electric Corporation (IEC). Measured and calculated values were found to be in reasonable agreement. We used the simulations for optimization and investigated temperature distribution, heat fluxes and concentration of chemical species. We optimized both the furnace flue gas temperature entering the convective path and the staged residence time for low NOx. We tested mass flow rates through close-coupled and separate overfire air ports and its arrangement and the coal powder fineness. These parameters can control the mixing rate between the fuel and the oxidizer streams and can affect the most important characteristics of the boiler such as temperature regimes, coal burning rate and nitrogen oxidation/reduction. From this effort, IEC started to improve the boiler performance by replacing the existing typical tangential burners to low NOx firing system to ensure the current regulation requirements of emission pollutions.

  11. Assessment of nitrogen oxide emission for designing boilers fired with coal dust

    Energy Technology Data Exchange (ETDEWEB)

    Kotler, V.R.; Gusev, L.N.; Babii, V.I.

    1983-09-01

    A method for forecasting emission of nitrogen oxides from steam boilers fired with coal is described. The method produces accurate results when nitrogen oxide emission from furnaces with straight-flow burners and turbulent-type burners fired with coal dusts is forecast. Oxides formed by decomposition of chemical compounds in coal (so-called 'fuel' nitrogen oxides) and nitrogen oxides formed by oxidation of molecular nitrogen by atomic oxygen (so-called 'thermal' nitrogen oxides) are evaluated. Zones in which the two types of nitrogen oxide are formed in flames are characterized. Factors which influence formation of nitrogen oxides in a furnace are evaluated: excess air, flue gas recirculation, design of a furnace and burners, movement of air and coal dust mixture in a furnace, temperature, methods for coal dust preparation, coal dust properties. Equations for forecasting emission of nitrogen oxides from furnaces are derived. Nomograms for easy calculation of emission are also given. Examples of using the method for forecasting emission of nitrogen oxides from furnaces fired with coal from the Kuzbass, the Donbass and Ehkibastuz are discussed. Comparisons of emission of nitrogen oxides calculated on the basis of the method and emission determined experimentally show that forecasting accuracy is high and errors do not exceed 10%. 5 references.

  12. Design concepts to enhance nuclear power plant protection

    International Nuclear Information System (INIS)

    Ericson, D.M. Jr.; Varnado, G.B.

    1980-01-01

    Using a modern design for a nuclear power plant as a point of departure, this study examines the enhancement of protection which may be achieved by changes to the design. These changes include concepts such as complete physical separation of redundant trains of safety equipment, hardened enclosures for water storage tanks, and hardened shutdown heat removal systems. The degree of enhancement (value) is examined in terms such as the potential reduction in the number of vital areas and the increase in probability of adversary sequence interruption. The impacts considered include constraints imposed upon operations and maintenance personnel and increased capital and operating costs. The study concludes that structural design changes alone do not provide significant increases in protection

  13. Operational and layup cycle protection of high-pressure fossil-fired utility boilers using an organic filming amine

    Energy Technology Data Exchange (ETDEWEB)

    Verib, George J. [FirstEnergy Corp., Akron, OH (United States)

    2012-06-15

    Economic conditions have caused many fossil-fired units to either drastically cycle load or shut down during low demand periods, where previously the units had been under a constant-load operation. The most current cycle chemistry guidelines employed are excellent in protecting the steam-water cycle during constant-load operation, but they have not minimized corrosion and provided protection of unit equipment during economic reserve off periods. Alternate methods of off-line protection and transient-load operation have been explored to minimize corrosion during these periods. The FirstEnergy Corp. has been using an alternate proprietary, organic filming amine to protect units during operation and short-term non-operational periods. Explored are the initial issues of high steam cation conductivity, use of the filming amine to protect the cycle during idle production periods, and the chemical amounts needed. The proprietary chemistry has shown the ability to successfully and significantly reduce corrosion throughout the steam-water cycle during transient-load situations and during non-operational periods while maintaining the chemistry guidelines of the industry and OEMs. (orig.)

  14. Equipment design for reliability testing of protection system

    International Nuclear Information System (INIS)

    Situmorang, Johnny; Tjahjono, H.; Santosa, A. Z.; Tjahjani, S.DT.; Ismu, P.H; Haryanto, D.; Mulyanto, D.; Kusmono, S

    1999-01-01

    The equipment for reliability testing of cable of protection system has been designed as a a furnace with the electric heater have a 4 kW power, and need time 10 minute to reach the designed maximum temperature 3000C. The dimension of furnace is 800 mm diameter and 2000 mm length is isolated use rockwool isolator and coated by aluminium. For the designed maximum temperature the surface temperature is 78 0c. Assemble of specimens is arranged horizontally in the furnace. The failure criteria will be defined based on the behaviour of the load circuit in each line of cable specimens

  15. Regulatory analysis for the resolution of generic issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment

    International Nuclear Information System (INIS)

    Woods, H.W.

    1993-10-01

    Actuation of Fire Protection Systems (FPS) in Nuclear Power Plants have resulted in adverse interactions with equipment important to safety. Precursor operational experience has shown that 37% of all FPS actuations damaged some equipment, and 20% of all FPS actuations have resulted in a plant transient and reactor trip. On an average 0.17 FPS actuations per reactor year have been experienced in nuclear power plants in this country. This report presents the regulatory analysis for GI-57, ''Effects of Fire Protection System Actuation on Safety-Related Equipment''. The risk reduction estimates, cost/benefit analyses, and other insights gained during this effort have shown that implementation of the recommendations contained in this report can significantly reduce risk, and that these improvements can be warranted in accordance with the backfit rule, 10 CFR 50.109(a)(3). However, plant specific analyses are required in order to identify such improvements. Generic analyses can not serve to identify improvements that could be warranted for individual, specific plants. Plant specific analyses of the type needed for this purpose are underway as part of the Individual Plant Examination of External Events (IPEEE) program

  16. Nitinol Embolic Protection Filters: Design Investigation by Finite Element Analysis

    Science.gov (United States)

    Conti, Michele; de Beule, Matthieu; Mortier, Peter; van Loo, Denis; Verdonck, Pascal; Vermassen, Frank; Segers, Patrick; Auricchio, Ferdinando; Verhegghe, Benedict

    2009-08-01

    The widespread acceptance of carotid artery stenting (CAS) to treat carotid artery stenosis and its effectiveness compared with surgical counterpart, carotid endarterectomy (CEA), is still a matter of debate. Transient or permanent neurological deficits may develop in patients undergoing CAS due to distal embolization or hemodynamic changes. Design, development, and usage of embolic protection devices (EPDs), such as embolic protection filters, appear to have a significant impact on the success of CAS. Unfortunately, some drawbacks, such as filtering failure, inability to cross tortuous high-grade stenoses, malpositioning and vessel injury, still remain and require design improvement. Currently, many different designs of such devices are available on the rapidly growing dedicated market. In spite of such a growing commercial interest, there is a significant need for design tools as well as for careful engineering investigations and design analyses of such nitinol devices. The present study aims to investigate the embolic protection filter design by finite element analysis. We first developed a parametrical computer-aided design model of an embolic filter based on micro-CT scans of the Angioguard™ XP (Cordis Endovascular, FL) EPD by means of the open source pyFormex software. Subsequently, we used the finite element method to simulate the deployment of the nitinol filter as it exits the delivery sheath. Comparison of the simulations with micro-CT images of the real device exiting the catheter showed excellent correspondence with our simulations. Finally, we evaluated circumferential basket-vessel wall apposition of a 4 mm size filter in a straight vessel of different sizes and shape. We conclude that the proposed methodology offers a useful tool to evaluate and to compare current or new designs of EPDs. Further simulations will investigate vessel wall apposition in a realistic tortuous anatomy.

  17. Design and testing of integrated circuits for reactor protection channels

    International Nuclear Information System (INIS)

    Battle, R.E.; Vandermolen, R.I.; Jagadish, U.; Swail, B.K.; Naser, J.; Rana, I.

