Large Scale Experiments on Spacecraft Fire Safety

DEFF Research Database (Denmark)

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

2012-01-01

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

Evaluation of fire probabilistic safety assessment for a PWR plant

International Nuclear Information System (INIS)

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

2001-01-01

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

Development of IFC based fire safety assesment tools

DEFF Research Database (Denmark)

Taciuc, Anca; Karlshøj, Jan; Dederichs, Anne

2016-01-01

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

The influence of sodium fires on LMFBRs safety analysis

Energy Technology Data Exchange (ETDEWEB)

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

1979-03-01

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

The influence of sodium fires on LMFBRs safety analysis

International Nuclear Information System (INIS)

Justin, F.

1979-01-01

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

Nuclear insurance fire risk

International Nuclear Information System (INIS)

Dressler, E.G.

2001-01-01

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

Risk-based safety indicators

International Nuclear Information System (INIS)

Szikszai, T.

1997-01-01

The presentation discusses the following issues: The objectives of the risk-based indicator programme. The characteristics of the risk-based indicators. The objectives of risk-based safety indicators - in monitoring safety; in PSA applications. What indicators? How to produce the risk based indicators? PSA requirements

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

Directory of Open Access Journals (Sweden)

Sarsangi V.* MSc,

2016-08-01

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

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

Behavior based safety approach towards fire

International Nuclear Information System (INIS)

Suresh Kumar, R.

2009-01-01

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

Estimating Fire Risks at Industrial Nuclear Facilities

International Nuclear Information System (INIS)

Coutts, D.A.

1999-01-01

The Savannah River Site (SRS) has a wide variety of nuclear production facilities that include chemical processing facilities, machine shops, production reactors, and laboratories. Current safety documentation must be maintained for the nuclear facilities at SRS. Fire Risk Analyses (FRAs) are used to support the safety documentation basis. These FRAs present the frequency that specified radiological and chemical consequences will be exceeded. The consequence values are based on mechanistic models assuming specific fire protection features fail to function as designed

Large-Scale Spacecraft Fire Safety Tests

Science.gov (United States)

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

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

International Nuclear Information System (INIS)

Hosser, D.; Sprey, W.

1986-01-01

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

Getting fire risk assessment right.

Science.gov (United States)

Charters, David

2012-06-01

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

Large-Scale Spacecraft Fire Safety Experiments in ISS Resupply Vehicles

Science.gov (United States)

Ruff, Gary A.; Urban, David

2013-01-01

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

Risk Assessment of the Main Control Room Fire Using Fire Simulations

International Nuclear Information System (INIS)

Kang, Dae Il; Kim, Kilyoo; Jang, Seung Cheol

2013-01-01

KAERI is performing a fire PSA for a reference plant, Ulchin Unit 3, as part of developing the Korean site risk profile (KSRP). Fire simulations of the MCR fire were conducted using the CFAST (Consolidated Fire Growth and Smoke Transport) model and FDS (fire dynamic simulator) to improve the uncertainty in the MCR fire risk analysis. Using the fire simulation results, the MCR abandonment risk was evaluated. Level 1 PSA (probabilistic safety assessment) results of Ulchin Unit 3 using the EPRI PRA (probabilistic risk assessment) implementation guide showed that the MCR (main control room) fire was the main contributor to the core damage frequency. Recently, U. S. NRC and EPRI developed NUREG/CR-6850 to provide state-of-the-art methods, tools, and data for the conduct of a fire PSA for a commercial NPP

Risk-based safety indicators

International Nuclear Information System (INIS)

Sedlak, J.

2001-12-01

The report is structured as follows: 1. Risk-based safety indicators: Typology of risk-based indicators (RBIs); Tools for defining RBIs; Requirements for the PSA model; Data sources for RBIs; Types of risks monitored; RBIs and operational safety indicators; Feedback from operating experience; PSO model modification for RBIs; RBI categorization; RBI assessment; RBI applications; Suitable RBI applications. 2. Proposal for risk-based indicators: Acquiring information from operational experience; Method of acquiring safety relevance coefficients for the systems from a PSA model; Indicator definitions; On-line indicators. 3. Annex: Application of RBIs worldwide. (P.A.)

Tech assist/fire safety assessment of 100K area facilities

International Nuclear Information System (INIS)

Johnson, B.H.

1994-01-01

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

A fire risk assessment model for residential high-rises with a single stairwell

DEFF Research Database (Denmark)

Hansen, N. D.; Steffensen, F.B.; Valkvist, M.B.

2018-01-01

As few or none prescriptive guidelines for fire risk assessment of residential high-rise buildings exist, it has been unclear which fire safety design features constitute an acceptable (adequate) safety level. In order to fill this gap a simplified risk-based decision-support tool, the Fire Risk...... Model (FRM), was developed. The FRM evaluates both the risk level to the occupants and the property risk level as a function of the building characteristics, height and fire safety features for single stairwell residential high-rise buildings. The acceptability of a high-rise design is then defined......, and the associated performance of the FRM evaluated. It was found that compartmentation and the door configurations in the egress path play an important role, along with sprinklers, in order for the design to successfully keep the stairwell free from smoke. Specifically, modern curtain wall facades were found...

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

International Nuclear Information System (INIS)

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

2006-12-01

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

Fire risk assessment in Germany. Procedure, data, results

International Nuclear Information System (INIS)

Berg, H.P.

2000-01-01

The recommended approach for a quantitative fire risk assessment to be applied within periodic safety reviews of nuclear power plants in Germany starts with a screening process providing critical fire zones and is followed by a quantitative analysis using a standard event tree with elements for fire initiation, ventilation of the room, fire detection, fire suppression, and fire propagation. In a final step, the fire induced frequency of initiating events, the main contributors and the calculated hazard state frequency for the fire event are determined. For that purpose, a comprehensive data base is needed which has been developed in particular for active fire protection measures. As an example results of one fire PSA are reported. (author)

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)

Reducing the risk, managing safety.

Science.gov (United States)

Aldridge, Peter

2016-02-01

Fire safety in healthcare premises has always been a challenge to those that discharge this duty. Statutory compliance should be a matter of course, but in an ever increasingly challenged NHS, even this is not a given. While the NHS is driven by managing very complex risk to deliver cutting edge healthcare, providers cannot be risk averse. Which risk, however, takes priority? Here Peter Aldridge, fire and corporate services manager at Leeds Teaching Hospitals NHS Trust, and Secretary to the National Association of Healthcare Fire Officers (NAHFO)--which will this month and next jointly stage fire safety seminars with IHEEM; see page 8--considers the key issues, with input from a fire officer at a leading mental health and community Trust.

Gis-Based Multi-Criteria Decision Analysis for Forest Fire Risk Mapping

Science.gov (United States)

Akay, A. E.; Erdoğan, A.

2017-11-01

The forested areas along the coastal zone of the Mediterranean region in Turkey are classified as first-degree fire sensitive areas. Forest fires are major environmental disaster that affects the sustainability of forest ecosystems. Besides, forest fires result in important economic losses and even threaten human lives. Thus, it is critical to determine the forested areas with fire risks and thereby minimize the damages on forest resources by taking necessary precaution measures in these areas. The risk of forest fire can be assessed based on various factors such as forest vegetation structures (tree species, crown closure, tree stage), topographic features (slope and aspect), and climatic parameters (temperature, wind). In this study, GIS-based Multi-Criteria Decision Analysis (MCDA) method was used to generate forest fire risk map. The study was implemented in the forested areas within Yayla Forest Enterprise Chiefs at Dursunbey Forest Enterprise Directorate which is classified as first degree fire sensitive area. In the solution process, "extAhp 2.0" plug-in running Analytic Hierarchy Process (AHP) method in ArcGIS 10.4.1 was used to categorize study area under five fire risk classes: extreme risk, high risk, moderate risk, and low risk. The results indicated that 23.81 % of the area was of extreme risk, while 25.81 % was of high risk. The result indicated that the most effective criterion was tree species, followed by tree stages. The aspect had the least effective criterion on forest fire risk. It was revealed that GIS techniques integrated with MCDA methods are effective tools to quickly estimate forest fire risk at low cost. The integration of these factors into GIS can be very useful to determine forested areas with high fire risk and also to plan forestry management after fire.

Fire Safety (For Parents)

Science.gov (United States)

... Staying Safe Videos for Educators Search English Español Fire Safety KidsHealth / For Parents / Fire Safety What's in ... event of a fire emergency in your home. Fire Prevention Of course, the best way to practice ...

Human Factors in Fire Safety Management and Prevention

Directory of Open Access Journals (Sweden)

M.A. Othuman Mydin

2014-07-01

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

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

Fire safety

International Nuclear Information System (INIS)

Keski-Rahkonen, O.; Bjoerkman, J.; Hostikka, S.; Mangs, J.; Huhtanen, R.; Palmen, H.; Salminen, A.; Turtola, A.

1998-01-01

According to experience and probabilistic risk assessments, fires present a significant hazard in a nuclear power plant. Fires may be initial events for accidents or affect safety systems planned to prevent accidents and to mitigate their consequences. The project consists of theoretical work, experiments and simulations aiming to increase the fire safety at nuclear power plants. The project has four target areas: (1) to produce validated models for numerical simulation programmes, (2) to produce new information on the behavior of equipment in case of fire, (3) to study applicability of new active fire protecting systems in nuclear power plants, and (4) to obtain quantitative knowledge of ignitions induced by important electric devices in nuclear power plants. These topics have been solved mainly experimentally, but modelling at different level is used to interpret experimental data, and to allow easy generalisation and engineering use of the obtained data. Numerical fire simulation has concentrated in comparison of CFD modelling of room fires, and fire spreading on cables on experimental data. So far the success has been good to fair. A simple analytical and numerical model has been developed for fire effluents spreading beyond the room of origin in mechanically strongly ventilated compartments. For behaviour of equipment in fire several full scale and scaled down calorimetric experiments were carried out on electronic cabinets, as well as on horizontal and vertical cable trays. These were carried out to supply material for CFD numerical simulation code validation. Several analytical models were developed and validated against obtained experimental results to allow quick calculations for PSA estimates as well as inter- and extrapolations to slightly different objects. Response times of different commercial fire detectors were determined for different types of smoke, especially emanating from smoldering and flaming cables to facilitate selection of proper detector

Fire Risk Scoping Study: Investigation of nuclear power plant fire risk, including previously unaddressed issues

International Nuclear Information System (INIS)

Lambright, J.A.; Nowlen, S.P.; Nicolette, V.F.; Bohn, M.P.

1989-01-01

An investigation of nuclear power plant fire risk issues raised as a result of the USNRC sponsored Fire Protection Research Program at Sandia National Laboratories has been performed. The specific objectives of this study were (1) to review and requantify fire risk scenarios from four fire probabilistic risk assessments (PRAs) in light of updated data bases made available as a result of USNRC sponsored Fire Protection Research Program and updated computer fire modeling capabilities, (2) to identify potentially significant fire risk issues that have not been previously addressed in a fire risk context and to quantify the potential impact of those identified fire risk issues where possible, and (3) to review current fire regulations and plant implementation practices for relevance to the identified unaddressed fire risk issues. In performance of the fire risk scenario requantifications several important insights were gained. It was found that utilization of a more extensive operational experience base resulted in both fire occurrence frequencies and fire duration times (i.e., time required for fire suppression) increasing significantly over those assumed in the original works. Additionally, some thermal damage threshold limits assumed in the original works were identified as being nonconservative based on more recent experimental data. Finally, application of the COMPBRN III fire growth model resulted in calculation of considerably longer fire damage times than those calculated in the original works using COMPBRN I. 14 refs., 2 figs., 16 tabs

Fire, safety and ventilation

Energy Technology Data Exchange (ETDEWEB)

Hindle, D.

1999-02-01

Correct ventilation in tunnel environments is vital for the comfort and safety of the people passing through. This article gives details of products from several manufacturers of safety rescue and fire fighting equipment, fire and fume detection equipment, special fire resistant materials, fire resistant hydraulic oils and fire dampers, and ventilation systems. Company addresses and fax numbers are supplied. 4 refs., 5 tabs., 10 photos.

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.

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)

Fire safety of wood construction

Science.gov (United States)

Robert H. White; Mark A. Dietenberger

2010-01-01

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

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Rocky Flats Plant Live-Fire Range Risk Analysis Report

Energy Technology Data Exchange (ETDEWEB)

Nicolosi, S.L.; Rodriguez, M.A.

1994-04-01

The objective of the Live-Fire Range Risk Analysis Report (RAR) is to provide an authorization basis for operation as required by DOE 5480.16. The existing Live-Fire Range does not have a safety analysis-related authorization basis. EG&G Rocky Flats, Inc. has worked with DOE and its representatives to develop a format and content description for development of an RAR for the Live-Fire Range. Development of the RAR is closely aligned with development of the design for a baffle system to control risks from errant projectiles. DOE 5480.16 requires either an RAR or a safety analysis report (SAR) for live-fire ranges. An RAR rather than a SAR was selected in order to gain flexibility to more closely address the safety analysis and conduct of operation needs for a live-fire range in a cost-effective manner.

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

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)

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

Directory of Open Access Journals (Sweden)

M. Mahdinia

2009-04-01

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

Cable fire risk of a nuclear power plant

International Nuclear Information System (INIS)

Aulamo, H.

1998-02-01

The aim of the study is to carry out a comprehensive review of cable fire risk issues of nuclear power plants (NPP) taking into account latest fire and risk assessment research results. A special emphasis is put on considering the fire risk analysis of cable rooms in the framework of TVO Olkiluoto NPP probabilistic safety assessment. The assumptions made in the analysis are assessed. The literature study section considers significant fire events at nuclear power plants, the most severe of which have nearly led to a reactor core damage (Browns Ferry, Greifswald, Armenia, Belojarsk, Narora). Cable fire research results are also examined

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...

Evacuation routes performances and fire safety of buildings

Directory of Open Access Journals (Sweden)

Laban Mirjana Đ.

2015-01-01

Full Text Available Residential buildings, public and business facilities with large number of occupants are particularly exposed to the risk of event with catastrophic consequences, especially in case of fire. Evacuation routes must be separated fire compartments with surfaces made of non-combustible materials. Safe evacuation of building occupants in case of fire is a crucial requirement for the preservation of human life in building. In our engineering practice, calculation model is usually applied in order to determine the time required for evacuation (SRPS TP 21. However, evacuation simulation models are more present in research papers, contributing to better assessment of flow of evacuation in the real time. These models could provide an efficient way of testing the safety of a building in the face of fire and indicate critical points at the evacuation paths. Computer models enable the development and analysis of multiple various scenarios during a fire event, contributing to defining the measures for improving the safety of the building in case of fire. This paper analyses the fulfilment of technical requirements for the safe evacuation and proposes improvement measures based on a comparative analysis of the time required for occupants' evacuation from the building (Department of Civil Engineering and Geodesy in Novi Sad, obtained by calculation model and by using evacuation simulation software.