    1995-01-01

    Custom and semicustom application-specific integrated circuit design and testing methods are investigated for use in research and commercial nuclear reactor safety systems. The Electric Power Research Institute and Oak Ridge National Laboratory are working together through a cooperative research and development agreement to apply modern technology to a nuclear reactor protection system. Purpose of this project is to demonstrate to the nuclear industry an alternative approach for new or upgrade reactor protection and safety system signal processing and voting logic. Motivation for this project stems from (1) the difficulty of proving that software-based protection systems are adequately reliable, (2) the obsolescence of the original equipment, and (3) the improved performance of digital processing

  18. 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

  19. Fires, ecological effects of

    Science.gov (United States)

    W. J. Bond; Robert Keane

    2017-01-01

    Fire is both a natural and anthropogenic disturbance influencing the distribution, structure, and functioning of terrestrial ecosystems around the world. Many plants and animals depend on fire for their continued existence. Others species, such as rainforest plants species, are extremely intolerant of burning and need protection from fire. The properties of a fire...

  20. Force Protection for Fire Fighters: Warm Zone Operations at Paramilitary Style Active Shooter Incidents in a Multi-Hazard Environment as a Fire Service Core Competency

    Science.gov (United States)

    2012-03-01

    Attacks,” Der Speigel, July 25, 2011, http://www.spiegel.de/international/europe/0,1518,776437,00.html 114 “Profile: Anders Behring Breivik ,” BBC...144 Patrick Donovan, “Puyallup Fire & Rescue’s Response to Active School Shooting Incident,” National Fire Academy (July 2008): 24, 26, 49...Learn Them.” Homeland Security Affairs Journal II, no. 2 (July 2006): 11. Donovan, Patrick . “Puyallup Fire & Rescue’s Response to Active School

  1. Maintenance of fire systems and equipment at Virginia Power

    International Nuclear Information System (INIS)

    Doubrely, E.B. Jr.

    1989-01-01

    The basics of fire protection systems maintenance are well codified and documented in the National Fire Codes published by the National Fire Protection Association. In addition, Insurers often promulgate minimum standards for fire protection systems design and maintenance to which they attach conditions of insurability. Regulatory agencies and even in-house corporate policies can impact the maintenance of fire protection systems and equipment. This presentation will focus on the various methods and alternate ways of performing system maintenance, whether required by code, insurer, or by some regulatory commitment at Virginia Powers North Anna and Surry nuclear power stations. The approach to performing similar work is handled differently at each station. This difference can be attributed to proximity to outside assistance as well as plant philosophy. In addition to station maintenance practices, a discussion of in-house servicing of portable fire suppression equipment is offered. 1 tab

  2. Crumple zone design for pedestrian protection using impact analysis

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Hyung Il; Jeon, Young Eun; Kim, Dae Young; Kim, Heon Young [Kangwon National Univ., Chuncheon si (Korea, Republic of); Kim, Yong Soo [Product Development Team, Gyeongsan si (Korea, Republic of)

    2012-08-15

    This paper describes the design process for an automobile crumple zone for pedestrian protection. The impact load and bending moments predicted by impact analysis were used to design a plastic structure that may help reduce pedestrian injuries to the thigh area. The fracture effect was incorporated into the model by calculating the damage to the plastic material during impact, and the analysis was conducted under the European New Car Assessment Program (Euro NCAP) test conditions, using the upper legform developed by ESI Corporation. In addition, the values predicted by the analysis were validated by comparison with results of actual impact tests.

  3. Respiratory protective device design using control system techniques

    Science.gov (United States)

    Burgess, W. A.; Yankovich, D.

    1972-01-01

    The feasibility of a control system analysis approach to provide a design base for respiratory protective devices is considered. A system design approach requires that all functions and components of the system be mathematically identified in a model of the RPD. The mathematical notations describe the operation of the components as closely as possible. The individual component mathematical descriptions are then combined to describe the complete RPD. Finally, analysis of the mathematical notation by control system theory is used to derive compensating component values that force the system to operate in a stable and predictable manner.

  4. Crumple zone design for pedestrian protection using impact analysis

    International Nuclear Information System (INIS)

    Moon, Hyung Il; Jeon, Young Eun; Kim, Dae Young; Kim, Heon Young; Kim, Yong Soo

    2012-01-01

    This paper describes the design process for an automobile crumple zone for pedestrian protection. The impact load and bending moments predicted by impact analysis were used to design a plastic structure that may help reduce pedestrian injuries to the thigh area. The fracture effect was incorporated into the model by calculating the damage to the plastic material during impact, and the analysis was conducted under the European New Car Assessment Program (Euro NCAP) test conditions, using the upper legform developed by ESI Corporation. In addition, the values predicted by the analysis were validated by comparison with results of actual impact tests

  5. FAULT-TOLERANT DESIGN FOR ADVANCED DIVERSE PROTECTION SYSTEM

    Directory of Open Access Journals (Sweden)

    YANG GYUN OH

    2013-11-01

    Full Text Available For the improvement of APR1400 Diverse Protection System (DPS design, the Advanced DPS (ADPS has recently been developed to enhance the fault tolerance capability of the system. Major fault masking features of the ADPS compared with the APR1400 DPS are the changes to the channel configuration and reactor trip actuation equipment. To minimize the fault occurrences within the ADPS, and to mitigate the consequences of common-cause failures (CCF within the safety I&C systems, several fault avoidance design features have been applied in the ADPS. The fault avoidance design features include the changes to the system software classification, communication methods, equipment platform, MMI equipment, etc. In addition, the fault detection, location, containment, and recovery processes have been incorporated in the ADPS design. Therefore, it is expected that the ADPS can provide an enhanced fault tolerance capability against the possible faults within the system and its input/output equipment, and the CCF of safety systems.

  6. 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

  7. 77 FR 58081 - Protection of Stratospheric Ozone: Listing of Substitutes for Ozone-Depleting Substances-Fire...

    Science.gov (United States)

    2012-09-19

    ... 332919 Nozzles, fire fighting, manufacturing. Manufacturing 334290 Fire detection and alarm systems... substitutes for halon 1301 for use in total flooding fire suppression systems in normally unoccupied spaces... regulated Category NAICS Code entities Construction 238210 Alarm system (e.g., fire, burglar), electric...

  8. Design And Development Of An Automatic Single Phase Protective Device Using Ssr

    Directory of Open Access Journals (Sweden)

    Michael E.

    2017-10-01

    Full Text Available Since the discovery of energy safety has been a paramount subject matter. This we can see in todays electrical systems where protective devices such as fuse and circuit breakers are used to prevent fire hazards resulting from overload overvoltage and short circuits. However with all the revolution in technology these options may be considered less smart since the fuse made with wire strands calculated for specific current capacity faults permanently when the specified current rating is exceeded. While the circuit breaker which is made up of mechanical switch fails as a result of carbon forming and the wearing away of the contacts because of arcing. As a means of improvement this paper presents the design and development of an automatic single phase protective device using solid state relay SSR. This study is to ensure automatic cut off from power supply in cases of overvoltage above 240 V AC or when overload and short circuit current above 8amps is detected without permanent damage of a fuse placed along current path. Also the design will ensure that there is an automatic close circuit whenever the trigger switch is momentary switch is closed. The system is achieved via the use of PIC micro-controller current sensor and other discrete components. The system is tested and works well inhibiting the frequent faulting of fuses. It also helps to prevent hazard as a result of overvoltage overload and short circuit and ensures a close circuit when the trigger switch is closed.

  9. Environment protection by coupling of a municipal waste incinerator to an existing coal fire steam boiler

    Energy Technology Data Exchange (ETDEWEB)

    Ionel, I.; Stanescu, P.D.O.; Gruescu, C.; Savu, A.; Ungureanu, C. [University of Politehnic Timisoara, Timisoara (Romania)

    2006-12-15

    The paper offers an analysis of the potential coupling of a municipal waste incinerator in Romania, to an existing coal fired steam boiler. Considering the retention of heavy metals as well as HCl from the waste flue gases before entering the boiler, the simulation analysis of the boiler, under the situation that the gases from the scrubber are introduced, are presented As general conclusion one notes that it is possible to apply the concept even if the analysed case is of less importance, but more potential application are viewed for larger industrial application, for new concepts of modern power plants, to meet EU environmental regulations, especially for CO{sub 2} reduction.

  10. Extension and update of the reliability data for fire protection equipment in German light water reactors; Ergaenzung und Aktualisierung von Zuverlaessigkeitskenngroessen fuer Brandschutzeinrichtungen in deutschen Leichtwasserreaktoren

    Energy Technology Data Exchange (ETDEWEB)

    Forell, Burkhard; Einarsson, Svante

    2016-12-15

    Within the BMUB project 3610R01370 ''Extension and update of reliability data for fire protection equipment in German light water reactors'' plant-specific as well as generic failure rates for the technical reliability of active fire protection features in German nuclear power plants have been calculated. Based on results of previous projects, in this project observation times of components were updated and extended and additional components and functions were assessed. Now, the data evaluated results from a total of six German reference plants with seven reactor units.

  11. Effects of alpha-zirconium phosphate on thermal degradation and flame retardancy of transparent intumescent fire protective coating

    Energy Technology Data Exchange (ETDEWEB)

    Xing, Weiyi [State Key Laboratory of Fire Science, University of Science and Technology of China, 96 Jinzai Road, Hefei, Anhui 230026 (China); Zhang, Ping [State Key Laboratory Cultivation Base for Nonmetal Composites and Functional Materials, Southwest University of Science and Technology, 59 Qinglong Road, Mianyang 621010 (China); Song, Lei; Wang, Xin [State Key Laboratory of Fire Science, University of Science and Technology of China, 96 Jinzai Road, Hefei, Anhui 230026 (China); Hu, Yuan, E-mail: yuanhu@ustc.edu.cn [State Key Laboratory of Fire Science, University of Science and Technology of China, 96 Jinzai Road, Hefei, Anhui 230026 (China)

    2014-01-01

    Graphical abstract: - Highlights: • A transparent intumescent fire protective coating was obtained by UV-cured technology. • OZrP could enhance the thermal stability and anti-oxidation of the coating. • OZrP could reduce the combustion properties of the coatings. - Abstract: Organophilic alpha-zirconium phosphate (OZrP) was used to improve the thermal and fire retardant behaviors of the phenyl di(acryloyloxyethyl)phosphate (PDHA)-triglycidyl isocyanurate acrylate (TGICA)-2-phenoxyethyl acrylate (PHEA) (PDHA-TGICA-PHEA) coating. The morphology of nanocomposite coating was characterized by X-ray diffraction (XRD) and transmission electron microscopy (TEM). The effect of OZrP on the flame retardancy, thermal stability, fireproofing time and char formation of the coatings was investigated by microscale combustion calorimeter (MCC), thermogravimetric analysis (TGA), X-ray photoelectron spectroscopy (XPS), laser Raman spectroscopy (LRS) and scanning electric microscope (SEM). The results showed that by adding OZrP, the peak heat release rate and total heat of combustion were significantly reduced. The highest improvement was achieved with 0.5 wt% OZrP. XPS analysis indicated that the performance of anti-oxidation of the coating was improved with the addition of OZrP, and SEM images showed that a good synergistic effect was obtained through a ceramic-like layer produced by OZrP covered on the surface of char.

  12. Effects of alpha-zirconium phosphate on thermal degradation and flame retardancy of transparent intumescent fire protective coating

    International Nuclear Information System (INIS)

    Xing, Weiyi; Zhang, Ping; Song, Lei; Wang, Xin; Hu, Yuan

    2014-01-01

    Graphical abstract: - Highlights: • A transparent intumescent fire protective coating was obtained by UV-cured technology. • OZrP could enhance the thermal stability and anti-oxidation of the coating. • OZrP could reduce the combustion properties of the coatings. - Abstract: Organophilic alpha-zirconium phosphate (OZrP) was used to improve the thermal and fire retardant behaviors of the phenyl di(acryloyloxyethyl)phosphate (PDHA)-triglycidyl isocyanurate acrylate (TGICA)-2-phenoxyethyl acrylate (PHEA) (PDHA-TGICA-PHEA) coating. The morphology of nanocomposite coating was characterized by X-ray diffraction (XRD) and transmission electron microscopy (TEM). The effect of OZrP on the flame retardancy, thermal stability, fireproofing time and char formation of the coatings was investigated by microscale combustion calorimeter (MCC), thermogravimetric analysis (TGA), X-ray photoelectron spectroscopy (XPS), laser Raman spectroscopy (LRS) and scanning electric microscope (SEM). The results showed that by adding OZrP, the peak heat release rate and total heat of combustion were significantly reduced. The highest improvement was achieved with 0.5 wt% OZrP. XPS analysis indicated that the performance of anti-oxidation of the coating was improved with the addition of OZrP, and SEM images showed that a good synergistic effect was obtained through a ceramic-like layer produced by OZrP covered on the surface of char

  13. A Framework for Assessment of Intentional Fires

    Directory of Open Access Journals (Sweden)

    Iraj Mohammadfam

    2014-04-01

    Full Text Available Background & Objectives : It is not possible to live without using fire. However, fire could destruct human properties in a short time. One of the most important types of fire is intentional fire. This type of fire has become a great problem for insurance companies, fire departments, industries, government and business in the recent years. This study aimed to provide a framework for risk assessment of intentional fires . Methods: In the present study, risk assessment and management model for protecting critical properties and security vulnerability assessment model were used to develop a comprehensive framework for risk assessment of intentional fires. The framework was examined in an automotive industry . Results : The designed framework contained five steps as 1 asset inventory and prioritizing them according to their importance, 2 invasion assessment, 3 vulnerability assessment, 4 risk assessment and design and 5 implementation and evaluating the effectiveness of corrective/preventive actions. Thirty different scenarios for intentional fires were identified by implementing the designed framework in an automotive company, and then the associated risk of each scenario was quantitatively determined. Conclusion : Compared to seven models, the proposed framework represents its comprehension. Development of safety and security standards and a central security information bank to reduce security risks, including the risk of intentional fires is recommended .

  14. 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 ...

  15. Dependable Design Flow for Protection Systems using Programmable Logic Devices

    CERN Document Server

    Kwiatkowski, M

    2011-01-01

    Programmable Logic Devices (PLD) such as Field Programmable Gate Arrays (FPGA) are becoming more prevalent in protection and safety-related electronic systems. When employing such programmable logic devices, extra care and attention needs to be taken. The final synthesis result, used to generate the bit-stream to program the device, must be shown to meet the design’s requirements. This paper describes how to maximize confidence using techniques such as Formal Methods, exhaustive Hardware Description Language (HDL) code simulation and hardware testing. An example is given for one of the critical functions of the Safe Machine Parameters (SMP) system, used in the protection of the Large Hadron Collider (LHC) at CERN. CERN is also working towards an adaptation of the IEC- 61508 lifecycle designed for Machine Protection Systems (MPS), and the High Energy Physics environment, implementation of a protection function in FPGA code is only one small step of this lifecycle. The ultimate aim of this project is to cre...

  16. Designing and Maintaining a Communication Consulting Relationship: A Fire Officer Case Study

    Science.gov (United States)

    Cragan, John F.

    2008-01-01

    This case study describes a 35-year communication consulting relationship with the Illinois Fire Chiefs' Association. This case explains the fire chiefs' educational problems, the five-step method for creating an educational curriculum for fire officers, and the five-step procedure for continuous evaluation of the curriculum. Finally, an…

  17. U.S. position paper on sodium fires, design and testing

    International Nuclear Information System (INIS)

    Hilliard, R.K.; Johnson, R.P.; Powers, D.A.

    1982-05-01

    Sodium combustion phenomena and U.S. computer codes developed for sodium fires are discussed. Ways of preventing and mitigating sodium fires are described. Effects of sodium fires and spills on LMFBR structural materials, thermal insulation materials, and equipment/instrumentation are considered

  18. Optimizing Organophosphorus Fire Resistant Finish for Cotton Fabric Using Box-Behnken Design

    International Nuclear Information System (INIS)

    Sohail, Y.; Parag, B.; Nemeshwaree, B.; Giorgio, R.

    2016-01-01

    N-methylol dimethyl phosphono propionamide (MDPA) is one of the most utilized fire resistant (FR) finishes for cotton fabrics, utilized as part of a formulation with trimethylol melamine (TMM) to acquire better crosslinking and enhanced FR properties. The system parameters of the finishing treatment were upgraded for better FR properties and low mechanical loss to the fabric by the response surface methodology utilizing Box-Behnken statistical designed experimental strategy. The impacts of concentration on the cotton fabric’s properties (fire resistance and mechanical properties) were assessed with the regression equations. The optimum conditions by predicting the FR reagents focusing intact mechanical properties of the fabric were additionally studied. It was found that the parameters of crosslinking agents in the FR formulation have a prime role in the general FR properties of the cotton fabrics. The R-squared estimations of the considerable number of responses were above 92%, demonstrating the level of relationship between the predicted values by the Box-Behnken frameworks and the real test results.