Spacecraft Fire Safety Demonstration

Data.gov (United States)

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

Current Status of Fire Risk Assessment in Germany

International Nuclear Information System (INIS)

Berg, H. P.

2002-01-01

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

Fires and Food Safety

Science.gov (United States)

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

Smoking and Home Fire Safety

Science.gov (United States)

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

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

29 CFR 1915.502 - Fire safety plan.

Science.gov (United States)

2010-07-01

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

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

International Nuclear Information System (INIS)

Al-kattan, W.A.

2015-01-01

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

POZHARNYYe RISKI I IKH VLIYANIYe NA RISK-ORIYENTIROVANNYY PODKHOD PRI ORGANIZATSII I OSUSHCHESTVLENII FEDERAL'NOGO GOSUDARSTVENNOGO POZHARNOGO NADZORA [Fire risks and their impact on the risk-oriented approach in the organization and implementation of federal state fire supervision

Directory of Open Access Journals (Sweden)

Fomin A.I.

2017-09-01

Full Text Available The essence of fire risks and risk-oriented approaches in the organization and implementation of supervisory measures to fulfill the requirements in the field of fire safety is described. In accordance with the regulatory legal acts of the Russian Federation, the criteria for the assignment of protection objects and the frequency of conducting scheduled inspections with respect to them by the bodies of the federal state fire supervision are given. The influence of various factors on the risk category is given. Measures aimed at reducing the risk category and, as a result, reducing administrative barriers to the activities of legal entities and individuals have been identified. The analysis of the parameters influencing the magnitude of fire risks, as well as the risk category of the protection object, is given. The foregoing is provided in the form of an accessible scheme for persons who do not have special knowledge in meeting the requirements of fire safety. The urgency of developing a methodology and a criterion for reducing the hazard category of fire safety surveillance facilities is determined, taking into account the fulfillment by legal entities and individuals of previously issued regulations. That means: methodology, the application of which is possible when conducting unscheduled inspections by federal fire safety authorities.

The necessity of periodic fire safety review

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

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

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

Science.gov (United States)

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

2012-07-01

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

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

Science.gov (United States)

2010-07-01

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

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

International Nuclear Information System (INIS)

2000-01-01

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

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.)

The Safety Analysis of Shipborne Ammunition in Fire Environment

Science.gov (United States)

Ren, Junpeng; Wang, Xudong; Yue, Pengfei

2017-12-01

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

Fires in rooms containing electrical components - incident planning, fire fighting tactics, risks; Braender i driftrum - Insatsplaner, slaeckteknik, risker

Energy Technology Data Exchange (ETDEWEB)

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

2006-12-15

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

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

International Nuclear Information System (INIS)

1998-04-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

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

Transport fire safety engineering in the European Union - project TRANSFEU

Directory of Open Access Journals (Sweden)

Jolanta Maria RADZISZEWSKA-WOLIŃSKA

2011-01-01

Full Text Available Article presents European Research project (of FP7-SST-2008-RTD-1 for Surface transportation TRANSFEU. Projects undertakes to deliver both a reliable toxicity measurement methodology and a holistic fire safety approach for all kind of surface transport. It bases on a harmonized Fire Safety Engineering methodology which link passive fire security with active fire security mode. This all embracing system is the key to attain optimum design solutions in respect to fire safety objectives as an alternative to the prescriptive approach. It will help in the development of innovative solutions (design and products used for the building of the surface transport which will better respect the environment.In order to reach these objectives new toxicity measurement methodology and related classification of materials, new numerical fire simulation tools, fire test methodology (laboratory and full scale and a decisive tool to optimize or explore new design in accordance to the fire safety requirements will be developed.

Frequently Asked Questions in Fire Probabilistic Safety Assessment

International Nuclear Information System (INIS)

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

2010-05-01

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

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.)

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

International Nuclear Information System (INIS)

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

2003-07-01

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

Fire safety assessment of tunnel structures

DEFF Research Database (Denmark)

Gkoumas, Konstantinos; Giuliani, Luisa; Petrini, Francesco

2011-01-01

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

Some insights from fire risk analysis of US nuclear power plants

International Nuclear Information System (INIS)

Kazarians, M.; Lambright, J.A.; Frank, M.V.

1998-01-01

Fire risk analysis has been conducted for a significant portion of the nuclear power plants in the U.S. using either Probabilistic Risk Assessments (PRAs) or FIVE or a combination of the two methodologies. Practically all fire risk studies have used step-wise, screening approach. To establish the contents of a compartment, the cable routing information collected for Appendix R compliance have been used in practically all risk studies. In several cases, the analysts have gone beyond the Appendix R and have obtained the routing of additional cables. For fire impact analysis typically an existing PRA model is used. For fire frequencies, typically, a generic data base is used. Fire scenarios are identified in varying levels of detail. The most common approach, in the early stages of screening, is based on the assumption that given a fire, the entire contents of the compartment are lost. Less conservative scenarios are introduced at later stages of the analysis which may include fire propagation patterns, fires localized to an item. and suppression of the fire before critical damage. For fire propagation and damage analysis, a large number of studies have used FIVE and many have used COMPBRN. For detection and suppression analysis, the generic suppression system unavailabilities given in FIVE have been used. The total core damage frequencies typically range between 1x10 -6 to 1x10 -4 per year. Control rooms and cable spreading rooms are the two most common areas found to be significant contributors to fire risk. Other areas are mainly from the Auxiliary Building (in the case of PWRs) and Reactor Building (in the case of BWRs). Only in one case, the main contributor to fire is the turbine building, which included several safety related equipment and cables. (author)

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)

WRF-based fire risk modelling and evaluation for years 2010 and 2012 in Poland

Science.gov (United States)

Stec, Magdalena; Szymanowski, Mariusz; Kryza, Maciej

2016-04-01

Wildfires are one of the main ecosystems' disturbances for forested, seminatural and agricultural areas. They generate significant economic loss, especially in forest management and agriculture. Forest fire risk modeling is therefore essential e.g. for forestry administration. In August 2015 a new method of forest fire risk forecasting entered into force in Poland. The method allows to predict a fire risk level in a 4-degree scale (0 - no risk, 3 - highest risk) and consists of a set of linearized regression equations. Meteorological information is used as predictors in regression equations, with air temperature, relative humidity, average wind speed, cloudiness and rainfall. The equations include also pine litter humidity as a measure of potential fuel characteristics. All these parameters are measured routinely in Poland at 42 basic and 94 auxiliary sites. The fire risk level is estimated for a current (basing on morning measurements) or next day (basing on midday measurements). Entire country is divided into 42 prognostic zones, and fire risk level for each zone is taken from the closest measuring site. The first goal of this work is to assess if the measurements needed for fire risk forecasting may be replaced by the data from mesoscale meteorological model. Additionally, the use of a meteorological model would allow to take into account much more realistic spatial differentiation of weather elements determining the fire risk level instead of discrete point-made measurements. Meteorological data have been calculated using the Weather Research and Forecasting model (WRF). For the purpose of this study the WRF model is run in the reanalysis mode allowing to estimate all required meteorological data in a 5-kilometers grid. The only parameter that cannot be directly calculated using WRF is the litter humidity, which has been estimated using empirical formula developed by Sakowska (2007). The experiments are carried out for two selected years: 2010 and 2012. The

49 CFR 238.103 - Fire safety.

Science.gov (United States)

2010-10-01

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

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

International Nuclear Information System (INIS)

R. J. Garrett

2001-01-01

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

Cable fire risk of a nuclear power plant; Ydinvoimalaitoksen kaapelipaloriski

Energy Technology Data Exchange (ETDEWEB)

Aulamo, H.

1998-02-01

The aim of the study is to carry out a comprehensive review of cable fire risk issues of nuclear power plants (NPP) taking into account latest fire and risk assessment research results. A special emphasis is put on considering the fire risk analysis of cable rooms in the framework of TVO Olkiluoto NPP probabilistic safety assessment. The assumptions made in the analysis are assessed. The literature study section considers significant fire events at nuclear power plants, the most severe of which have nearly led to a reactor core damage (Browns Ferry, Greifswald, Armenia, Belojarsk, Narora). Cable fire research results are also examined. 62 refs.

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.

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

Engineering judgement and bridging the fire safety gap in existing nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Qamheiah, G.; Wu, Y., E-mail: gqamheiah@plcfire.com, E-mail: dwu@plcfire.com [PLC Fire Safety Solutions, Mississauga, ON (Canada)

2014-07-01

Canadian nuclear power plants were constructed in the 1960's through the 1980's. Fire safety considerations were largely based on guidance from general building and fire codes in effect at the time. Since then, nuclear specific fire safety standards have been developed and adopted by the Regulator, increasing the expected level of fire safety in the process. Application of the standards to existing plants was largely limited to operational requirements viewed as retroactive. However, as existing facilities undergo modifications or refurbishment for the purpose of life extension, the expectation is that the design requirements of these fire safety standards also be satisfied. This creates considerable challenges for existing nuclear power plants as fire safety requirements such as those intended to assure means for safe egress, prevention of fire spread and protection of redundancy rely upon fire protection features that are inherent in the physical infrastructural design. This paper focuses on the methodology for conducting fire safety gap analyses on existing plants, and the integral role that engineering judgement plays in the development of viable and cost effective solutions to achieve the objectives of the current fire safety standards. (author)

Fire Risk Assessment of Adaptive Re-Use of Historic Shop Houses for Sleeping Accommodations in Malaysia

Directory of Open Access Journals (Sweden)

Mydin M.A.O.

2014-01-01

Full Text Available Heritage buildings were generally constructed without regard for fire risks or the requirements for fire protection, as are obligatory in new constructions. When a heritage building undergoes a change to its original function, improvements to the building’s fire safety are necessary to meet the needs of possible increases in occupancy loads and to account for fire risks related to the new usage. This research focuses on fire safety risks, fire protection and safety systems as well as the rules and regulations that an adaptive reuse heritage shop house is bound to when transitioning to a sleeping accommodation, which, in this case, means becoming a hotel. In this research, six heritage shop houses were chosen as case studies. The objectives of this research were to evaluate current fire emergency plans as well as to identify and assess possible fire hazards created by adaptive reuse of heritage shop houses to sleeping accommodations in Penang through a series of observations and interviews. The results of the research show that most of the buildings were provided with inadequate fire safety systems.

Fire safety requirements for electrical cables towards nuclear reactor safety

International Nuclear Information System (INIS)

Raju, M.R.

2002-01-01

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

Nuclear power plants: a unique challenge to fire safety

International Nuclear Information System (INIS)

Nowlen, S.P.

1992-01-01

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

Fire risk analysis, fire simulation, fire spreading and impact of smoke and heat on instrumentation electronics - State-of-the-Art Report

International Nuclear Information System (INIS)

Roewekamp, M.; Bertrand, R.; Bonneval, F.; Hamblen, D.; Siu, N.; Aulamo, H.; Martila, J.; Sandberg, J.; Virolainen, R.

2000-01-01

OECD countries. The contents of each chapter are based on the writers' knowledge on his or her national practices and on the results of the questionnaire. The emphasis in the descriptions of the national practices also reflects the information supplied by the responding countries. Fire PSA is also used in other OECD countries, but the scope of this report is limited to those countries which responded to the questionnaire. The contents of this report are as follows: Fire PSA methodology overview - Based on a review of fire risk studies performed in the contributing countries, the report addresses different methodology and applications issues. Methodology issues, treated in Chapter 2, include the treatment of physical barriers, fire detection and suppression systems and fire fighting. They also include the treatment of operator actions and dependencies (both direct and indirect) between a fire and the plant's safety systems, definition of initiating events, and screening methods. Key assumptions and the effect of plant operational state (i.e., full power vs. low power operation) are dealt with in the report as well. Fire simulation models and codes applied or available - Chapter 3 of the report identifies which fire simulation codes have been used in actual PSAs. The models and scenarios used in different codes are described. To build confidence on fire simulation models, validation against experimental results in different types of fires is necessary. Fire experiments and the pre- and post experiment calculation used for code validation as well as ongoing fire simulation code development projects are discussed. Examples of fire scenarios and typical modeling assumptions are treated and numerous references are given in Chapter 3. References for experimental case studies and related simulation models and codes used for analyzing the production and spreading of smoke are also provided. The impact of smoke and heat - The immediate consequences of fires are caused by heat

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.

Investigation of Fire Safety Awareness and Management in Mall

Directory of Open Access Journals (Sweden)

Abdul Rahim N.

2014-03-01

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

An overview of the fire risk scoping study

International Nuclear Information System (INIS)

Nowlen, S.P.; Lambright, J.A.; Nicolette, V.F.; Bohn, M.P.

1989-01-01

The Fire Risk Scoping Study was sponsored by the US Nuclear Regulatory Commission and performed at Sandia National Laboratories. The study was initiated as a result of previous USNRC-sponsored fire research efforts that had identified certain fire risk issues that had not been addressed in previously completed commercial nuclear power plant fire risk analyses. The specific objectives of this study were (1) to review and requantify fire risk scenarios from four fire probabilistic risk assessments in light of updated data bases made available as a result of USNRC-sponsored Fire Protection Research Program and updated computer fire modeling capabilities, (2) to identify potentially significant fire risk issues that have not been previously addressed in a fire risk context and to quantify the potential impact of those identified fire risk issues where possible, and (3) to review current fire regulations and plant implementation practices for relevance to the identified unaddressed fire risk issues. 9 refs., 3 tabs

Fire safety analysis: methodology

International Nuclear Information System (INIS)

Kazarians, M.

1998-01-01

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

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

Science.gov (United States)

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

2015-08-01

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

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

CERN Document Server

Bernardini, Gabriele

2017-01-01

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

Cutting costs through detailed probabilistic fire risk analysis

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Luiz; Huser, Asmund; Vianna, Savio [Det Norske Veritas PRINCIPIA, Rio de Janeiro, RJ (Brazil)

2004-07-01

A new procedure for calculation of fire risks to offshore installations has been developed. The purposes of the procedure are to calculate the escalation and impairment frequencies to be applied in quantitative risk analyses, to optimize Passive Fire Protection (PFP) arrangement, and to optimize other fire mitigation means. The novelties of the procedure are that it uses state of the art Computational Fluid Dynamics (CFD) models to simulate fires and radiation, as well as the use of a probabilistic approach to decide the dimensioning fire loads. A CFD model of an actual platform was used to investigate the dynamic properties of a large set of jet fires, resulting in detailed knowledge of the important parameters that decide the severity of offshore fires. These results are applied to design the procedure. Potential increase in safety is further obtained for those conditions where simplified tools may have failed to predict abnormal heat loads due to geometrical effects. Using a field example it is indicated that the probabilistic approach can give significant reductions in PFP coverage with corresponding cost savings, still keeping the risk at acceptable level. (author)

Behavior based safety

International Nuclear Information System (INIS)

Sudhikumaran, T.V.; Mehta, S.C.; Goyal, D.K.