  19. Improved Design of Unequal Error Protection LDPC Codes

    Directory of Open Access Journals (Sweden)

    Sandberg Sara

    2010-01-01

    Full Text Available We propose an improved method for designing unequal error protection (UEP low-density parity-check (LDPC codes. The method is based on density evolution. The degree distribution with the best UEP properties is found, under the constraint that the threshold should not exceed the threshold of a non-UEP code plus some threshold offset. For different codeword lengths and different construction algorithms, we search for good threshold offsets for the UEP code design. The choice of the threshold offset is based on the average a posteriori variable node mutual information. Simulations reveal the counter intuitive result that the short-to-medium length codes designed with a suitable threshold offset all outperform the corresponding non-UEP codes in terms of average bit-error rate. The proposed codes are also compared to other UEP-LDPC codes found in the literature.

  20. Protective clothing[Occupational safety of personnel in the event of a sodium fire

    Energy Technology Data Exchange (ETDEWEB)

    Malet, J C; Regnier, J [DSN/SESTR, Centre de Cadarache, Saint-Paul-lez-Durance (France)

    1979-03-01

    The present operational and intervention suits are described. Research work is currently in progress to improve the performance of the existing suits and to develop more resistant protective clothing. (author)

  1. Game theoretic analysis of physical protection system design

    International Nuclear Information System (INIS)

    Canion, B.; Schneider, E.; Bickel, E.; Hadlock, C.; Morton, D.

    2013-01-01

    The physical protection system (PPS) of a fictional small modular reactor (SMR) facility have been modeled as a platform for a game theoretic approach to security decision analysis. To demonstrate the game theoretic approach, a rational adversary with complete knowledge of the facility has been modeled attempting a sabotage attack. The adversary adjusts his decisions in response to investments made by the defender to enhance the security measures. This can lead to a conservative physical protection system design. Since defender upgrades were limited by a budget, cost benefit analysis may be conducted upon security upgrades. One approach to cost benefit analysis is the efficient frontier, which depicts the reduction in expected consequence per incremental increase in the security budget

  2. Fire preparedness measures in buildings with hot laboratories

    International Nuclear Information System (INIS)

    Oberlaender, B.C.

    2003-01-01

    Important hot laboratory safety issues are the general design/construction of the building with respect to fire, fire prevention, fire protection, administrative controls, and risk assessment. Within the network of the European Working Group Hot Laboratories and Remote Handling items concerning 'fire preparedness measures in hot laboratories' were screened and studied. Two questionnaires were sent to European hot laboratories; the first in November 2002 on 'fire preparedness measures, fire detection and fire suppression/extinguishing in lead shielded cells, concrete shielded cells' and the second in June 2003 on 'Fire preparedness measures in buildings with hot laboratories'. The questionnaires were filled in by a total of ten hot laboratories in seven European countries. On request of participants the answers were evaluated and 'anonymised' for presentation and discussion at the plenary meeting. The answers showed that many European hot laboratories are implementing improvements to their fire protection programmes to comply with more stringent requirements of the national authorities. The recommendations ('International guidelines for the fire protection of Nuclear Power Plants') given by the insurance pools are followed up with national variations. An ISO standard (ISO 17873) is in progress giving criteria for the design and the operation of ventilation systems as well as fire hazard management in nuclear installations others than reactors

  3. 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

  4. Spatial-temporal distribution of fire-protected savanna physiognomies in Southeastern Brazil

    Directory of Open Access Journals (Sweden)

    Marcelo H.O. Pinheiro

    2010-06-01

    Full Text Available The analysis of the influence of edaphic finer textures, as a facilitating factor for the expansion of forest formations in the absence of fire, was possible thanks to rare characteristics found in a savanna fragment located in the State of São Paulo, Brazil. The total suppression of fire for over four decades, and the occurrence of two savanna physiognomies, cerrado sensu stricto and cerradão, allowed the conduction of this study based on the hypothesis that cerradão, a physiognomy of forest aspect consisting of fire-sensitive tree and shrubs species, is favored by fire absence and higher soil hydric retention capacity. Edaphic samples were collected from a regular grid of 200 m² for the production of isopletic maps of the distribution of clay, fine sand, coarse sand and silt edaphic textures by the geostatistic method of ordinary kriging. Changes in the areas occupied by both savanna physiognomies, defined on the basis of aerial photographs taken over a period of 43 years, were assessed through mean variation rates. Besides corroborating the hypothesis of edaphic hydric retention as a facilitating factor for the expansion of forest physiognomies in savanna areas, we were able to infer the positive influence of higher precipitation on the increase in cerradão expansion rates.A influência de texturas edáficas finas, como fator de facilitação para a expansão de formações florestais sobre áreas savânicas, através da maior retenção hídrica edáfica, na ausência de incêndios, foi possível ser estudada graças às características encontradas em um fragmento savânico com 38,8 ha, situado em Corumbataí (SP. A supressão total do fogo por quatro décadas, e a ocorrência de duas fisionomias, cerrado sensu stricto e cerradão, permitiram a condução deste estudo. Amostras de solo foram coletadas em uma grade regular de 200 m², abrangendo toda a área do fragmento. Foram produzidos mapas iso-pléticos, com a distribuição das

  5. Review of the IAEA fire symposium

    International Nuclear Information System (INIS)

    Fischer, J.

    1991-01-01

    The IAEA Symposium on Fire Protection and Fire Fighting in Nuclear Installations covered a large scope in the field in order to provide the opportunity for screening all aspects of present technology, research and development, standardization, licensing and fire fighting practices. Although application to any nuclear facility was within its scope, the majority of presentations concerned nuclear power plants. The approach to fire protection is the classical one in all plant designs: reduction of fire loads, appropriate zoning, manual and automatic extinguishment. However, methods of analysis and consequence prediction are changing. Computerized fire modelling is becoming a powerful tool in this area; probabilistic analytical methods are being improved, though they are not yet used widely for fire hazards. Differences in opinion were revealed in the definition of barrier resistance, the prediction of cable insulation behaviour and the optimal design of extinguishing systems. Greater international co-operation, especially in these areas, may be a good way of optimizing results with limited resources. Discussion contributions showed interest in exchange of experience in more specialized topics and encouraged the IAEA to increase its activity in the area of fire protection. (orig.)

  6. System 80+{trademark} standard design incorporates radiation protection lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Crom, T.D.; Naugle, C.L. [Duke Engineering & Services, Inc., Charlotte, NC (United States); Turk, R.S. [ABB Combustion Engineering Nuclear Power, Windsor, CT (United States)

    1995-03-01

    Many lessons have been learned from the current generation of nuclear plants in the area of radiation protection. The following paper will outline how the lessons learned have been incorporated into the design and operational philosophy of the System 80+{trademark} Standard Design currently under development by ABB Combustion Engineering (ABB-CE) with support from Duke Engineering and Services, Inc. and Stone and Webster Engineering Corporation in the Balance-of-Plant design. The System 80+{trademark} Standard Design is a complete nuclear power plant for national and international markets, designed in direct response to utility needs for the 1990`s, and scheduled for Nuclear Regulatory Commission (NRC) Design Certification under the new standardization rule (10 CFR Part 52). System 80+{trademark} is a natural extension of System 80{sup R} technology, an evolutionary change based on proven Nuclear Steam Supply System (NSSS) in operation at Palo Verde in Arizona and under construction at Yonggwang in the Republic of Korea. The System 80+{trademark} Containment and much of the Balance of Plant design is based upon Duke Power Company`s Cherokee Plant, which was partially constructed in the late 1970`s, but, was later canceled (due to rapid declined in electrical load growth). The System 80+{trademark} Standard Design meets the requirements given in the Electric Power Research Institute (EPRI) Advanced Light Water Reactor (ALWR) Requirements Document. One of these requirements is to limit the occupational exposure to 100 person-rem/yr. This paper illustrates how this goal can be achieved through the incorporation of lessons learned, innovative design, and the implementation of a common sense approach to operation and maintenances practices.

  7. Hazardous air pollutant emissions from gas-fired combustion sources: emissions and the effects of design and fuel type

    Energy Technology Data Exchange (ETDEWEB)

    England, G.C.; McGrath, T.P. [GE-Energy and Environmental Research Corp., Irvine, CA (United States); Gilmer, L. [Equilon Enterprises, Bellaire, TX (United States); Seebold, J.G. [Chevron Research and Technology Co., Richmond, CA (United States); Lev-On, M. [ARCO, Los Angeles, CA (United States); Hunt, T. [American Petroleum Institute, Washington, DC (United States)

    2001-07-01

    Air emissions from gas-fired combustion devices such as boilers, process heaters, gas turbines and stationary reciprocating engines contain hazardous air pollutants (HAPs) subjected to consideration under the federal clean air act (CAA). This work presents a recently completed major research project to develop an understanding of HAP emissions from gas-fired boilers and process heaters and new HAP emission factors based on field emission tests of gas-fired external combustion devices used in the petroleum industry. The effect of combustion system design and operating parameters on HAP emissions determined by both field and research tests are discussed. Data from field tests of gas-fired petroleum industry boilers and heaters generally show very low emission levels of organic HAPs. A comparison of the emission data for boilers and process heaters, including units with and without various forms of NO{sub x} emission controls, showed no significant difference in organic HAP emission characteristics due to process or burner design. This conclusion is also supported by the results of research tests with different burner designs. Based on field tests of units fired with natural gas and various petroleum industry process gases and research tests in which gas composition was intentionally varied, organic HAP emissions were not determined to be significantly affected by the gas composition. Research data indicate that elevated organic HAP emission levels are found only under extreme operating conditions (starved air or high excess air combustion) associated with poor combustion. (author)

  8. Hazardous air pollutant emissions from gas-fired combustion sources: emissions and the effects of design and fuel type

    International Nuclear Information System (INIS)

    England, G.C.; McGrath, T.P.; Gilmer, L.; Seebold, J.G.; Lev-On, M.; Hunt, T.

    2001-01-01

    Air emissions from gas-fired combustion devices such as boilers, process heaters, gas turbines and stationary reciprocating engines contain hazardous air pollutants (HAPs) subjected to consideration under the federal clean air act (CAA). This work presents a recently completed major research project to develop an understanding of HAP emissions from gas-fired boilers and process heaters and new HAP emission factors based on field emission tests of gas-fired external combustion devices used in the petroleum industry. The effect of combustion system design and operating parameters on HAP emissions determined by both field and research tests are discussed. Data from field tests of gas-fired petroleum industry boilers and heaters generally show very low emission levels of organic HAPs. A comparison of the emission data for boilers and process heaters, including units with and without various forms of NO x emission controls, showed no significant difference in organic HAP emission characteristics due to process or burner design. This conclusion is also supported by the results of research tests with different burner designs. Based on field tests of units fired with natural gas and various petroleum industry process gases and research tests in which gas composition was intentionally varied, organic HAP emissions were not determined to be significantly affected by the gas composition. Research data indicate that elevated organic HAP emission levels are found only under extreme operating conditions (starved air or high excess air combustion) associated with poor combustion. (author)

  9. Industry participation in the development of a risk-informed, performance-based regulation for fire protection at US nuclear power plants

    International Nuclear Information System (INIS)

    Emerson, F.A.

    1998-01-01

    The USNRC staff have recently been directed by the NRC Commissioners to evaluate quickly the development of a risk-informed, performance-based fire protection regulation to replace the current regulations. The US nuclear industry does not believe a new rule is necessary to increase fire safety, and believes that there are significant risks and potentially significant benefits depending on the construction of the rule. However, the industry will actively work with NRC staff if rulemaking proceeds such that the risks are minimized and the benefits maximized. A Nuclear Energy Institute (NEI) Issue Task Force (ITF) has been established to guide the participation of industry in any rulemaking activity. If rulemaking proceeds, a framework should be established for the evolution of a fire protection rule from the current prescriptive basis to a risk-informed, performance-based rule. (author)

  10. Building 431 fire tests

    International Nuclear Information System (INIS)

    Alvares, N.J.; Beason, D.G.; Ford, H.W.; Magee, M.W.

    1977-01-01

    An extensive discussion of considerations for fire protection in the LLL mirror fusion test facility (MFTF) is presented. Because of the large volume and high bays of the building, sufficient data on fire detection is unavailable. Results of fire detection tests using controlled fire sources in the building are presented. Extensive data concerning the behavior of the building atmosphere are included. Candidate fire detection instrumentation and extinguishing systems for use in the building are briefly reviewed

  11. Reactor protection system design using application specific integrated circuits

    International Nuclear Information System (INIS)

    Battle, R.E.; Bryan, W.L.; Kisner, R.A.; Wilson, T.L. Jr.

    1992-01-01

    Implementing reactor protection systems (RPS) or other engineering safeguard systems with application specific integrated circuits (ASICs) offers significant advantages over conventional analog or software based RPSs. Conventional analog RPSs suffer from setpoints drifts and large numbers of discrete analog electronics, hardware logic, and relays which reduce reliability because of the large number of potential failures of components or interconnections. To resolve problems associated with conventional discrete RPSs and proposed software based RPS systems, a hybrid analog and digital RPS system implemented with custom ASICs is proposed. The actual design of the ASIC RPS resembles a software based RPS but the programmable software portion of each channel is implemented in a fixed digital logic design including any input variable computations. Set point drifts are zero as in proposed software systems, but the verification and validation of the computations is made easier since the computational logic an be exhaustively tested. The functionality is assured fixed because there can be no future changes to the ASIC without redesign and fabrication. Subtle error conditions caused by out of order evaluation or time dependent evaluation of system variables against protection criteria are eliminated by implementing all evaluation computations in parallel for simultaneous results. On- chip redundancy within each RPS channel and continuous self-testing of all channels provided enhanced assurance that a particular channel is available and faults are identified as soon as possible for corrective actions. The use of highly integrated ASICs to implement channel electronics rather than the use of discrete electronics greatly reduces the total number of components and interconnections in the RPS to further increase system reliability. A prototype ASIC RPS channel design and the design environment used for ASIC RPS systems design is discussed

  12. Design of an experiment to measure fire exposure of packages aboard container cargo ships

    International Nuclear Information System (INIS)

    Koski, J.A.

    1998-01-01

    The test described in this paper is intended to measure the typical accident environment for a radioactive materials package in a fire abroad a container cargo ship. A stack of nice used standard cargo containers will be variously loaded with empty packages, simulated packages and combustible cargo and placed over a large hydrocarbon pool fire of one hour duration. Fire environments, both inside and outside the containers, typical of on-deck stowage will be measured as well as the potential for container-to-container fire spread. With the use of the inverse heat conduction calculations, the local heat transfer to the simulated packages can be estimated from thermocouple data. Data recorded will also provide information on fire durations in each container, fire intensity and container-to-container fire spread characteristics. (authors)

  13. Development of fire PRA methodologies for the analysis of typical Italian NPP designs

    International Nuclear Information System (INIS)

    Silvestri, E.; Dore, B.; Ferro, G.; Apostolakis, G.

    1987-01-01

    To compute fire induced Core Melt probability, the results of hazard and propagation analyses were combined with the Core Melt frequency computed for the initiating event and the support state as determined by the fire considered. From the PRA for internal event, the average value of this frequency was found 2.5x10 -3 event/year. Using the average fire frequency the resulting fire induced Core Melt frequency is 1.4x10 -8 event/year. Although high separation of safety systems is required in Italian PWR plants, the frequency of fire induced Core Melt can reach values not negligible with respect to Italian safety standards. For this reason, fire PRA studies for the entire plant are considered necessary and should be performed with appropriate modifications of the methods used for the American plants in order to be able to estimate lower fire induced Core Melt frequencies. (orig./HP)

  14. Assessment of the Fire Risk Levels in an Office Building and a Nightclub with Prescriptive Designs

    DEFF Research Database (Denmark)

    Yilmaz, D.; Steffensen, F.B.; Jomaas, Grunde

    2014-01-01

    A comparison of the risk level of an office building and a nightclub with code compliant prescriptive designs was conducted in order to evaluate whether an uniform safety level of the two occupancy types can be established. A risk assessment method using Monte Carlo simulations and 1- and 2-zone......-movement time and the movement time were adjusted for the required safe egress time (RSET) of the nightclub. The number of simulations required in order to obtain reliable results was considered sufficient at 20,000. The comparison of the risk profiles of the nightclub and the office building showed significant...... difference in risk levels, with that of the nightclub being substantially higher. The higher risk level in the nightclub is caused by a relatively fast mean value of the fire growth rate and the high number of occupants. Hence, the requirements in the prescriptive code do not ensure a similar safety level...