2009-01-01

Behaviour Based Safety (popularly known as BBS) is a new methodology for achieving injury free work place and total Safety Culture. BBS is successfully being implemented and is being practiced as a work methodology for achieving a loss and injury free work environment and work practice. Through BBS, it was brought out that the root causes of all Industrial accidents some how originate from the 'at risk' behaviour of some individual or group of individuals at some level. The policy of NPCIL is to excel in the field of Industrial and Fire Safety in comparison to international standards. This article indents to bring out the various parameters helping in installing BBS programme at any plant. (author)

Real time forest fire warning and forest fire risk zoning: a Vietnamese case study

Science.gov (United States)

Chu, T.; Pham, D.; Phung, T.; Ha, A.; Paschke, M.

2016-12-01

Forest fire occurs seriously in Vietnam and has been considered as one of the major causes of forest lost and degradation. Several studies of forest fire risk warning were conducted using Modified Nesterov Index (MNI) but remaining shortcomings and inaccurate predictions that needs to be urgently improved. In our study, several important topographic and social factors such as aspect, slope, elevation, distance to residential areas and road system were considered as "permanent" factors while meteorological data were updated hourly using near-real-time (NRT) remotely sensed data (i.e. MODIS Terra/Aqua and TRMM) for the prediction and warning of fire. Due to the limited number of weather stations in Vietnam, data from all active stations (i.e. 178) were used with the satellite data to calibrate and upscale meteorological variables. These data with finer resolution were then used to generate MNI. The only significant "permanent" factors were selected as input variables based on the correlation coefficients that computed from multi-variable regression among true fire-burning (collected from 1/2007) and its spatial characteristics. These coefficients also used to suggest appropriate weight for computing forest fire risk (FR) model. Forest fire risk model was calculated from the MNI and the selected factors using fuzzy regression models (FRMs) and GIS based multi-criteria analysis. By this approach, the FR was slightly modified from MNI by the integrated use of various factors in our fire warning and prediction model. Multifactor-based maps of forest fire risk zone were generated from classifying FR into three potential danger levels. Fire risk maps were displayed using webgis technology that is easy for managing data and extracting reports. Reported fire-burnings thereafter have been used as true values for validating the forest fire risk. Fire probability has strong relationship with potential danger levels (varied from 5.3% to 53.8%) indicating that the higher

Risk based limits for Operational Safety Requirements

International Nuclear Information System (INIS)

Cappucci, A.J. Jr.

1993-01-01

OSR limits are designed to protect the assumptions made in the facility safety analysis in order to preserve the safety envelope during facility operation. Normally, limits are set based on ''worst case conditions'' without regard to the likelihood (frequency) of a credible event occurring. In special cases where the accident analyses are based on ''time at risk'' arguments, it may be desirable to control the time at which the facility is at risk. A methodology has been developed to use OSR limits to control the source terms and the times these source terms would be available, thus controlling the acceptable risk to a nuclear process facility. The methodology defines a new term ''gram-days''. This term represents the area under a source term (inventory) vs time curve which represents the risk to the facility. Using the concept of gram-days (normalized to one year) allows the use of an accounting scheme to control the risk under the inventory vs time curve. The methodology results in at least three OSR limits: (1) control of the maximum inventory or source term, (2) control of the maximum gram-days for the period based on a source term weighted average, and (3) control of the maximum gram-days at the individual source term levels. Basing OSR limits on risk based safety analysis is feasible, and a basis for development of risk based limits is defensible. However, monitoring inventories and the frequencies required to maintain facility operation within the safety envelope may be complex and time consuming

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....

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

International Nuclear Information System (INIS)

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

2000-01-01

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

46 CFR 62.35-15 - Fire safety.

Science.gov (United States)

2010-10-01

... 46 Shipping 2 2010-10-01 2010-10-01 false Fire safety. 62.35-15 Section 62.35-15 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) MARINE ENGINEERING VITAL SYSTEM AUTOMATION Requirements for Specific Types of Automated Vital Systems § 62.35-15 Fire safety. (a) All required fire pump...

Risks due to fires at Big Rock Point

International Nuclear Information System (INIS)

Brinsfield, W.A.; Blanchard, D.P.

1983-01-01

The unique and older designs of the Big Rock Point nuclear plant is such that fires contribute significantly to the probability of core damage predicted in the probabilistic risk assessment performed for this plant. The methodology employed to determine this contribution reflects the unique, as constructed, plant design, while systematically and logically addressing the true effect of fires on the operation of the plant and the safety of the public. As a result of the methodology utilized in the PRA, recommendations are made which minimize the risk of core damage due to fires. Included in these recommendations is a proposal for equipment and controls to be included on the Big Rock Point alternate shutdown panel

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

International Nuclear Information System (INIS)

Alvarez, L.M.

1983-01-01

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

Fire Safety Deficiencies

Data.gov (United States)

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

40 CFR 30.18 - Hotel and motel fire safety.

Science.gov (United States)

2010-07-01

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

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

International Nuclear Information System (INIS)

COLLOPY, M.T.

1999-01-01

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

Alcohol skin preparation causes surgical fires.

Science.gov (United States)

Rocos, B; Donaldson, L J

2012-03-01

Surgical fires are a rare but serious preventable safety risk in modern hospitals. Data from the US show that up to 650 surgical fires occur each year, with up to 5% causing death or serious harm. This study used the National Reporting and Learning Service (NRLS) database at the National Patient Safety Agency to explore whether spirit-based surgical skin preparation fluid contributes to the cause of surgical fires. The NRLS database was interrogated for all incidents of surgical fires reported between 1 March 2004 and 1 March 2011. Each report was scrutinised manually to discover the cause of the fire. Thirteen surgical fires were reported during the study period. Of these, 11 were found to be directly related to spirit-based surgical skin preparation or preparation soaked swabs and drapes. Despite manufacturer's instructions and warnings, surgical fires continue to occur. Guidance published in the UK and US states that spirit-based skin preparation solutions should continue to be used but sets out some precautions. It may be that fire risk should be included in pre-surgical World Health Organization checklists or in the surgical training curriculum. Surgical staff should be aware of the risk that spirit-based skin preparation fluids pose and should take action to minimise the chance of fire occurring.

Risk Analysis for Road Tunnels – A Metamodel to Efficiently Integrate Complex Fire Scenarios

DEFF Research Database (Denmark)

Berchtold, Florian; Knaust, Christian; Arnold, Lukas

2018-01-01

Fires in road tunnels constitute complex scenarios with interactions between the fire, tunnel users and safety measures. More and more methodologies for risk analysis quantify the consequences of these scenarios with complex models. Examples for complex models are the computational fluid dynamics...... complex scenarios in risk analysis. To face this challenge, we improved the metamodel used in the methodology for risk analysis presented on ISTSS 2016. In general, a metamodel quickly interpolates the consequences of few scenarios simulated with the complex models to a large number of arbitrary scenarios...... used in risk analysis. Now, our metamodel consists of the projection array-based design, the moving least squares method, and the prediction interval to quantify the metamodel uncertainty. Additionally, we adapted the projection array-based design in two ways: the focus of the sequential refinement...

High resolution fire risk mapping in Italy

Science.gov (United States)

Fiorucci, Paolo; Biondi, Guido; Campo, Lorenzo; D'Andrea, Mirko

2014-05-01

extinguishing actions, leaving more resources to improve safety in areas at risk. With the availability of fire perimeters mapped over a period spanning from 5 to 10 years, depending by the region, a procedure was defined in order to assess areas at risk with high spatial resolution (900 m2) based on objective criteria by observing past fire events. The availability of fire perimeters combined with a detailed knowledge of topography and land cover allowed to understand which are the main features involved in forest fire occurrences and their behaviour. The seasonality of the fire regime was also considered, partitioning the analysis in two macro season (November- April and May- October). In addition, the total precipitation obtained from the interpolation of 30 years-long time series from 460 raingauges and the average air temperature obtained downscaling 30 years ERA-INTERIM data series were considered. About 48000 fire perimeters which burnt about 5500 km2 were considered in the analysis. The analysis has been carried out at 30 m spatial resolution. Some important considerations relating to climate and the territorial features that characterize the fire regime at national level contribute to better understand the forest fire phenomena. These results allow to define new strategies for forest fire prevention and management extensible to other geographical areas.

Probabilistic fire risk assessment for Koeberg Nuclear Power Station Unit 1

International Nuclear Information System (INIS)

Grobbelaar, J.F.; Foster, N.A.S.; Luesse, L.J.

1995-01-01

A probabilistic fire risk assessment was done for Koeberg Nuclear Power Station Unit 1. Areas where fires are likely to start were identified. Equipment important to safety, as well as their power and/or control cable routes were identified in each fire confinement sector. Fire confinement sectors where internal initiating events could be caused by fire were identified. Detection failure and suppression failure fault trees and event trees were constructed. The core damage frequency associated with each fire confinement sector was calculated, and important fire confinement sectors were identified. (author)

Appraisal of Fire Safety Management Systems at Educational Buildings

Directory of Open Access Journals (Sweden)

Nadzim N.

2014-01-01

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

Probabilistic safety analysis for fire events for the NPP Isar 2

International Nuclear Information System (INIS)

Schmaltz, H.; Hristodulidis, A.

2007-01-01

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

Review of UCN 5,6 Fire PSA Model based on ANS Fire PRA Standard

International Nuclear Information System (INIS)

Yang, Joon Eon; Lee, Yoon Hwan

2006-12-01

Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). This approach uses the fire risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In fire risk informed/performance-based decision/operation, fire PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of fire PSA. ANS (American Nuclear Society) has developed a guidance called 'ANS Fire PRA Methodology Standard'. However, in Korea, there have been no attempts to evaluate the quality of fire PSA model itself. Therefore, we cannot be sure about the quality of fire PSA whether or not the present fire PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of fire PSA model quality is the basis for the fire risk informed/performance-based decision/operation. In this report, we have evaluated the quality of fire PSA model for Ulchin 5 and 6 units based on the ANS Fire PRA Standard. We, also, have derived what items are to be improved to upgrade the quality of fire PSA model and how it can be improved. This report can be used as the base of the fire risk informed/performance-based decision/operation work in Korea

Quantitative Risk Modeling of Fire on the International Space Station

Science.gov (United States)

Castillo, Theresa; Haught, Megan

2014-01-01

The International Space Station (ISS) Program has worked to prevent fire events and to mitigate their impacts should they occur. Hardware is designed to reduce sources of ignition, oxygen systems are designed to control leaking, flammable materials are prevented from flying to ISS whenever possible, the crew is trained in fire response, and fire response equipment improvements are sought out and funded. Fire prevention and mitigation are a top ISS Program priority - however, programmatic resources are limited; thus, risk trades are made to ensure an adequate level of safety is maintained onboard the ISS. In support of these risk trades, the ISS Probabilistic Risk Assessment (PRA) team has modeled the likelihood of fire occurring in the ISS pressurized cabin, a phenomenological event that has never before been probabilistically modeled in a microgravity environment. This paper will discuss the genesis of the ISS PRA fire model, its enhancement in collaboration with fire experts, and the results which have informed ISS programmatic decisions and will continue to be used throughout the life of the program.

Safety tests carried out at Cadarache. Sodium fires

International Nuclear Information System (INIS)

Fruchard, M.

1976-01-01

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

Fire safety study of Dodewaard and Borssele nuclear power plants

International Nuclear Information System (INIS)

1988-03-01

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

Risk-based rules for crane safety systems

Energy Technology Data Exchange (ETDEWEB)

Ruud, Stian [Section for Control Systems, DNV Maritime, 1322 Hovik (Norway)], E-mail: Stian.Ruud@dnv.com; Mikkelsen, Age [Section for Lifting Appliances, DNV Maritime, 1322 Hovik (Norway)], E-mail: Age.Mikkelsen@dnv.com

2008-09-15

The International Maritime Organisation (IMO) has recommended a method called formal safety assessment (FSA) for future development of rules and regulations. The FSA method has been applied in a pilot research project for development of risk-based rules and functional requirements for systems and components for offshore crane systems. This paper reports some developments in the project. A method for estimating target reliability for the risk-control options (safety functions) by means of the cost/benefit decision criterion has been developed in the project and is presented in this paper. Finally, a structure for risk-based rules is proposed and presented.

Risk-based rules for crane safety systems

International Nuclear Information System (INIS)

Ruud, Stian; Mikkelsen, Age

2008-01-01

The International Maritime Organisation (IMO) has recommended a method called formal safety assessment (FSA) for future development of rules and regulations. The FSA method has been applied in a pilot research project for development of risk-based rules and functional requirements for systems and components for offshore crane systems. This paper reports some developments in the project. A method for estimating target reliability for the risk-control options (safety functions) by means of the cost/benefit decision criterion has been developed in the project and is presented in this paper. Finally, a structure for risk-based rules is proposed and presented

Forest fire risk zonation mapping using remote sensing technology

Science.gov (United States)

Chandra, Sunil; Arora, M. K.

2006-12-01

Forest fires cause major losses to forest cover and disturb the ecological balance in our region. Rise in temperature during summer season causing increased dryness, increased activity of human beings in the forest areas, and the type of forest cover in the Garhwal Himalayas are some of the reasons that lead to forest fires. Therefore, generation of forest fire risk maps becomes necessary so that preventive measures can be taken at appropriate time. These risk maps shall indicate the zonation of the areas which are in very high, high, medium and low risk zones with regard to forest fire in the region. In this paper, an attempt has been made to generate the forest fire risk maps based on remote sensing data and other geographical variables responsible for the occurrence of fire. These include altitude, temperature and soil variations. Key thematic data layers pertaining to these variables have been generated using various techniques. A rule-based approach has been used and implemented in GIS environment to estimate fuel load and fuel index leading to the derivation of fire risk zonation index and subsequently to fire risk zonation maps. The fire risk maps thus generated have been validated on the ground for forest types as well as for forest fire risk areas. These maps would help the state forest departments in prioritizing their strategy for combating forest fires particularly during the fire seasons.