  15. Thermodynamic analysis and conceptual design for partial coal gasification air preheating coal-fired combined cycle

    Science.gov (United States)

    Xu, Yue; Wu, Yining; Deng, Shimin; Wei, Shirang

    2004-02-01

    The partial coal gasification air pre-heating coal-fired combined cycle (PGACC) is a cleaning coal power system, which integrates the coal gasification technology, circulating fluidized bed technology, and combined cycle technology. It has high efficiency and simple construction, and is a new selection of the cleaning coal power systems. A thermodynamic analysis of the PGACC is carried out. The effects of coal gasifying rate, pre-heating air temperature, and coal gas temperature on the performances of the power system are studied. In order to repower the power plant rated 100 MW by using the PGACC, a conceptual design is suggested. The computational results show that the PGACC is feasible for modernizing the old steam power plants and building the new cleaning power plants.

  16. Improving disaster risk reduction capacity of District Civil Protection Units in managing veld fires: A case of Mangwe District in Matabeleland South Province, Zimbabwe

    Directory of Open Access Journals (Sweden)

    Ernest Dube

    2015-05-01

    Full Text Available This article analysed disaster risk reduction capacity of District Civil Protection Units (DCPUs in managing veld fires in Mangwe District of Matabeleland South Province, Zimbabwe. Veld fires have resulted in unnecessary material, environmental and economic losses. Communities’ livelihoods and property have been destroyed, and the natural environment depleted. The research sought to improve disaster risk reduction capacity of DCPUs in managing veld fires, through new intervention strategies and a new model. The objectives of the study were to investigate the main causes of veld fires; to analyse their impacts; to examine the effectiveness of the current intervention strategies; and to identify challenges in implementing these interventions. Furthermore, the study sought to recommend new possible intervention strategies. This mainly qualitative study employed self-administered questionnaires, interviews and focus-group discussions. Questionnaires were used to investigate members of the DCPU’s ideas, views and experiences, interviews solicited perceptions of community leaders and their subjects, whilst focus-group discussions assisted with information from members of the District Civil Protection Planning Committee. Veld fires in the district are mainly caused by human activities, and they are prevalent during the months of September and October. They affect livelihoods and the natural environment the most. This study found that DCPUs are not prepared to manage veld fires and therefore recommended new strategies and adoption of the community-based disaster risk reduction model. The new strategies include involving community leaders and members of the communities in DCPUs; regular training and workshops to members of DCPUs on veld fire management; creation of fire protection associations; regular campaigns and rehearsal of emergency drills by the DCPU personnel; the introduction of competitions and incentives in veld fire management; vigorous

  17. THE CONCEPTUAL DESIGN ASSESSMENT FOR THE CO-FIRING OF BIO-REFINERY SUPPLIED LIGNIN PROJECT

    International Nuclear Information System (INIS)

    Ted Berglund; Jeffrey T. Ranney; Carol L. Babb; Jacqueline G. Broder

    2001-01-01

    The major aspects of this project are proceeding toward completion. Prior to this quarter, design criteria, tentative site selection, facility layout, and preliminary facility cost estimates were completed and issued. Processing of bio-solids was completed, providing material for the pilot operations. Pilot facility design, equipment selection, and modification were completed during the fourth quarter of 2000. Initial pilot facility shakedown was completed during the fourth quarter. After some unavoidable delays, a suitable representative supply of MSW feed material was procured. During this first quarter of 2001, shredding of the feed material and final feed conditioning were completed. Pilot facility hydrolysis production was completed to produce lignin for co-fire testing. During this quarter, TVA completed the washing and dewatering of the lignin material produced from the MSW hydrolysis. Seven drums of lignin material were washed to recover the acid and sugar from the lignin and provide an improved fuel for steam generation. Samples of both the lignin and bio-solids fuel materials for co-fire testing were sent to the co-fire facility (EERC) for evaluation. After sample evaluation, EERC approved sending the material and all of the necessary fuel for testing was shipped to EERC. EERC has requested and will receive coal typical of the fuel to the TVA-Colbert boilers. This material will be used at EERC as baseline material and for mixing with the bio-fuel for combustion testing. EERC combustion testing of the bio based fuels is scheduled to begin in August of 2001. The TVA-Colbert facility has neared completion of the task to evaluate the co-location of the Masada facility on the operation of the power generation facility. The TVA-Colbert fossil plant is fully capable of providing a reliable steam supply. The preferred steam supply connection points and steam pipeline routing have been identified. The environmental review of the pipeline routing has been completed

  18. The burning behaviour of sodium and consequences to be drawn for fire protection measures, by the example of the Kalkar nuclear power plant

    International Nuclear Information System (INIS)

    Hoppe, E.

    1977-01-01

    The burning behaviour of sodium leakages is described. The specific protective measures to be derived from the burning behaviour is discussed using the example of the Kalkar nuclear power station, where sodium is used as a coolant. A basic boundary condition to be considered in the system of protective measures against Na fires is the activity confinement in case of a release of radioactive sodium. (orig.) [de

  19. Fire simulation of pool fire with effects of a ventilation controlled compartment by using a fire model, CFAST

    International Nuclear Information System (INIS)

    Hattori, Yasuo; Suto, Hitoshi; Shirai, Koji; Eguchi, Yuzuru; Matsuyama, Ken

    2015-01-01

    The basic performance for numerical analysis of fire parameters in a compartment by using a zone model, CFAST (Consolidated model of Fire growth And Smoke Transport), which has been widely applied for fire protection design of buildings, was examined. Special attentions were paid to the effects of compartment geometry under poor ventilation conditions with mechanical systems. The simulations were carried out under conditions corresponding to previous experiments, in which fire parameters have been precisely measured. The comparison between numerical simulations and experiments indicated that the CFAST principally has a capability to represent the time-histories of air-temperature in the high air-temperature layer generated in the vicinity of ceiling of the compartment, by applying the proper boundary conditions. These results suggest that numerical analysis for time-series of air temperature and smoke concentration in compartments must be a powerful tool for discussion on validity of fire protection schemes. (author)

  20. Examples of radiation protection optimization in design and operation

    International Nuclear Information System (INIS)

    Gonzalez, A.J.; Palacios, E.; Curti, A.; Agatiello, O.; Majchrzak, J.

    1982-01-01

    The practical use of the requirement of optimization of radiological protection is presented. Application examples for designing ventilation systems and for maintenance operations of nuclear plants are given. A method is developed for the application of the optimization requirement to the design of ventilation systems in contaminated environments. Representative values of the main parameters are presented and their relevant features are discussed. A practical example shows actual results for a radioisotope production plant. Causes influencing collective doses incurred by the workers during maintenance operations are analyzed. A method is presented for the optimization of both the level of training of personnel and the apportionment of individual doses. As an example, this methodology is applied to the maintenance operations in a nuclear power plant. (author)

  1. Preliminary design of the thermal protection system for solar probe

    Science.gov (United States)

    Dirling, R. B., Jr.; Loomis, W. C.; Heightland, C. N.

    1982-01-01

    A preliminary design of the thermal protection system for the NASA Solar Probe spacecraft is presented. As presently conceived, the spacecraft will be launched by the Space Shuttle on a Jovian swing-by trajectory and at perihelion approach to three solar radii of the surface of the Earth's sun. The system design satisfies maximum envelope, structural integrity, equipotential, and mass loss/contamination requirements by employing lightweight carbon-carbon emissive shields. The primary shield is a thin shell, 15.5-deg half-angle cone which absorbs direct solar flux at up to 10-deg off-nadir spacecraft pointing angles. Secondary shields of sandwich construction and low thickness-direction thermal conductivity are used to reduce the primary shield infrared radiation to the spacecraft payload.

  2. Mitigation of fire damage and escalation by fireproofing: A risk-based strategy

    International Nuclear Information System (INIS)

    Tugnoli, Alessandro; Cozzani, Valerio; Di Padova, Annamaria; Barbaresi, Tiziana; Tallone, Fabrizio

    2012-01-01

    Passive fire protection by the application of fireproofing materials is a crucial safety barrier in the prevention of the escalation of fire scenarios. Fireproofing improves the capacity of process items and of support structures to maintain their structural integrity during a fire, preventing or at least delaying the collapse of structural elements. Maintenance and cost issues require, however, to apply such protection only where an actual risk of severe fire scenarios is present. Available methodologies for fireproofing application in on-shore installation do not consider the effect of jet-fires. In the present study, a risk-based methodology aimed at the protection from both pool fire and jet fire escalation was developed. The procedure addresses both the prevention of domino effect and the mitigation of asset damage due to the primary fire scenario. The method is mainly oriented to early design application, allowing the identification of fireproofing zones in the initial phases of lay-out definition.

  3. Fire performance of multi-storey wooden facades

    Directory of Open Access Journals (Sweden)

    Östman Birgit A.-L.

    2013-11-01

    Full Text Available Two series of full scale fire tests of wooden facades according to the Swedish test SP Fire 105 are presented, one series for different shares of untreated wood (partial wood and structural fire protection with a fire shield above the window and another series for fire retardant treated, FRT, wood. The results are compared with data from the Single Burning Item test and the cone calorimeter. For FRT wood, the need for verification of the weather durability of the treatment is stressed and a new European technical specification CEN/TS 15912 presented. The need to use fire stops behind multi-storey façade claddings to avoid fire spread in the cavities is underlined and the possibilities of fire safety design with sprinklers is briefly presented.

  4. 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)

  5. Failsafe design criteria for computer based reactor protection systems

    International Nuclear Information System (INIS)

    Keats, A.B.

    1980-01-01

    The design criteria proposed are an extrapolation of the failsafe mode of operation used in the UK in hardwired reactor protection systems. This is achieved by making the operational condition of the reactor dependent upon an energetic state of the protection system components. An important objective of the proposed design criteria is to eliminate, or at least to minimize, the need for a failure-mode-and-effect-analysis (FMEA) of the computer software. This demands some well defined but simple constraints upon the way in which data are stored in the computers, but the objective is achieved almost entirely by hardware properties of the system. The first of these is the systematic use of hardwired test inputs which cause transient excursions into the tripped state in a uniquely ordered but easily recognizable sequence. The second is the use of hardwired pattern recognition logic which generates a dynamic healthy stimulus for the shutdown actuators only in response to the unique sequence formed by the hardwired input signal pattern. It therefore detects abnormal states of any of the system inputs, software errors, wiring errors and hardware failures. This hardwired logic is conceptually simple, failsafe, and is amenable to simple FMEA. (U.K.)

  6. Spatial optimization of operationally relevant large fire confine and point protection strategies: Model development and test cases

    Science.gov (United States)

    Yu Wei; Matthew P. Thompson; Jessica R. Haas; Gregory K. Dillon; Christopher D. O’Connor

    2018-01-01

    This study introduces a large fire containment strategy that builds upon recent advances in spatial fire planning, notably the concept of potential wildland fire operation delineations (PODs). Multiple PODs can be clustered together to form a “box” that is referred as the “response POD” (or rPOD). Fire lines would be built along the boundary of an rPOD to contain a...

  7. Iron aluminide weld overlay coatings for boiler tube protection in coal-fired low NOx boilers

    Energy Technology Data Exchange (ETDEWEB)

    Banovic, S.W.; DuPont, J.N.; Marder, A.R. [Lehigh Univ., Bethlehem, PA (United States). Energy Research Center

    1997-12-01

    Iron aluminide weld overlay coatings are currently being considered for enhanced sulfidation resistance in coal-fired low NO{sub x} boilers. The use of these materials is currently limited due to hydrogen cracking susceptibility, which generally increases with an increase in aluminum concentration of the deposit. The overall objective of this program is to attain an optimum aluminum content with good weldability and improved sulfidation resistance with respect to conventional materials presently in use. Research has been initiated using Gas Tungsten Arc Welding (GTAW) in order to achieve this end. Under different sets of GTAW parameters (wire feed speed, current), both single and multiple pass overlays were produced. Characterization of all weldments was conducted using light optical microscopy, scanning electron microscopy, and electron probe microanalysis. Resultant deposits exhibited a wide range of aluminum contents (5--43 wt%). It was found that the GTAW overlays with aluminum contents above {approximately}10 wt% resulted in cracked coatings. Preliminary corrosion experiments of 5 to 10 wt% Al cast alloys in relatively simple H{sub 2}/H{sub 2}S gas mixtures exhibited corrosion rates lower than 304 stainless steel.

  8. Exploiting heat treatment effects on SMAs macro and microscopic properties in developing fire protection devices

    Science.gov (United States)

    Burlacu, L.; Cimpoeşu, N.; Bujoreanu, L. G.; Lohan, N. M.

    2017-08-01

    Ni-Ti shape memory alloys (SMAs) are intelligent alloys which demonstrate unique properties, such as shape memory effect, two-way shape memory effect, super-elasticity and vibration damping which, accompanied by good processability, excellent corrosion resistance and biocompatibility as well as fair wear resistance and cyclic stability, enabled the development of important industrial applications (such as sensors, actuators, fasteners, couplings and valves), medical applications (such as stents, bone implants, orthodontic archwires, minimal invasive surgical equipment) as well as environmental health and safety devices (anti-seismic dampers, fire safety devices). The phase transitions in Ni-Ti SMAs are strongly influenced by processing methods, chemical compositions and thermomechanical history. This paper presents a study of the effects of heat treatment on the mechanical and thermal properties of commercial Ni-Ti shape memory alloy (SMA). The experimental work involved subjecting a SMA rod to heat-treatment consisting in heating up to 500°C, 10 minutes-maintaining and water quenching. Mechanical properties were highlighted by microhardness tests while thermal characteristics were emphasized by differential scanning calorimetry (DSC). The presence of chemical composition fluctuations was checked by X-ray energy dispersive spectroscopy performed with an EDAX Bruker analyzer.

  9. Fire risk assessment for hydrogen at EDG/battery room

    Energy Technology Data Exchange (ETDEWEB)

    Jee, Moon Hak; Hong, Sung Yull; Choi, Kwang Hee; Jung, Hyun Jong; Park, Kyung Hyum [Korea electric Power Research Institute, Taejon (Korea, Republic of); Song, Jin Bae [KHNP, Wolsong (Korea, Republic of)

    2004-07-01

    At the design stage of Nuclear Power Plant, the fire hazard analysis for the fire zone or compartment is implemented according to the fire protection requirement and the document is required for the licensing approval. On the basis of fire hazard analysis, the evaluation for the safe shutdown capability is preceded for each fire zone that contains safety-important systems and facilities. The primary philosophy for the fire safety is to secure fire defense-in-depth at Nuclear Power Plants that represents fire prevention, fire protection, and mitigation from fire damage. One of the concerning fire zones that need quantitative fire hazard analysis as well as qualitative fire evaluation at Nuclear Power Plants is the battery room at Emergency Diesel Generator (EDG) Room. For an example, Emergency Power Supply System called as EPS at Wolsong Nuclear Power Plant generates emergency power and supply the electric power to the safety-related systems and essential facilities during the loss of on-site and off-site AC power. For the start of emergency power generator, it needs DC power from the battery units inside the EPS room. For the emergency supply of DC power, the battery at EPS room should be recharged during the standby period to compensate the reduced chemical energy that was converted to the electric energy or depleted through the natural process. During the recharge process, especially at the time of charging current becoming greater than the nominal floating current or at the time of over-charging period, the hydrogen and the oxygen are generated from the positive plate and cathodic part respectively and escaped through the vent holes or crevices. In this context, the fire hazard assessment should be done for the EPS/battery room with quantitative approach and the fire safety evaluation for the explosion of hydrogen gas must be done under the specific fire protection program at Nuclear Power Plants.