Risk-informed decision-making analysis for the electrical raceway fire barrier systems on a BWR-4 plant

International Nuclear Information System (INIS)

Wu, Ching-Hui; Lin, Tsu-Jen; Kao, Tsu-Mu; Chen, Chyn-Rong

2003-01-01

This paper describes a risk-informed decision-making approach used to resolve the fire barrier issue in a BWR-4 nuclear plant where Appendix R separation requirements cannot be met without installing additional fire protection features such as electrical raceway fire barrier system. The related risk measures in CDF (core damage frequency) and LERF (large early release frequency) of the fire barrier issue can be determined by calculating the difference in plant risks between various alternative cases and that met the requirement of the Appendix R. In some alternative cases, additional early-detection and fast-response fire suppression systems are suggested. In some other cases, cable re-routing of some improper layout of non-safety related cables are required. Sets of fire scenarios are re-evaluated more detailed by reviewing the cable damage impact for the BWR-4 plant. The fire hazard model, COMPBRM III-e, is used in this study and the dominant results in risk measures are benchmarked with the CFD code, FDS 2.0, to ensure that the risk impact of fire barrier is estimated accurately in the risk-informed decision making. The traditional deterministic qualitative methods, such as defense-in-depth, safety margin and post-fire safety shutdown capability are also proceeded. The value-impact analysis for proposed alternatives of fire wrapping required by Appendix R has been completed for technical basis of the exemption on Appendix R application. The outcome of the above analysis should be in compliance with the regulatory guidelines (RG) 1.174 and 1.189 for the applications in the risk-informed decision-making of the fire wrapping issues. (author)

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

International Nuclear Information System (INIS)

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

1976-01-01

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

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

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

International Nuclear Information System (INIS)

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

1986-06-01

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

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

International Nuclear Information System (INIS)

Murakami, Tomoyuki; Nishihara, Tetsuo; Kunitomi, Kazuhiko

2008-01-01

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

Safety assessment of indoor live fire range, May 1989

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-05-01

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

Risk assessment of main control board fire using fire dynamics simulator

Energy Technology Data Exchange (ETDEWEB)

Kang, Dae Il, E-mail: dikang@kaeri.re.kr [KAERI, 1045 Daedeokdaero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of); Kim, Kilyoo; Jang, Seung-Cheol [KAERI, 1045 Daedeokdaero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of); Yoo, Seong Yeon [Chungnam National University, 79, Daehagro, Yuseong-Gu, Daejeon (Korea, Republic of)

2015-08-15

Highlights: • A decision tree for evaluating the risk of a main control board (MCB) fire was proposed to systematically determine the MCB fire scenarios. • Fire simulations using fire dynamics simulator (FDS) were performed to estimate the time to MCR abandonment. • Non-propagating and propagating fire scenarios were considered for fire simulations. • The current study indicates that the quantification of the MCB fire risk should address the propagating fire and non-propagating fire scenarios if the MCB has no internal barriers between the panels. - Abstract: This paper presents the process and results of a risk assessment for a main control board (MCB) fire using fire dynamics simulator (FDS). A decision tree for evaluating the risk of a MCB fire was proposed to systematically determine the MCB fire scenarios, and fire simulations using FDS were performed to estimate the time to MCR abandonment. As a reference NPP for this study, Hanul unit 3 in Korea was selected and its core damage frequency (CDF) owing to the MCB fire was quantified. Two types of fire scenarios were considered for fire simulations: non-propagating fire scenarios occurring within a single MCB panel and propagating fire scenarios spreading from one control panel to the adjacent panels. Further, the fire scenarios were classified into fires with and without a heating, ventilation, and air conditioning system (HVACS). The fire simulation results showed that the major factor causing the MCR evacuation was the optical density irrelevant to the availability of the HVACS. The risk assessment results showed that the abandonment fire scenario risk was less than the non-abandonment fire scenario risk and the propagating fire scenario risk was greater than the non-propagating fire scenario risk.

Risk assessment of main control board fire using fire dynamics simulator

International Nuclear Information System (INIS)

Kang, Dae Il; Kim, Kilyoo; Jang, Seung-Cheol; Yoo, Seong Yeon

2015-01-01

Highlights: • A decision tree for evaluating the risk of a main control board (MCB) fire was proposed to systematically determine the MCB fire scenarios. • Fire simulations using fire dynamics simulator (FDS) were performed to estimate the time to MCR abandonment. • Non-propagating and propagating fire scenarios were considered for fire simulations. • The current study indicates that the quantification of the MCB fire risk should address the propagating fire and non-propagating fire scenarios if the MCB has no internal barriers between the panels. - Abstract: This paper presents the process and results of a risk assessment for a main control board (MCB) fire using fire dynamics simulator (FDS). A decision tree for evaluating the risk of a MCB fire was proposed to systematically determine the MCB fire scenarios, and fire simulations using FDS were performed to estimate the time to MCR abandonment. As a reference NPP for this study, Hanul unit 3 in Korea was selected and its core damage frequency (CDF) owing to the MCB fire was quantified. Two types of fire scenarios were considered for fire simulations: non-propagating fire scenarios occurring within a single MCB panel and propagating fire scenarios spreading from one control panel to the adjacent panels. Further, the fire scenarios were classified into fires with and without a heating, ventilation, and air conditioning system (HVACS). The fire simulation results showed that the major factor causing the MCR evacuation was the optical density irrelevant to the availability of the HVACS. The risk assessment results showed that the abandonment fire scenario risk was less than the non-abandonment fire scenario risk and the propagating fire scenario risk was greater than the non-propagating fire scenario risk

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

International Nuclear Information System (INIS)

1998-01-01

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

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

DEFF Research Database (Denmark)

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

2014-01-01

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

Achieving safety/risk goals for less ATR backup power upgrades

International Nuclear Information System (INIS)

Atkinson, S.A.

1995-01-01

The Advanced Test Reactor probabilistic risk assessment for internal fire and flood events defined a relatively high risk for a total loss of electric power possibly leading to core damage. Backup power sources were disabled due to fire and flooding in the diesel generator area with propagation of the flooding to a common switchgear room. The ATR risk assessment was employed to define options for relocation of backup power system components to achieve needed risk reduction while minimizing costs. The risk evaluations were performed using sensitivity studies and importance measures. The risk-based evaluations of relocation options for backup power systems saved over $3 million from what might have been otherwise considered open-quotes necessaryclose quotes for safety/risk improvement. The ATR experience shows that the advantages of a good risk assessment are to define risk significance, risk specifics, and risk solutions which enable risk goals to be achieved at the lowest cost

Fire and blast safety manual for fuel element manufacture

International Nuclear Information System (INIS)

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

1988-01-01

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

Pedestrian safety management using the risk-based approach

Directory of Open Access Journals (Sweden)

Romanowska Aleksandra

2017-01-01

Full Text Available The paper presents a concept of a multi-level pedestrian safety management system. Three management levels are distinguished: strategic, tactical and operational. The basis for the proposed approach to pedestrian safety management is a risk-based method. In the approach the elements of behavioural and systemic theories were used, allowing for the development of a formalised and repeatable procedure integrating the phases of risk assessment and response to the hazards of road crashes involving pedestrians. Key to the method are tools supporting pedestrian safety management. According to the risk management approach, the tools can be divided into two groups: tools supporting risk assessment and tools supporting risk response. In the paper attention is paid to selected tools supporting risk assessment, with particular emphasis on the methods for estimating forecasted pedestrian safety measures (at strategic, national and regional level and identification of particularly dangerous locations in terms of pedestrian safety at tactical (regional and local and operational level. The proposed pedestrian safety management methods and tools can support road administration in making rational decisions in terms of road safety, safety of road infrastructure, crash elimination measures or reducing the consequences suffered by road users (particularly pedestrians as a result of road crashes.

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

International Nuclear Information System (INIS)

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

1976-01-01

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

Risk based maintenance to increase safety and decrease costs

International Nuclear Information System (INIS)

Phillips, J.H.

2000-01-01

Risk-Based techniques have been developed for commercial nuclear power plants for the last eight years by a team working through the ASME Center for Research and Technology Development (CRTD). System boundaries and success criteria is defined using the Probabilistic Risk Analysis or Probabilistic Safety Analysis developed to meet the Individual Plant Evaluation. Final ranking of components is by a plant expert panel similar to the one developed for the Maintenance Rule. Components are identified as being high risk-significant or low risk-significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of plants. Results from the first risk-based inspection pilot plant indicates safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. Pilot studies on risk-based testing indicate that about 60% of pumps and 25 to 30% of valves in plants are high safety-significant The reduction in inspection and testing reduces the person-rem exposure and resulting in further increases in safety. These techniques have been documented in publications by the ASME CRTD which are referenced. (author)

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

Science.gov (United States)

Arch, B N; Thurston, M N

2013-06-01

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

Risk Insights Gained from Fire Incidents

International Nuclear Information System (INIS)

Kazarians, Mardy; Nowlen, Steven P.

1999-01-01

There now exist close to 20 years of history in the application of Probabilistic Risk Assessment (PRA) for the analysis of fire risk at nuclear power plants. The current methods are based on various assumptions regarding fire phenomena, the impact of fire on equipment and operator response, and the overall progression of a fire event from initiation through final resolution. Over this same time period, a number of significant fire incidents have occurred at nuclear power plants around the world. Insights gained from US experience have been used in US studies as the statistical basis for establishing fire initiation frequencies both as a function of the plant area and the initiating fire source.To a lesser extent, the fire experience has also been used to assess the general severity and duration of fires. However, aside from these statistical analyses, the incidents have rarely been scrutinized in detail to verify the underlying assumptions of fire PRAs. This paper discusses an effort, under which a set of fire incidents are being reviewed in order to gain insights directly relevant to the methods, data, and assumptions that form the basis for current fire PRAs. The paper focuses on the objectives of the effort, the specific fire events being reviews methodology, and anticipated follow-on activities

Fire Safety Trianing in Health Care Institutions.

Science.gov (United States)

American Hospital Association, Chicago, IL.

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

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...

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

Overview of Risk Mitigation for Safety-Critical Computer-Based Systems

Science.gov (United States)

Torres-Pomales, Wilfredo

2015-01-01

This report presents a high-level overview of a general strategy to mitigate the risks from threats to safety-critical computer-based systems. In this context, a safety threat is a process or phenomenon that can cause operational safety hazards in the form of computational system failures. This report is intended to provide insight into the safety-risk mitigation problem and the characteristics of potential solutions. The limitations of the general risk mitigation strategy are discussed and some options to overcome these limitations are provided. This work is part of an ongoing effort to enable well-founded assurance of safety-related properties of complex safety-critical computer-based aircraft systems by developing an effective capability to model and reason about the safety implications of system requirements and design.

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...

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

Directory of Open Access Journals (Sweden)

Laban Mirjana Đ.

2015-01-01

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

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

DEFF Research Database (Denmark)

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

2014-01-01

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

Safety assessment of outdoor live fire range

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-05-01

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-07-30

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

Wildfire risk reduction in the United States: Leadership staff perceptions of local fire department roles and responsibilities

Science.gov (United States)

Rachel S. Madsen; Hylton J. G. Haynes; Sarah M. McCaffrey

2018-01-01

As wildland fires have had increasing negative impacts on a range of human values, in many parts of the United States (U.S.) and around the world, collaborative risk reduction efforts among agencies, homeowners, and fire departments are needed to improve wildfire safety and mitigate risk. Using interview data from 46 senior officers from local fire departments around...

Developing a Risk Model for Fire in Passenger Ships - Based on Bayesian Belief Network

OpenAIRE

Dokmo, Hanne Bjørkås

2016-01-01

Passenger ships, especially cruise ships, are rapidly increasing in size. With larger vessels, comes a greater risk to the passengers if something where to happen. A fire on a passenger vessel can spread quickly, and with as much as thousands of people needing to be evacuated many things could go wrong. The issue of the safety on board is therefore crucial to consider, seeing as the consequences could be tremendous. There are three types of passenger ships; Passenger vessel, RoPax vessel and ...

National Fire Risk Map for Continental USA: Creation and Validation

International Nuclear Information System (INIS)

Zhang, Q; Wollersheim, M; Griffiths, S; Maddox, I

2014-01-01

A nation-wide fire risk map for the continental USA has been created based on a hybrid fire risk model, incorporating a combination of static risk indicators which change very slowly over time, and dynamic risk indicators that may vary significantly from week-to-week. Static risk indicators include: terrain elevation, terrain slope, terrain aspect, and distance from roads and settlements. Each of the static risk indicators are derived from Intermap's high-accuracy NEXTMap ® USA database. The dynamic risk indicators are derived from satellite-based multi-spectral imagery and provide a snapshot of the fuel-moisture conditions during fire seasons. Each of these risk indicators are combined to produce a map provided at 5m posting and normalized to the range of 0 (very low risk) and 255 (very high risk). The map has been validated in two selected areas using historical fire information

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

International Nuclear Information System (INIS)

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

1985-01-01

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

A different approach to quantifying fire risks when decision making

International Nuclear Information System (INIS)

Hay, Adrian

1991-01-01

This article outlines an alternative approach to fire safety design which involves decision making on the basis of risk considerations. The methodology is being developed in conjunction with the nuclear industry but is considered equally applicable to other industrial facilities. (author)

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

Internet of Things Based Combustible Ice Safety Monitoring System Framework

Science.gov (United States)

Sun, Enji

2017-05-01

As the development of human society, more energy is requires to meet the need of human daily lives. New energies play a significant role in solving the problems of serious environmental pollution and resources exhaustion in the present world. Combustible ice is essentially frozen natural gas, which can literally be lit on fire bringing a whole new meaning to fire and ice with less pollutant. This paper analysed the advantages and risks on the uses of combustible ice. By compare to other kinds of alternative energies, the advantages of the uses of combustible ice were concluded. The combustible ice basic physical characters and safety risks were analysed. The developments troubles and key utilizations of combustible ice were predicted in the end. A real-time safety monitoring system framework based on the internet of things (IOT) was built to be applied in the future mining, which provide a brand new way to monitoring the combustible ice mining safety.

Fire risk in California

Science.gov (United States)

Peterson, Seth Howard

Fire is an integral part of ecosystems in the western United States. Decades of fire suppression have led to (unnaturally) large accumulations of fuel in some forest communities, such as the lower elevation forests of the Sierra Nevada. Urban sprawl into fire prone chaparral vegetation in southern California has put human lives at risk and the decreased fire return intervals have put the vegetation community at risk of type conversion. This research examines the factors affecting fire risk in two of the dominant landscapes in the state of California, chaparral and inland coniferous forests. Live fuel moisture (LFM) is important for fire ignition, spread rate, and intensity in chaparral. LFM maps were generated for Los Angeles County by developing and then inverting robust cross-validated regression equations from time series field data and vegetation indices (VIs) and phenological metrics from MODIS data. Fire fuels, including understory fuels which are not visible to remote sensing instruments, were mapped in Yosemite National Park using the random forests decision tree algorithm and climatic, topographic, remotely sensed, and fire history variables. Combining the disparate data sources served to improve classification accuracies. The models were inverted to produce maps of fuel models and fuel amounts, and these showed that fire fuel amounts are highest in the low elevation forests that have been most affected by fire suppression impacting the natural fire regime. Wildland fires in chaparral commonly burn in late summer or fall when LFM is near its annual low, however, the Jesusita Fire burned in early May of 2009, when LFM was still relatively high. The HFire fire spread model was used to simulate the growth of the Jesusita Fire using LFM maps derived from imagery acquired at the time of the fire and imagery acquired in late August to determine how much different the fire would have been if it had occurred later in the year. Simulated fires were 1.5 times larger

Building safety and human behaviour in fire: A literature review

NARCIS (Netherlands)

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

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-05-15

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-15

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

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

African Journals Online (AJOL)

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

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

International Nuclear Information System (INIS)

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

2015-01-01

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

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

International Nuclear Information System (INIS)

Aaslund, A.