  10. Fire risk assessment for hydrogen at EDG/battery room

    International Nuclear Information System (INIS)

    Jee, Moon Hak; Hong, Sung Yull; Choi, Kwang Hee; Jung, Hyun Jong; Park, Kyung Hyum; Song, Jin Bae

    2004-01-01

    At the design stage of Nuclear Power Plant, the fire hazard analysis for the fire zone or compartment is implemented according to the fire protection requirement and the document is required for the licensing approval. On the basis of fire hazard analysis, the evaluation for the safe shutdown capability is preceded for each fire zone that contains safety-important systems and facilities. The primary philosophy for the fire safety is to secure fire defense-in-depth at Nuclear Power Plants that represents fire prevention, fire protection, and mitigation from fire damage. One of the concerning fire zones that need quantitative fire hazard analysis as well as qualitative fire evaluation at Nuclear Power Plants is the battery room at Emergency Diesel Generator (EDG) Room. For an example, Emergency Power Supply System called as EPS at Wolsong Nuclear Power Plant generates emergency power and supply the electric power to the safety-related systems and essential facilities during the loss of on-site and off-site AC power. For the start of emergency power generator, it needs DC power from the battery units inside the EPS room. For the emergency supply of DC power, the battery at EPS room should be recharged during the standby period to compensate the reduced chemical energy that was converted to the electric energy or depleted through the natural process. During the recharge process, especially at the time of charging current becoming greater than the nominal floating current or at the time of over-charging period, the hydrogen and the oxygen are generated from the positive plate and cathodic part respectively and escaped through the vent holes or crevices. In this context, the fire hazard assessment should be done for the EPS/battery room with quantitative approach and the fire safety evaluation for the explosion of hydrogen gas must be done under the specific fire protection program at Nuclear Power Plants

  11. 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

  12. 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)

  13. 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

  14. Analysing initial attack on wildland fires using stochastic simulation.

    Science.gov (United States)

    Jeremy S. Fried; J. Keith Gilless; James. Spero

    2006-01-01

    Stochastic simulation models of initial attack on wildland fire can be designed to reflect the complexity of the environmental, administrative, and institutional context in which wildland fire protection agencies operate, but such complexity may come at the cost of a considerable investment in data acquisition and management. This cost may be well justified when it...

  15. Design options for improving protective gloves for industrial assembly work.

    Science.gov (United States)

    Dianat, Iman; Haslegrave, Christine M; Stedmon, Alex W

    2014-07-01

    The study investigated the effects of wearing two new designs of cotton glove on several hand performance capabilities and compared them against the effects of barehanded, single-layered and double cotton glove conditions when working with hand tools (screwdriver and pliers). The new glove designs were based on the findings of subjective hand discomfort assessments for this type of work and aimed to match the glove thickness to the localised pressure and sensitivity in different areas of the hand as well as to provide adequate dexterity for fine manipulative tasks. The results showed that the first prototype glove and the barehanded condition were comparable and provided better dexterity and higher handgrip strength than double thickness gloves. The results support the hypothesis that selective thickness in different areas of the hand could be applied by glove manufacturers to improve the glove design, so that it can protect the hands from the environment and at the same time allow optimal hand performance capabilities. Copyright © 2014 Elsevier Ltd and The Ergonomics Society. All rights reserved.

  16. Subsurface Fire Hazards Technical Report

    International Nuclear Information System (INIS)

    Logan, R.C.

    1999-01-01

    The results from this report are preliminary and cannot be used as input into documents supporting procurement, fabrication, or construction. This technical report identifies fire hazards and proposes their mitigation for the subsurface repository fire protection system. The proposed mitigation establishes the minimum level of fire protection to meet NRC regulations, DOE fire protection orders, that ensure fire containment, adequate life safety provisions, and minimize property loss. Equipment requiring automatic fire suppression systems is identified. The subsurface fire hazards that are identified can be adequately mitigated

  17. Design and Development of Functionally Effective Human-Machine Interfaces for Firing Room Displays

    Science.gov (United States)

    Cho, Henry

    2013-01-01

    This project involves creating software for support equipment used on the Space Launch System (SLS). The goal is to create applications and displays that will be used to remotely operate equipment from the firing room and will continue to support the SLS launch vehicle to the extent of its program. These displays include design practices that help to convey information effectively, such as minimizing distractions at normal operating state and displaying intentional distractions during a warning or alarm state. The general practice for creating an operator display is to reduce the detail of unimportant aspects of the display and promote focus on data and dynamic information. These practices include using minimalist design, using muted tones for background colors, using a standard font at a readable text size, displaying alarms visible for immediate attention, grouping data logically, and displaying data appropriately varying on the type of data. Users of these displays are more likely to stay focused on operating for longer periods by using design practices that reduce eye strain and fatigue. Effective operator displays will improve safety by reducing human errors during operation, which will help prevent catastrophic accidents. This report entails the details of my work on developing remote displays for the Hypergolic fuel servicing system. Before developing a prototype display, the design and requirements of the system are outlined and compiled into a document. Then each subsystem has schematic representations drawn that meet the specifications detailed in the document. The schematics are then used as the outline to create display representations of each subsystem. Each display is first tested individually. Then the displays are integrated with a prototype of the master system, and they are tested in a simulated environment then retested in the real environment. Extensive testing is important to ensure the displays function reliably as intended.

  18. Designing trails for subaquatic tourism in Marine Protected Areas

    Directory of Open Access Journals (Sweden)

    Cristina Piñeiro-Corbeira

    2014-05-01

    Full Text Available Although the range of touristic activities that take place in the sea has greatly expanded in recent years, the marine realm continues to be one of the least known to the public. Scuba diving and snorkeling are popular activities in the marine environment. Among its benefits, snorkeling is simple, cheap, and accessible to a wide range of population. In this regard, it has considerable potential as a tool for environmental education as it allows a firsthand observation of the subaquatic seascape as well as a direct interaction with marine wildlife. These attributes, together with its low ecological impact, make snorkeling an activity particularly suitable for marine protected areas. Yet, its implementation in marine protected areas requires new tools for an appropriate use. Here, we show an innovative procedure for assessing the underwater seascape that should help in the designation of touristic subaquatic trails analogous to those commonly used in terrestrial landscapes. We elaborated a system of 18 “Perceptible Seascape Elements”, grouped into 9 Concepts, that leads to a “Potential Observation Index” summarizing the seabed landscape qualities that can be observed while snorkeling. Tests of this approach in a National Park (Parque Nacional Marítimo-Terrestre de las Islas Atlánticas de Galicia led to the design and ranking of 6 underwater trails. On the other hand, we used standardized questionnaires to determine the attributes of park’s visitors, their expectative, their perception of the marine environment, and previous skills in snorkeling. Many visitors were mostly unaware of the qualities of the marine environment of the National Park but we found considerable interest in new alternatives to enjoy the marine environment such as snorkeling. Our procedure and results could help to add snorkeling to the set of environmental education strategies already used in the Park.

  19. Temperature of Steel Columns under Natural Fire

    Directory of Open Access Journals (Sweden)

    F. Wald

    2004-01-01

    Full Text Available Current fire design models for time-temperature development within structural elements as well as for structural behaviour are based on isolated member tests subjected to standard fire regimes, which serve as a reference heating, but do not model natural fire. Only tests on a real structure under a natural fire can evaluate future models of the temperature developments in a fire compartment, of the transfer of heat into the structure and of the overall structural behaviour under fire.To study overall structural behaviour, a research project was conducted on an eight storey steel frame building at the  Cardington Building Research Establishment laboratory on January 16, 2003. A fire compartment 11×7 m was prepared on the fourth floor. A fire load of 40 kg/m2 was applied with 100 % permanent mechanical load and 65 % of imposed load. The paper summarises the experimental programme and shows the temperature development of the gas in the fire compartment and of the fire protected columns bearing the unprotected floors.

  20. Microfine coal firing results from a retrofit gas/oil-designed industrial boiler

    Energy Technology Data Exchange (ETDEWEB)

    Patel, R.; Borio, R.W.; Liljedahl, G. [Combustion Engineering, Inc., Windsor, CT (United States)] [and others

    1995-11-01

    Under US Department of Energy, Pittsburgh Energy Technology Center (PETC) support, the development of a High Efficiency Advanced Coal Combustor (HEACC) has been in progress since 1987 at the ABB Power Plant Laboratories. The initial work on this concept produced an advanced coal firing system that was capable of firing both water-based and dry pulverized coal in an industrial boiler environment.