2000-03-01

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

A Method of Fire Scenarios Identification in a Consolidated Fire Risk Analysis

International Nuclear Information System (INIS)

Lim, Ho Gon; Han, Sang Hoon; Yang, Joon Eon

2010-01-01

Conventional fire PSA consider only two cases of fire scenarios, that is one for fire without propagation and the other for single propagation to neighboring compartment. Recently, a consolidated fire risk analysis using single fault tree (FT) was developed. However, the fire scenario identification in the new method is similar to conventional fire analysis method. The present study develops a new method of fire scenario identification in a consolidated fire risk analysis method. An equation for fire propagation is developed to identify fire scenario and a mapping method of fire scenarios into internal event risk model is discussed. Finally, an algorithm for automatic program is suggested

Safety analysis of the existing 850 Firing Facility

International Nuclear Information System (INIS)

Odell, B.N.

1986-01-01

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

Safety analysis of the existing 851 Firing Facility

International Nuclear Information System (INIS)

Odell, B.N.

1986-01-01

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

The Italian National Guidelines for the fire safety of facades

Directory of Open Access Journals (Sweden)

Lamberto Mazziotti

2013-11-01

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

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

Methodology of using CFD-based risk assessment in road tunnels

Directory of Open Access Journals (Sweden)

Vidmar Peter

2007-01-01

Full Text Available The definition of the deterministic approach in the safety analyses comes from the need to understand the conditions that come out during the fire accident in a road tunnel. The key factor of the tunnel operations during the fire is the ventilation, which during the initial fazes of the fire, impact strongly on the evacuation of people and latter on the access of the intervention units in the tunnel. The paper presents the use of the computational fluid dynamics model in the tunnel safety assessment process. The model is validated by comparing data with experimental and quantifying the differences. The set-up of the initial and boundary conditions and the requirement for grid density found during the validation tests is used to prepare three kind of fire scenarios 20 MW, 50 MW, and 100 MW, with different ventilation conditions; natural, semi transverse, full transverse, and longitudinal ventilation. The observed variables, soot density and temperature, are presented in minutes time steps trough the entire tunnel length. Comparing the obtained data in a table, allows the analyses of the ventilation conditions for different heat releases from fires. The second step is to add additional criteria of human behaviour inside the tunnel (evacuation and human resistance to the elevated gas concentrations and temperature. What comes out is a fully deterministic risk matrix that is based on the calculated data where the risk is ranged on five levels, from the lowest to a very danger level. The deterministic risk matrix represents the alternative to a probabilistic safety assessment methodology, where the fire risk is represented in detail as well as the computational fluid dynamics model results are physically correct. .

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

Directory of Open Access Journals (Sweden)

Kalyana Chakravarthy Pentapati

2015-01-01

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

Industrial safety and fire protection during the construction phase

International Nuclear Information System (INIS)

Zimmer, K.

1977-01-01

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

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

Planning an Automatic Fire Detection, Alarm, and Extinguishing System for Research Laboratories

Directory of Open Access Journals (Sweden)

Rostam Golmohamadi

2014-04-01

Full Text Available Background & Objectives: Educational and research laboratories in universities have a high risk of fire, because they have a variety of materials and equipment. The aim of this study was to provide a technical plan for safety improvement in educational and research laboratories of a university based on the design of automatic detection, alarm, and extinguishing systems . Methods : In this study, fire risk assessment was performed based on the standard of Military Risk Assessment method (MIL-STD-882. For all laboratories, detection and fire alarm systems and optimal fixed fire extinguishing systems were designed. Results : Maximum and minimum risks of fire were in chemical water and wastewater (81.2% and physical agents (62.5% laboratories, respectively. For studied laboratories, we designed fire detection systems based on heat and smoke detectors. Also in these places, fire-extinguishing systems based on CO2 were designed . Conclusion : Due to high risk of fire in studied laboratories, the best control method for fire prevention and protection based on special features of these laboratories is using automatic detection, warning and fire extinguishing systems using CO2 .

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...

Risk Quantitative Determination of Fire and Explosion in a Process Unit By Dow’s Fire and Explosion Index

Directory of Open Access Journals (Sweden)

S. Varmazyar

2008-04-01

Full Text Available Background and aims   Fire and explosion hazards are the first and second of major hazards in process industries, respectively. This study has been done to determine fire and explosion risk severity,radius of exposure and estimating of most probable loss.   Methods   In this quantitative study process unit has been selected with affecting parameters on  fire and explosion risk. Then, it was analyzed by DOW's fire and explosion index (F&EI. Technical data were obtained from process documents and reports, fire and explosion guideline.After calculating of DOW's index, radius of exposure determined and finally most  probable loss was estimated.   Results   The results showed an F&EI value of 226 for this process unit.The F&EI was extremely  high and unacceptable.Risk severity was categorized in sever class.Radius of exposure and damage factor were calculated 57 meters and 83%,respectively. As well as most probable loss was  estimated about 6.7 million dollars.   Conclusion   F&EI is a proper technique for risk assessment and loss estimation of fire and  explosion in process industries.Also,It is an important index for detecting high risk and low risk   areas in an industry. At this technique, all of factors affecting on fire and explosion risk was  showed as index that is a base for judgement risk class. Finally, estimated losses could be used as  a base of fire and explosion insurance.

Formal safety assessment based on relative risks model in ship navigation

Energy Technology Data Exchange (ETDEWEB)

Hu Shenping [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: sphu@mmc.shmtu.edu.cn; Fang Quangen [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: qgfang@mmc.shmtu.edu.cn; Xia Haibo [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: hbxia@mmc.shmtu.edu.cn; Xi Yongtao [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: xiyt@mmc.shmtu.edu.cn

2007-03-15

Formal safety assessment (FSA) is a structured and systematic methodology aiming at enhancing maritime safety. It has been gradually and broadly used in the shipping industry nowadays around the world. On the basis of analysis and conclusion of FSA approach, this paper discusses quantitative risk assessment and generic risk model in FSA, especially frequency and severity criteria in ship navigation. Then it puts forward a new model based on relative risk assessment (MRRA). The model presents a risk-assessment approach based on fuzzy functions and takes five factors into account, including detailed information about accident characteristics. It has already been used for the assessment of pilotage safety in Shanghai harbor, China. Consequently, it can be proved that MRRA is a useful method to solve the problems in the risk assessment of ship navigation safety in practice.

Formal safety assessment based on relative risks model in ship navigation

International Nuclear Information System (INIS)

Hu Shenping; Fang Quangen; Xia Haibo; Xi Yongtao

2007-01-01

Formal safety assessment (FSA) is a structured and systematic methodology aiming at enhancing maritime safety. It has been gradually and broadly used in the shipping industry nowadays around the world. On the basis of analysis and conclusion of FSA approach, this paper discusses quantitative risk assessment and generic risk model in FSA, especially frequency and severity criteria in ship navigation. Then it puts forward a new model based on relative risk assessment (MRRA). The model presents a risk-assessment approach based on fuzzy functions and takes five factors into account, including detailed information about accident characteristics. It has already been used for the assessment of pilotage safety in Shanghai harbor, China. Consequently, it can be proved that MRRA is a useful method to solve the problems in the risk assessment of ship navigation safety in practice

Bayesian-network-based safety risk analysis in construction projects

International Nuclear Information System (INIS)

Zhang, Limao; Wu, Xianguo; Skibniewski, Miroslaw J.; Zhong, Jingbing; Lu, Yujie

2014-01-01

This paper presents a systemic decision support approach for safety risk analysis under uncertainty in tunnel construction. Fuzzy Bayesian Networks (FBN) is used to investigate causal relationships between tunnel-induced damage and its influential variables based upon the risk/hazard mechanism analysis. Aiming to overcome limitations on the current probability estimation, an expert confidence indicator is proposed to ensure the reliability of the surveyed data for fuzzy probability assessment of basic risk factors. A detailed fuzzy-based inference procedure is developed, which has a capacity of implementing deductive reasoning, sensitivity analysis and abductive reasoning. The “3σ criterion” is adopted to calculate the characteristic values of a triangular fuzzy number in the probability fuzzification process, and the α-weighted valuation method is adopted for defuzzification. The construction safety analysis progress is extended to the entire life cycle of risk-prone events, including the pre-accident, during-construction continuous and post-accident control. A typical hazard concerning the tunnel leakage in the construction of Wuhan Yangtze Metro Tunnel in China is presented as a case study, in order to verify the applicability of the proposed approach. The results demonstrate the feasibility of the proposed approach and its application potential. A comparison of advantages and disadvantages between FBN and fuzzy fault tree analysis (FFTA) as risk analysis tools is also conducted. The proposed approach can be used to provide guidelines for safety analysis and management in construction projects, and thus increase the likelihood of a successful project in a complex environment. - Highlights: • A systemic Bayesian network based approach for safety risk analysis is developed. • An expert confidence indicator for probability fuzzification is proposed. • Safety risk analysis progress is extended to entire life cycle of risk-prone events. • A typical

Study of methodology for low power/shutdown fire PSA

International Nuclear Information System (INIS)

Yan Zhen; Li Zhaohua; Li Lin; Song Lei

2014-01-01

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

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

International Nuclear Information System (INIS)

Orta Aguilera, R.

1993-01-01

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

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

Science.gov (United States)

2010-10-01

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

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

Science.gov (United States)

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

2016-06-08

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

Forest fire risk assessment-an integrated approach based on multicriteria evaluation.

Science.gov (United States)

Goleiji, Elham; Hosseini, Seyed Mohsen; Khorasani, Nematollah; Monavari, Seyed Masoud

2017-11-06

The present study deals with application of the weighted linear combination method for zoning of forest fire risk in Dohezar and Sehezar region of Mazandaran province in northern Iran. In this study, the effective criteria for fires were identified by the Delphi method, and these included ecological and socioeconomic parameters. In this regard, the first step comprised of digital layers; the required data were provided from databases, related centers, and field data collected in the region. Then, the map of criteria was digitized in a geographic information system, and all criteria and indexes were normalized by fuzzy logic. After that, the geographic information system (GIS 10.3) was integrated with the Weighted Linear Combination and the Analytical Network Process, to produce zonation of the forest fire risk map in the Dohezar and Sehezar region. In order to analyze accuracy of the evaluation, the results obtained from the study were compared to records of former fire incidents in the region. This was done using the Kappa coefficient test and a receiver operating characteristic curve. The model showing estimations for forest fire risk explained that the prepared map had accuracy of 90% determined by the Kappa coefficient test and the value of 0.924 by receiver operating characteristic. These results showed that the prepared map had high accuracy and efficacy.

Risk perceptions and behavioral context: U.S. Forest Service fire management professionals

Science.gov (United States)

Taylor, Jonathan G.; Carpenter, Edwin H.; Cortner, Hanna J.; Cleaves, David A.

1989-01-01

Fire managers from the U.S. Forest Service were surveyed to determine which decision factors most strongly influenced their fire‐risk decisions. Safety, the resources at risk, public opinion, and the reliability of information were important influences on these decisions. This research allowed direct comparison between fire managers’ perceptions of factor importance and how their fire‐risk decisions changed in response to those factors. These risk decisions were highly responsive to changes in context (an escaped wildfire decision versus a prescribed burning decision) as well as to changing factors. The results demonstrate the utility of using scenarios in risk research and the vital importance of context in studying risk‐taking behavior. Research which attempts to remove risk decisions from their real‐world context may well distort the nature of risk‐taking behavior.

Toward a Safety Risk-Based Classification of Unmanned Aircraft

Science.gov (United States)

Torres-Pomales, Wilfredo

2016-01-01

There is a trend of growing interest and demand for greater access of unmanned aircraft (UA) to the National Airspace System (NAS) as the ongoing development of UA technology has created the potential for significant economic benefits. However, the lack of a comprehensive and efficient UA regulatory framework has constrained the number and kinds of UA operations that can be performed. This report presents initial results of a study aimed at defining a safety-risk-based UA classification as a plausible basis for a regulatory framework for UA operating in the NAS. Much of the study up to this point has been at a conceptual high level. The report includes a survey of contextual topics, analysis of safety risk considerations, and initial recommendations for a risk-based approach to safe UA operations in the NAS. The next phase of the study will develop and leverage deeper clarity and insight into practical engineering and regulatory considerations for ensuring that UA operations have an acceptable level of safety.

Developing safety performance functions incorporating reliability-based risk measures.

Science.gov (United States)

Ibrahim, Shewkar El-Bassiouni; Sayed, Tarek

2011-11-01

Current geometric design guides provide deterministic standards where the safety margin of the design output is generally unknown and there is little knowledge of the safety implications of deviating from these standards. Several studies have advocated probabilistic geometric design where reliability analysis can be used to account for the uncertainty in the design parameters and to provide a risk measure of the implication of deviation from design standards. However, there is currently no link between measures of design reliability and the quantification of safety using collision frequency. The analysis presented in this paper attempts to bridge this gap by incorporating a reliability-based quantitative risk measure such as the probability of non-compliance (P(nc)) in safety performance functions (SPFs). Establishing this link will allow admitting reliability-based design into traditional benefit-cost analysis and should lead to a wider application of the reliability technique in road design. The present application is concerned with the design of horizontal curves, where the limit state function is defined in terms of the available (supply) and stopping (demand) sight distances. A comprehensive collision and geometric design database of two-lane rural highways is used to investigate the effect of the probability of non-compliance on safety. The reliability analysis was carried out using the First Order Reliability Method (FORM). Two Negative Binomial (NB) SPFs were developed to compare models with and without the reliability-based risk measures. It was found that models incorporating the P(nc) provided a better fit to the data set than the traditional (without risk) NB SPFs for total, injury and fatality (I+F) and property damage only (PDO) collisions. Copyright © 2011 Elsevier Ltd. All rights reserved.

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

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

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

Fire Risk in MTBF Evaluation for UPS System

Directory of Open Access Journals (Sweden)

Stefano Elia

2016-01-01

Full Text Available The reliability improvement of no-break redundant electrical systems is the first aim of the proposed strategy. The failure of some UPS (Uninterruptible Power Supply system may lead to the fire occurrence. The most used electrical configurations are presented and discussed in the paper. The innovation of the proposed method consists of taking into account the fire risk to improve the accuracy of wiring configuration and component’s failure rate. Thorough research on MTBF (Mean Time Between Failure data has been performed for each wiring component and UPS. The fire risk is taken into account introducing an equivalent fire block in the Reliability Block Diagram scheme; it has an MTBF value calculated form yearly statistics of UPS fire events. The reliability of the most used UPS electrical configurations is evaluated by means of the RBD method. Different electrical systems have been investigated and compared based on MTBF. The importance of fire compartmentation between two or more UPS’ connected in parallel is proved here.

Assessment of the overall fire safety arrangements at nuclear power plants

International Nuclear Information System (INIS)

1996-01-01

The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire safety of nuclear power plants. The publication comprises a detailed checklist of the specific elements to be addressed when assessing the adequacy and effectiveness of the overall fire safety arrangements of 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 outlined in Safety Guide No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, and it is recommended that it be used in conjunction with this Safety Series publication

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

International Nuclear Information System (INIS)

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

2005-03-01

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

Influence of safeguards and fire protection on criticality safety

International Nuclear Information System (INIS)

Six, D.E.

1980-01-01

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

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.

Risk based regulation: a convenient concept for legislation and regulation in the field of technical risks?

International Nuclear Information System (INIS)

Seiler, J.H.

1998-01-01

Legislation and regulation concerning risk activities are traditionally based on deterministic safety measures. This may lead to inefficient results: sometimes the law requires safety measures which are - from an economic viewpoint - not justified because of their poor cost-effectiveness; sometimes it does not require safety measures although they would be very efficient. The risk based regulation approach wants to make the law more efficient and to get more safety at less costs. Legislation and regulation should be based on terms of risk rather than on deterministic rules. Risk should be expressed in quantitative terms and risk regulation should be based on the cost-effectiveness of safety measures. Thus a most efficient (in the sense of the economic analysis of the law) strategy for safety and environmental law could be established. The approach is economically reasonable and theoretically convincing. Its practical implementation however raises a lot of technical and legal questions. The project 'Risk Based Regulation' (1996-1999), sponsored by the Swiss National Fund for Scientific Research, intends to evaluate the practical feasibility of the approach from a technical and a legal view. It contains a general part which describes the risk based regulation approach and its legal and technical questions, case studies which try to practically implement the risk based regulation approach; the case studies are: storage and management of explosives in the army, storage and management of explosives for non-military purposes, safety at work, accident prevention in the non-professional field (mainly road accidents), fire protection, transportation of dangerous goods, waste disposal: traditional waste, waste disposal: radioactive waste, nuclear energy (reactor safety), a synthesis with recommendations for the future legislation and regulation in the field of technical risks. The paper presents the project and its preliminary results. (author)

Instrumentation for mine safety: fire and smoke problems and solutions

International Nuclear Information System (INIS)

Stevens, R.B.

1982-01-01

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

Quantitative risk assessment of continuous liquid spill fires based on spread and burning behaviours

DEFF Research Database (Denmark)

Zhao, Jinlong; Huang, Hong; Li, Yuntao

2017-01-01

Spill fires usually occur during the storage and transportation of hazardous materials, posing a threat to the people and environment in their immediate proximity. In this paper, a classical Quantitative Risk Assessment (QRA) method is used to assess the risk of spill fires. In this method......, the maximum spread area and the steady burning area are introduced as parameters to clearly assess the range of influence of the spill fire. In the calculations, a modified spread model that takes into consideration the burning rate variation is established to calculate the maximum spread area. Furthermore......, large-scale experiments of spill fires on water and a glass sheet were conducted to verify the accuracy and application of the model. The results show that the procedure we developed can be used to quantitatively calculate the risk associated with a continuous spill fire....

Validation of risk-based performance indicators: Safety system function trends

International Nuclear Information System (INIS)

Boccio, J.L.; Vesely, W.E.; Azarm, M.A.; Carbonaro, J.F.; Usher, J.L.; Oden, N.

1989-10-01

This report describes and applies a process for validating a model for a risk-based performance indicator. The purpose of the risk-based indicator evaluated, Safety System Function Trend (SSFT), is to monitor the unavailability of selected safety systems. Interim validation of this indicator is based on three aspects: a theoretical basis, an empirical basis relying on statistical correlations, and case studies employing 25 plant years of historical data collected from five plants for a number of safety systems. Results using the SSFT model are encouraging. Application of the model through case studies dealing with the performance of important safety systems shows that statistically significant trends in, and levels of, system performance can be discerned which thereby can provide leading indications of degrading and/or improving performances. Methods for developing system performance tolerance bounds are discussed and applied to aid in the interpretation of the trends in this risk-based indicator. Some additional characteristics of the SSFT indicator, learned through the data-collection efforts and subsequent data analyses performed, are also discussed. The usefulness and practicality of other data sources for validation purposes are explored. Further validation of this indicator is noted. Also, additional research is underway in developing a more detailed estimator of system unavailability. 9 refs., 18 figs., 5 tabs

Modeling of Electrical Cable Failure in a Dynamic Assessment of Fire Risk

Science.gov (United States)

Bucknor, Matthew D.

Fires at a nuclear power plant are a safety concern because of their potential to defeat the redundant safety features that provide a high level of assurance of the ability to safely shutdown the plant. One of the added complexities of providing protection against fires is the need to determine the likelihood of electrical cable failure which can lead to the loss of the ability to control or spurious actuation of equipment that is required for safe shutdown. A number of plants are now transitioning from their deterministic fire protection programs to a risk-informed, performance based fire protection program according to the requirements of National Fire Protection Association (NFPA) 805. Within a risk-informed framework, credit can be taken for the analysis of fire progression within a fire zone that was not permissible within the deterministic framework of a 10 CFR 50.48 Appendix R safe shutdown analysis. To perform the analyses required for the transition, plants need to be able to demonstrate with some level of assurance that cables related to safe shutdown equipment will not be compromised during postulated fire scenarios. This research contains the development of new cable failure models that have the potential to more accurately predict electrical cable failure in common cable bundle configurations. Methods to determine the thermal properties of the new models from empirical data are presented along with comparisons between the new models and existing techniques used in the nuclear industry today. A Dynamic Event Tree (DET) methodology is also presented which allows for the proper treatment of uncertainties associated with fire brigade intervention and its effects on cable failure analysis. Finally a shielding analysis is performed to determine the effects on the temperature response of a cable bundle that is shielded from a fire source by an intervening object such as another cable tray. The results from the analyses demonstrate that models of similar

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

OpenAIRE

HIMOTO, Keisuke; TANAKA, Takeyoshi

2008-01-01

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

An overview of the fire risk scoping study objectives, approach, findings and follow-on efforts

International Nuclear Information System (INIS)

Nowlen, S.P.; Lambright, J.A.; Nicolette, V.F.; Bohn, M.P.

1989-01-01

The Fire Risk Scoping Study was sponsored by the US Nuclear Regulatory Commission and performed at Sandia National Laboratories. The study was initiated as a result of previous USNRC-sponsored fire research efforts that had identified certain fire risk issues which had not been addressed in previously completed commercial nuclear power plant fire risk analyses. The specific objectives of this study were (1) to review and requantify fire risk scenarios from four fire probabilistic risk assessments (PRAs) in light of updated data bases made available as a result of USNRC sponsored Fire Protection Research Program and updated computer fire modeling capabilities, (2) to identify potentially significant fire risk issues that have not been previously addressed in a fire risk context and to quantify the potential impact of those identified fire risk issues where possible, and (3) to review current fire regulations and plant implementation practices for relevance to the identified unaddressed fire risk issues. 8 refs., 2 tabs

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

Energy Technology Data Exchange (ETDEWEB)

Herms, C D

1982-01-07

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

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

Science.gov (United States)

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

2007-01-01

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

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.

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

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.

Toward risk assessment 2.0: Safety supervisory control and model-based hazard monitoring for risk-informed safety interventions

International Nuclear Information System (INIS)

Favarò, Francesca M.; Saleh, Joseph H.

2016-01-01

Probabilistic Risk Assessment (PRA) is a staple in the engineering risk community, and it has become to some extent synonymous with the entire quantitative risk assessment undertaking. Limitations of PRA continue to occupy researchers, and workarounds are often proposed. After a brief review of this literature, we propose to address some of PRA's limitations by developing a novel framework and analytical tools for model-based system safety, or safety supervisory control, to guide safety interventions and support a dynamic approach to risk assessment and accident prevention. Our work shifts the emphasis from the pervading probabilistic mindset in risk assessment toward the notions of danger indices and hazard temporal contingency. The framework and tools here developed are grounded in Control Theory and make use of the state-space formalism in modeling dynamical systems. We show that the use of state variables enables the definition of metrics for accident escalation, termed hazard levels or danger indices, which measure the “proximity” of the system state to adverse events, and we illustrate the development of such indices. Monitoring of the hazard levels provides diagnostic information to support both on-line and off-line safety interventions. For example, we show how the application of the proposed tools to a rejected takeoff scenario provides new insight to support pilots’ go/no-go decisions. Furthermore, we augment the traditional state-space equations with a hazard equation and use the latter to estimate the times at which critical thresholds for the hazard level are (b)reached. This estimation process provides important prognostic information and produces a proxy for a time-to-accident metric or advance notice for an impending adverse event. The ability to estimate these two hazard coordinates, danger index and time-to-accident, offers many possibilities for informing system control strategies and improving accident prevention and risk mitigation

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

International Nuclear Information System (INIS)

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

2017-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-02-15

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

Solving the Problem of Multiple-Criteria Building Design Decisions with respect to the Fire Safety of Occupants: An Approach Based on Probabilistic Modelling

Directory of Open Access Journals (Sweden)

Egidijus Rytas Vaidogas

2015-01-01

Full Text Available The design of buildings may include a comparison of alternative architectural and structural solutions. They can be developed at different levels of design process. The alternative design solutions are compared and ranked by applying methods of multiple-criteria decision-making (MCDM. Each design is characterised by a number of criteria used in a MCDM problem. The paper discusses how to choose MCDM criteria expressing fire safety related to alternative designs. Probability of a successful evacuation of occupants from a building fire and difference between evacuation time and time to untenable conditions are suggested as the most important criteria related to fire safety. These two criteria are treated as uncertain quantities expressed by probability distributions. Monte Carlo simulation of fire and evacuation processes is natural means for an estimation of these distributions. The presence of uncertain criteria requires applying stochastic MCDM methods for ranking alternative designs. An application of the safety-related criteria is illustrated by an example which analyses three alternative architectural floor plans prepared for a reconstruction of a medical building. A MCDM method based on stochastic simulation is used to solve the example problem.

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

Directory of Open Access Journals (Sweden)

Fatma Lestari

2010-10-01

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

University building safety index measurement using risk and implementation matrix

Science.gov (United States)

Rahman, A.; Arumsari, F.; Maryani, A.

2018-04-01

Many high rise building constructed in several universities in Indonesia. The high-rise building management must provide the safety planning and proper safety equipment in each part of the building. Unfortunately, most of the university in Indonesia have not been applying safety policy yet and less awareness on treating safety facilities. Several fire accidents in university showed that some significant risk should be managed by the building management. This research developed a framework for measuring the high rise building safety index in university The framework is not only assessed the risk magnitude but also designed modular building safety checklist for measuring the safety implementation level. The safety checklist has been developed for 8 types of the university rooms, i.e.: office, classroom, 4 type of laboratories, canteen, and library. University building safety index determined using risk-implementation matrix by measuring the risk magnitude and assessing the safety implementation level. Building Safety Index measurement has been applied in 4 high rise buildings in ITS Campus. The building assessment showed that the rectorate building in secure condition and chemical department building in beware condition. While the library and administration center building was in less secure condition.

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

Science.gov (United States)

2013-03-20

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

Potential fire or explosion risks in reprocessing plants

International Nuclear Information System (INIS)

Lefort, G.

1983-05-01

Installation for reprocessing are large chemical plants handling large quantities of inflammable solvents and products allowing large risk of fire. Further, the chemical process involves the use of oxidizer and reducer agents which can have a very strong chemical activity and by certain circumstances create overpressures or large explosions. This paper shows the principal radioactive consequences we can retain in safety analyses. As an example the combustion phenomenon involved in a solid waste storage silo with irradiated uranium traces is described [fr

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

International Nuclear Information System (INIS)

1996-01-01

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

CONSIDERATIONS ON RISK MANAGEMENT APPLIED TO FOREST FIRES

Directory of Open Access Journals (Sweden)

Ioan Valentin Marcel Posea

2016-07-01

Full Text Available Forest risk and management are ubiquitous in any socio-economic activity. Forestry, more than any other field, is at risk from fire. Consequently, it appears the necessity to implement a fire risk management that could resolve, at least partially, the specific problems. This study attempts to identify the specific stages and processes of forest fire risk management and their content. At the same time, I will try to highlight how a forest fire risk management process planning can be achieved and to present a way of achieving the Plan. I also deem necessary a forest fire risk monitoring and control system that I have built using the Deming cycle.

Motorcoach Fire Safety Analysis.

Science.gov (United States)

2009-07-01

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

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

Directory of Open Access Journals (Sweden)

Trika Pitana

2017-09-01

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

FIRE HAZARDS ANALYSIS - BUSTED BUTTE

International Nuclear Information System (INIS)

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

2001-01-01

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

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

Science.gov (United States)

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

2014-08-01

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

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)

Proposal for the improvement of IRD safety culture based on risk analysis

International Nuclear Information System (INIS)

Aguiar, L.A.; Ferreira, P.R.R.; Silveira, C.S.

2017-01-01

The Safety Culture (SC) is a concept about the relationship of individuals and organizations towards the safety in a specific activity. Any organization that carries out activities with risks has a SC, even at minimum levels. People perceive different types of radiation risks in very different ways, therefore, to identify and to analysis of the possible radiation risks resulting from normal operation or accident conditions is an important issue in order to improve the SC in organization. The main is to present guidelines for the improvement of the safety culture in the Institute of Radiation Protection and Dosimetry - IRD through on risk-based approach. The methodology proposed here is: A) select a division of the IRD for case study; B) assess the level of the 10 culture safety basic elements of the IRD division selected; C) conduct a survey of the hazards and risks associated with the various activities developed by the division; D) reassess the level of the 10 basic elements of CS; And E) analyze the results and correlate the impact of risk knowledge on safety culture improvement. The expected result is improvement the safety and of safety culture by understanding of radiation risks and hazards relating to work and to the working environment; and thus enforce a collective commitment to safety by teams and individuals and raise the safety culture to higher levels. (author)

Proposal for the improvement of IRD safety culture based on risk analysis

Energy Technology Data Exchange (ETDEWEB)

Aguiar, L.A.; Ferreira, P.R.R. [Instituto de Radioproteção e Dosimetria (DIRAD/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Silveira, C.S., E-mail: laguiar@ird.gov.br [Comissão Nacional de Energia Nuclear (DRS/CGMI/CNEN), Rio de Janeiro, RJ (Brazil)

2017-07-01

The Safety Culture (SC) is a concept about the relationship of individuals and organizations towards the safety in a specific activity. Any organization that carries out activities with risks has a SC, even at minimum levels. People perceive different types of radiation risks in very different ways, therefore, to identify and to analysis of the possible radiation risks resulting from normal operation or accident conditions is an important issue in order to improve the SC in organization. The main is to present guidelines for the improvement of the safety culture in the Institute of Radiation Protection and Dosimetry - IRD through on risk-based approach. The methodology proposed here is: A) select a division of the IRD for case study; B) assess the level of the 10 culture safety basic elements of the IRD division selected; C) conduct a survey of the hazards and risks associated with the various activities developed by the division; D) reassess the level of the 10 basic elements of CS; And E) analyze the results and correlate the impact of risk knowledge on safety culture improvement. The expected result is improvement the safety and of safety culture by understanding of radiation risks and hazards relating to work and to the working environment; and thus enforce a collective commitment to safety by teams and individuals and raise the safety culture to higher levels. (author)

Hotel and Motel Fire Safety Project - USFA

Data.gov (United States)

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

A method for mapping fire hazard and risk across multiple scales and its application in fire management

Science.gov (United States)

Robert E. Keane; Stacy A. Drury; Eva C. Karau; Paul F. Hessburg; Keith M. Reynolds

2010-01-01

This paper presents modeling methods for mapping fire hazard and fire risk using a research model called FIREHARM (FIRE Hazard and Risk Model) that computes common measures of fire behavior, fire danger, and fire effects to spatially portray fire hazard over space. FIREHARM can compute a measure of risk associated with the distribution of these measures over time using...

Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

International Nuclear Information System (INIS)

Samanta, P.K.; Kim, I.S.; Vesely, W.E.

1992-01-01

Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation

DOPO-Modified Two-Dimensional Co-Based Metal-Organic Framework: Preparation and Application for Enhancing Fire Safety of Poly(lactic acid).

Science.gov (United States)

Hou, Yanbei; Liu, Longxiang; Qiu, Shuilai; Zhou, Xia; Gui, Zhou; Hu, Yuan

2018-03-07

Co-based metal-organic framework (Co-MOF) nanosheets were successfully synthesized by the organic ligands with Schiff base structure. The laminated structure gives Co-MOF nanosheets a great advantage in the application in the flame retardant field. Meanwhile, -C═N- from Schiff base potentially provides active sites for further modification. In this work, 9,10-dihydro-9-oxa-10-phosphaphenanthrene-10-oxide (DOPO) was used to modify Co-MOF (DOPO@Co-MOF) to further enhance its flame retardant efficiency. It is attractive that DOPO has a synergistic effect with Co-MOF on improving fire safety of poly(lactic acid) (PLA). The obvious decrease in the values of peak heat release (27%), peak smoke production (56%), and total CO yield (20%) confirmed the enhanced fire safety of PLA composites. The possible flame retardant mechanism was proposed based on characterization results. Moreover, the addition of DOPO@Co-MOF had a positive influence on the mechanical performance, including tensile properties and impact resistance. This work designed and synthesized two-dimensional MOFs with active groups. As-prepared Co-MOF with expected structure shows a novel direction of preparing MOFs for flame retardant application.

CCDP evaluation of the fire areas of KSNP using CFAST

International Nuclear Information System (INIS)

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

2005-01-01

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

Safety study of fire protection for nuclear fuel cycle facility

International Nuclear Information System (INIS)

2013-01-01

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

Fire safety in the atomic age

International Nuclear Information System (INIS)

Whitman, L.E.

1980-01-01

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

The role of hazard- and risk-based approaches in ensuring food safety

DEFF Research Database (Denmark)

Barlow, Susan M.; Boobis, Alan R.; Bridges, Jim

2015-01-01

action. Risk-based approaches allow consideration of exposure in assessing whether there may be unacceptable risks to health. Scope and approach The advantages and disadvantages of hazard- and risk-based approaches for ensuring the safety of food chemicals, allergens, ingredients and microorganisms were...

Fire safety in atomic power plants

International Nuclear Information System (INIS)

Kench, R.L.; British Insurance

1988-01-01

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

Fire and explosion safety in the petroleum sector

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

The conference has 13 presentations in topics on LNG projects nationally and internationally, simulations of gas dispersion due to LNG discharges, transports of pressurized natural gas, technological aspects of fire protection and combat equipment, safety aspects of offshore installations and transportation systems, offshore platform and transportation systems design and various examples of safety design and management. Some experiences within safety engineering in the petroleum exploitation are included.

Analysis of fire risk in French pressurized water reactors

International Nuclear Information System (INIS)

Savornin; Brauns; Deletre; Laborde; Malet; Haller; Vachon; Rebuffat

1988-10-01

In a nuclear power station, as in other industrial Installations, fire can be the cause of considerable damage involving loss of capital for the operator along with loss of availability for electrical energy production which must be made up for at a later date. But to make matters worse, fire could also compromise safety of the installation, in order words it could be the cause of an accident involving discharge of radioactivity into the environment, if special precautions were not taken. Clearly then, in view of installation availability and of the very high level of safety which must be guaranteed, fire protection becomes an issue of the utmost importance. Although, practically speaking, fire protection is a composite issue affecting availability as much as installation safety, it is the latter subject which we intend to discuss in our paper

Modeling of compartment fire

International Nuclear Information System (INIS)

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

2011-01-01

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

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

Spacecraft Fire Safety 1956 to 1999: An Annotated Bibliography

Science.gov (United States)

Friedman, Robert; Ruff, Gary A.

2013-01-01

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

Fire and explosion security in the petroleum sector

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The conference has 12 presentations on topics regarding fire fighting, explosions and development scenarios, safety and security aspects, management of safety issues and measures and preparedness. Some accidents and fires are discussed. Some important problems with LNG with respects to plants, transport, fires and risk assessment are presented.

Managing the risks of risk management on large fires

Science.gov (United States)

Donald G. MacGregor; Armando González-Cabán

2013-01-01

Large fires pose risks to a number of important values, including the ecology, property and the lives of incident responders. A relatively unstudied aspect of fire management is the risks to which incident managers are exposed due to organizational and sociopolitical factors that put them in a position of, for example, potential liability or degradation of their image...

Risk Classification and Risk-based Safety and Mission Assurance

Science.gov (United States)

Leitner, Jesse A.

2014-01-01

Recent activities to revamp and emphasize the need to streamline processes and activities for Class D missions across the agency have led to various interpretations of Class D, including the lumping of a variety of low-cost projects into Class D. Sometimes terms such as Class D minus are used. In this presentation, mission risk classifications will be traced to official requirements and definitions as a measure to ensure that projects and programs align with the guidance and requirements that are commensurate for their defined risk posture. As part of this, the full suite of risk classifications, formal and informal will be defined, followed by an introduction to the new GPR 8705.4 that is currently under review.GPR 8705.4 lays out guidance for the mission success activities performed at the Classes A-D for NPR 7120.5 projects as well as for projects not under NPR 7120.5. Furthermore, the trends in stepping from Class A into higher risk posture classifications will be discussed. The talk will conclude with a discussion about risk-based safety and mission assuranceat GSFC.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

William E. Kastenberg; Edward Blandford; Lance Kim

2009-03-31

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

International Nuclear Information System (INIS)

Kastenberg, William E.; Blandford, Edward; Kim, Lance

2009-01-01

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public

Safety analysis of the existing 804 and 845 firing facilities

International Nuclear Information System (INIS)

Odell, B.N.

1986-01-01

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

Modeling issues in nuclear plant fire risk analysis

International Nuclear Information System (INIS)

Siu, N.

1989-01-01

This paper discusses various issues associated with current models for analyzing the risk due to fires in nuclear power plants. Particular emphasis is placed on the fire growth and suppression models, these being unique to the fire portion of the overall risk analysis. Potentially significant modeling improvements are identified; also discussed are a variety of modeling issues where improvements will help the credibility of the analysis, without necessarily changing the computed risk significantly. The mechanistic modeling of fire initiation is identified as a particularly promising improvement for reducing the uncertainties in the predicted risk. 17 refs., 5 figs. 2 tabs

Strengthening air traffic safety management by moving from outcome-based towards risk-based evaluation of runway incursions

International Nuclear Information System (INIS)

Stroeve, Sybert H.; Som, Pradip; Doorn, Bas A. van; Bakker, G.J.

2016-01-01

Current safety management of aerodrome operations uses judgements of severity categories to evaluate runway incursions. Incident data show a small minority of severe incursions and a large majority of less severe incursions. We show that these severity judgements are mainly based upon the outcomes of runway incursions, in particular on the closest distances attained. As such, the severity-based evaluation leads to coincidental safety management feedback, wherein causes and risk implications of runway incursions are not well considered. In this paper we present a new framework for the evaluation of runway incursions, which effectively uses all runway incursions, which judges same types of causes similarly, and which structures causes and risk implications. The framework is based on risks of scenarios associated with the initiation of runway incursions. As a basis an inventory of scenarios is provided, which can represent almost all runway incursions involving a conflict with an aircraft. A main step in the framework is the assessment of the conditional probability of a collision given a runway incursion scenario. This can be effectively achieved for large sets of scenarios by agent-based dynamic risk modelling. The results provide detailed feedback on risks of runway incursion scenarios, thus enabling effective safety management. - Highlights: • Current evaluation of runway incursions is primarily based on their outcomes. • A new framework assesses collision risk given initiation of runway incursions. • Agent-based dynamic risk modelling can evaluate the risks of many scenarios. • A developed scenario inventory can represent almost all runway incursions. • The framework provides detailed feedback to safety management.

[Occupational risks among public safety and security forces].

Science.gov (United States)

Candura, S M; Verni, P; Minelli, C M; Rosso, G L; Cappelli, M I; Strambi, S; Martellosio, V

2006-01-01

The present paper tries to identify the occupational risk factors (physical, chemical, biological, psychological), variable depending on jobs and tasks, to which the heterogeneous public safety/security workers are exposed. The fight against criminality and public order maintenance imply (sometimes fatal) traumatic risks, and expose to psychophysical and sensorial tiring, unfavourable macro- and microclimatic conditions, the risk of baropathy (air navigation, underwater activities), noise (generated by firearms and several other sources), vibrations and shakings (automatic weapons, transport vehicles), the risk of electric injury, ionizing (X and gamma rays) and non-inonizing (ultraviolet rays, microwaves and radiofrequencies, electromagnetic fields) radiations. Chemical hazards include carbon monoxide and other combustion products (fires, urban traffic), substances released in chemical accidents, tear gases, lead (firing grounds, metal works, environmental pollution), solvents, lubrificants and cutting oils (mechanic repair and maintenance), laboratory materials and reagents, irritant and/or sensitizing agents contained in gloves. The main biological risks are tetanus, blood-borne diseases (viral hepatitis, AIDS), aerogenous diseases (e.g., tuberculosis, Legionnaire's disease, epidemic cerebrospinal meningitis), dog- or horse-transmitted zoonosis. Finally, emotional, psychosomatic and behavioural stress-related disorders (e.g., burn-out syndrome, post-traumatic stress disorder) are typically frequent. The presence of numerous and diversified hazards among public safety/security forces imposes the adoption of occupational medicine measures, including risk assessment, health education, technical and environmental prevention, personal protective devices, sanitary surveillance and biological monitoring, clinical interventions (diagnosis, therapy and rehabilitation of occupational accidents and illnesses), prompt medico-legal evaluation of occupational

Topology optimization for simplified structural fire safety

DEFF Research Database (Denmark)

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

2016-01-01

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

75 FR 40845 - Preventing Deaths and Injuries of Fire Fighters Using Risk Management Principles at Structure Fires

Science.gov (United States)

2010-07-14

... NIOSH 141-A] Preventing Deaths and Injuries of Fire Fighters Using Risk Management Principles at... publication entitled ``Preventing Deaths and Injuries of Fire Fighters Using Risk Management Principles at... fires in unoccupied structures to using established risk management principles at all structure fires...

Improved Methods for Fire Risk Assessment in Low-Income and Informal Settlements

Directory of Open Access Journals (Sweden)

John Twigg

2017-02-01

Full Text Available Fires cause over 300,000 deaths annually worldwide and leave millions more with permanent injuries: some 95% of these deaths are in low- and middle-income countries. Burn injury risk is strongly associated with low-income and informal (or slum settlements, which are growing rapidly in an urbanising world. Fire policy and mitigation strategies in poorer countries are constrained by inadequate data on incidence, impacts, and causes, which is mainly due to a lack of capacity and resources for data collection, analysis, and modelling. As a first step towards overcoming such challenges, this project reviewed the literature on the subject to assess the potential of a range of methods and tools for identifying, assessing, and addressing fire risk in low-income and informal settlements; the process was supported by an expert workshop at University College London in May 2016. We suggest that community-based risk and vulnerability assessment methods, which are widely used in disaster risk reduction, could be adapted to urban fire risk assessment, and could be enhanced by advances in crowdsourcing and citizen science for geospatial data creation and collection. To assist urban planners, emergency managers, and community organisations who are working in resource-constrained settings to identify and assess relevant fire risk factors, we also suggest an improved analytical framework based on the Haddon Matrix.

Improved Methods for Fire Risk Assessment in Low-Income and Informal Settlements.

Science.gov (United States)

Twigg, John; Christie, Nicola; Haworth, James; Osuteye, Emmanuel; Skarlatidou, Artemis

2017-02-01

Fires cause over 300,000 deaths annually worldwide and leave millions more with permanent injuries: some 95% of these deaths are in low- and middle-income countries. Burn injury risk is strongly associated with low-income and informal (or slum) settlements, which are growing rapidly in an urbanising world. Fire policy and mitigation strategies in poorer countries are constrained by inadequate data on incidence, impacts, and causes, which is mainly due to a lack of capacity and resources for data collection, analysis, and modelling. As a first step towards overcoming such challenges, this project reviewed the literature on the subject to assess the potential of a range of methods and tools for identifying, assessing, and addressing fire risk in low-income and informal settlements; the process was supported by an expert workshop at University College London in May 2016. We suggest that community-based risk and vulnerability assessment methods, which are widely used in disaster risk reduction, could be adapted to urban fire risk assessment, and could be enhanced by advances in crowdsourcing and citizen science for geospatial data creation and collection. To assist urban planners, emergency managers, and community organisations who are working in resource-constrained settings to identify and assess relevant fire risk factors, we also suggest an improved analytical framework based on the Haddon Matrix.

EFFECTS OF FIRE FUMES ON ALMOND SAFETY AND QUALITY

Directory of Open Access Journals (Sweden)

Amanda Ramírez-Gandolfo

2011-08-01

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

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

Science.gov (United States)

Greene, Michael A

2012-06-01

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

Risk assessment study of fire following earthquake: a case study of petrochemical enterprises in China

Science.gov (United States)

Li, J.; Wang, Y.; Chen, H.; Lin, L.

2013-04-01

After an earthquake, the fire risk of petrochemistry enterprises is higher than that of other enterprises as it involves production processes with inflammable and explosive characteristics. Using Chinese petrochemical enterprises as the research object, this paper uses a literature review and case summaries to study, amongst others, the classification of petrochemical enterprises, the proportion of daily fires, and fire loss ratio. This paper builds a fire following earthquake risk assessment model of petrochemical enterprises based on a previous earthquake fire hazard model, and the earthquake loss prediction assessment method, calculates the expected loss of the fire following earthquake in various counties and draws a risk map. Moreover, this research identifies high-risk areas, concentrating on the Beijing-Tianjin-Tangshan region, and Shandong, Jiangsu, and Zhejiang provinces. Differences in enterprise type produce different levels and distribution of petrochemical enterprises earthquake fire risk. Furthermore, areas at high risk of post-earthquake fires and with low levels of seismic fortification require extra attention to ensure appropriate mechanisms are in place.

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

Science.gov (United States)

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

2016-01-01

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

The role of hazard- and risk-based approaches in ensuring food safety

OpenAIRE

Barlow, Susan M.; Boobis, Alan R.; Bridges, Jim; Cockburn, Andrew; Dekant, Wolfgang; Hepburn, Paul; Houben, Geert F.; König, Jürgen; Nauta, Maarten; Schuermans, Jeroen; Bánáti, Diána

2015-01-01

BackgroundFood legislation in the European Union and elsewhere includes both hazard- and risk-based approaches for ensuring safety. In hazard-based approaches, simply the presence of a potentially harmful agent at a detectable level in food is used as a basis for legislation and/or risk management action. Risk-based approaches allow consideration of exposure in assessing whether there may be unacceptable risks to health.Scope and approachThe advantages and disadvantages of hazard- and risk-ba...

A Study on the Estimation Method of Risk Based Area for Jetty Safety Monitoring

Directory of Open Access Journals (Sweden)

Byeong-Wook Nam

2015-09-01

Full Text Available Recently, the importance of safety-monitoring systems was highlighted by the unprecedented collision between a ship and a jetty in Yeosu. Accordingly, in this study, we introduce the concept of risk based area and develop a methodology for a jetty safety-monitoring system. By calculating the risk based areas for a ship and a jetty, the risk of collision was evaluated. To calculate the risk based areas, we employed an automatic identification system for the ship, stopping-distance equations, and the regulation velocity near the jetty. In this paper, we suggest a risk calculation method for jetty safety monitoring that can determine the collision probability in real time and predict collisions using the amount of overlap between the two calculated risk based areas. A test was conducted at a jetty control center at GS Caltex, and the effectiveness of the proposed risk calculation method was verified. The method is currently applied to the jetty-monitoring system at GS Caltex in Yeosu for the prevention of collisions.

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

Science.gov (United States)

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

2017-02-01

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

Applying Multi-Criteria Analysis Methods for Fire Risk Assessment

Directory of Open Access Journals (Sweden)

Pushkina Julia

2015-11-01

Full Text Available The aim of this paper is to prove the application of multi-criteria analysis methods for optimisation of fire risk identification and assessment process. The object of this research is fire risk and risk assessment. The subject of the research is studying the application of analytic hierarchy process for modelling and influence assessment of various fire risk factors. Results of research conducted by the authors can be used by insurance companies to perform the detailed assessment of fire risks on the object and to calculate a risk extra charge to an insurance premium; by the state supervisory institutions to determine the compliance of a condition of object with requirements of regulations; by real state owners and investors to carry out actions for decrease in degree of fire risks and minimisation of possible losses.

Risk-based evaluation tool for safety-related maintenance involving scaffolding

International Nuclear Information System (INIS)

Stevens, C.; Azizi, M.; Massman, M.

1988-01-01

The US Nuclear Regulatory Commission (NRC) has expressed a general concern that transient materials in and around safety systems at nuclear power plants represent a seismic safety hazard to the plant, in particular, the uncontrolled use of scaffolding during maintenance activities. Currently, most plants perform a seismic safety analysis for all uses of scaffolding near safety-related equipment to determine appropriate tie-down locations, scaffolding reinforcements, etc. This is both time-consuming and, for the most part, unnecessary. A workable engineering solution based on risk analysis techniques has been developed and is being used at the Palo Verde nuclear generating station (PVNGS)

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

Directory of Open Access Journals (Sweden)

Kolaitis Dionysios I.

2013-11-01

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

Fire risk analysis in ITER tritium building

International Nuclear Information System (INIS)

Lignini, Franck; Uzan-Elbez, Joelle; Girard, Jean-Philippe; Porfiri, Maria Teresa; Rodriguez-Rodrigo, Lina

2005-01-01

Events, such as fire, have been considered in ITER documentation of low probability and a general approach has been defined in [Technical basis for the ITER final design, EDA Documentation Series I, No. 22, IAEA, Vienna, 2001] to be developed later for the ITER specific site. It was said that 'these hazards will be treated according to the industrial safety regulations and practices of the host country'. In the framework of studies for the European ITER site in Cadarache, an assessment of fire hazard has been done in order to ensure compliance with French safety requirements. In this report, a summary of existing laws is presented and an example of the deterministic approach to be followed for the preliminary safety report (PSR) is given on the analysis of tritium building design

Evaluation model for safety capacity of chemical industrial park based on acceptable regional risk

Institute of Scientific and Technical Information of China (English)

Guohua Chen; Shukun Wang; Xiaoqun Tan

2015-01-01

The paper defines the Safety Capacity of Chemical Industrial Park (SCCIP) from the perspective of acceptable regional risk. For the purpose of exploring the evaluation model for the SCCIP, a method based on quantitative risk assessment was adopted for evaluating transport risk and to confirm reasonable safety transport capacity of chemical industrial park, and then by combining with the safety storage capacity, a SCCIP evaluation model was put forward. The SCCIP was decided by the smaller one between the largest safety storage capacity and the maximum safety transport capacity, or else, the regional risk of the park will exceed the acceptable level. The developed method was applied to a chemical industrial park in Guangdong province to obtain the maximum safety transport capacity and the SCCIP. The results can be realized in the regional risk control of the park effectively.

Upgrading of fire safety in Indian nuclear power plants

International Nuclear Information System (INIS)

Agarwal, N.K.

1998-01-01

Indian nuclear power programme started with the installation of 2 nos. of Boiling Water Reactor (BWR) at Tarapur (TAPS I and II) of 210 MWe each commissioned in the year 1996. The Pressurized Heavy Water Reactor (PHWR) programme in the country started with the installation of 2x220 MWe stations at Rawatbhatta near Kota (RAPS I and II) in the State of Rajasthan in the sixties. At the present moment, the country has 10 stations in operation. Construction is going on for 4 more units of 220 MWe where as work on two more 500 MWe units is going to start soon. Fire safety systems for the earlier units were engineered as per the state-of-art knowledge available then. The need for review of fire protection systems in the Indian nuclear power plants has also been felt since long almost after Brown's Ferry fire in 1975 itself. Task forces consisting of fire experts, systems design engineers, O and M personnel as well as the Fire Protection engineers at the plant were constituted for each plant to review the existing fire safety provisions in details and highlight the upgradation needed for meeting the latest requirements as per the national as well as international practices. The recommendations made by three such task forces for the three plants are proposed to be reviewed in this paper. The paper also highlights the recommendations to be implemented immediately as well as on long-term basis over a period of time

Surface Fire Hazards Analysis Technical Report-Constructor Facilities

International Nuclear Information System (INIS)

Flye, R.E.

2000-01-01

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

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

International Nuclear Information System (INIS)

Wanless, J.

1985-11-01

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

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

The Angra 1 fire PRA project

International Nuclear Information System (INIS)

Silva, Luiz E. Massiere de C.; Kassawara, Robert

2009-01-01

The Angra 1 Fire PRA (Probabilistic Risk Assessment) is under development by ELETRONUCLEAR jointly with EPRI (Electric Power Research Institute). The project was started January of 2007 and it is foreseen to be finished in the middle of the next year. The study is being conducted according to the newest methodology developed by EPRI and NRC/RES (U.S. Nuclear Regulatory Commission - Office of Regulatory Research) published in 2005 as Fire PRA Methodology for Nuclear Power Facilities (NUREG/CR-6850 or EPRI TR-1011989) [1]. Starting from the Internal Events Angra 1 PRA model Level 1 the project aims to be a comprehensive plant-specific fire analysis to identify the possible consequences of a fire in the plant vital areas which threaten the integrity of systems relevant to the safety, challenging the safety functions and representing a risk of accident that can lead to a core damage. The main tasks include the plant boundary and partitioning, the fire PRA component selection and the identification of the possible fire scenarios (ignition, propagation, detection, extinction and hazards) considering human failure events to establish the fire-induced risk model for quantification of the risk for nuclear core damage taking into account the plant design and its fire protection resources. This work presents a general discussion on the methodology applied to the completed steps of the project. (author)

Setting priorities for private land conservation in fire-prone landscapes: Are fire risk reduction and biodiversity conservation competing or compatible objectives?

Science.gov (United States)

Syphard, Alexandra D.; Butsic, Van; Bar-Massada, Avi; Keeley, Jon E.; Tracey, Jeff A.; Fisher, Robert N.

2016-01-01

Although wildfire plays an important role in maintaining biodiversity in many ecosystems, fire management to protect human assets is often carried out by different agencies than those tasked for conserving biodiversity. In fact, fire risk reduction and biodiversity conservation are often viewed as competing objectives. Here we explored the role of management through private land conservation and asked whether we could identify private land acquisition strategies that fulfill the mutual objectives of biodiversity conservation and fire risk reduction, or whether the maximization of one objective comes at a detriment to the other. Using a fixed budget and number of homes slated for development, we simulated 20 years of housing growth under alternative conservation selection strategies, and then projected the mean risk of fires destroying structures and the area and configuration of important habitat types in San Diego County, California, USA. We found clear differences in both fire risk projections and biodiversity impacts based on the way conservation lands are prioritized for selection, but these differences were split between two distinct groupings. If no conservation lands were purchased, or if purchases were prioritized based on cost or likelihood of development, both the projected fire risk and biodiversity impacts were much higher than if conservation lands were purchased in areas with high fire hazard or high species richness. Thus, conserving land focused on either of the two objectives resulted in nearly equivalent mutual benefits for both. These benefits not only resulted from preventing development in sensitive areas, but they were also due to the different housing patterns and arrangements that occurred as development was displaced from those areas. Although biodiversity conflicts may still arise using other fire management strategies, this study shows that mutual objectives can be attained through land-use planning in this region. These results likely

Fire Risk Assessment: A Systematic Review of the Methodology and Functional Areas

Directory of Open Access Journals (Sweden)

Parisa Moshashaei

2017-01-01

Full Text Available Fire is a physical and social phenomenon that affects both individuals and the environment. Fire risk assessment is a critical part of a fire prevention program. In this process, the fire risk associated with the possibility of occurrence and severity of damage resulting from the fire is estimated and calculated. In this paper, a classification scheme and a systematic literature review are presented in order to classify and interpret the current researches on fire risk assessment methodologies and applications. Based on the scheme, 93 scholarly papers from 13 journals are categorized into application areas and other categories. The application areas include the papers on the topics of environmental impact, production and industry, transportation, buildings, power industry, oil and gas industry, urban fires and other topics. Scholarly papers are also classified by (1 year of publication, (2 journal of publication, (3 year of publication and application areas and (4 authors’ nationality. The survey results show that the largest number of papers was published during the period 2010-2012 with 31 (33.33%, the most of the studies have been carried out on environmental impact (47.31%, the journal of Forest Ecology and Management had the highest percentage of articles with 26.88%. It is hoped that the paper can meet the needs of researchers for easy references of fire risk assessment methodologies and applications. Therefore, this work would be able to provide useful insights into the anatomy of the fire-risk assessment methods, and suggest academic researchers and experts a framework for future attempts and researches.

Safety demonstration test on solvent fire in fuel reprocessing plant

International Nuclear Information System (INIS)

Nishio, Gunji; Hashimoto, Kazuichiro

1989-03-01

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

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.

The Research on Safety Management Information System of Railway Passenger Based on Risk Management Theory

Science.gov (United States)

Zhu, Wenmin; Jia, Yuanhua

2018-01-01

Based on the risk management theory and the PDCA cycle model, requirements of the railway passenger transport safety production is analyzed, and the establishment of the security risk assessment team is proposed to manage risk by FTA with Delphi from both qualitative and quantitative aspects. The safety production committee is also established to accomplish performance appraisal, which is for further ensuring the correctness of risk management results, optimizing the safety management business processes and improving risk management capabilities. The basic framework and risk information database of risk management information system of railway passenger transport safety are designed by Ajax, Web Services and SQL technologies. The system realizes functions about risk management, performance appraisal and data management, and provides an efficient and convenient information management platform for railway passenger safety manager.

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

Behaviour of electrical cables under fire conditions

International Nuclear Information System (INIS)

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

2002-01-01

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

The role of hazard- and risk-based approaches in ensuring food safety

NARCIS (Netherlands)

Barlow, S.M.; Boobis, A.R.; Bridges, J.; Cockburn, A.; Dekant, W.; Hepburn, P.; Houben, G.F.; König, J.; Nauta, M.J.; Schuermans, J.; Bánáti, D.

2015-01-01

Background: Food legislation in the European Union and elsewhere includes both hazard- and risk-based approaches for ensuring safety. In hazard-based approaches, simply the presence of a potentially harmful agent at a detectable level in food is used as a basis for legislation and/or risk management

Application of fire models for risk analysis in french nuclear power plants

International Nuclear Information System (INIS)

Brauns, P.

1989-04-01

Numerical simulations of compartment fires have been carried out in the French 900 MW and 1 300 MW nuclear power plants, to obtain quantitative data about this particular kind of risk: characteristic spreading times from one redundant electrical train to the other one, behaviour of important electrical components... The main stages of both studies were the following: selection of rooms, the location or function of which are essential for the plant safety in case of fire, on-site inspections to collect information about these rooms (amount of fuel, openings...), definition of fire scenarios, improvement of the fire model VESTA-PLUS, and, finally calculations using this computer code. The simulations have shown two major trends: i) the spreading times, without taking into account any external intervention, are always greater than half an hour, and ii) the specific design of the 1 300 MW power plants generally prevents one of the redundant train from being damaged due to a fire occurring in a room containing the other one. Examples of typical results obtained are given, showing the capability of application of the improved fire model to complex problems

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

Chapter 4. Predicting post-fire erosion and sedimentation risk on a landscape scale

Science.gov (United States)

MacDonald, L.H.; Sampson, R.; Brady, D.; Juarros, L.; Martin, Deborah

2000-01-01

Historic fire suppression efforts have increased the likelihood of large wildfires in much of the western U.S. Post-fire soil erosion and sedimentation risks are important concerns to resource managers. In this paper we develop and apply procedures to predict post-fire erosion and sedimentation risks on a pixel-, catchment-, and landscape-scale in central and western Colorado.Our model for predicting post-fire surface erosion risk is conceptually similar to the Revised Universal Soil Loss Equation (RUSLE). One key addition is the incorporation of a hydrophobicity risk index (HY-RISK) based on vegetation type, predicted fire severity, and soil texture. Post-fire surface erosion risk was assessed for each 90-m pixel by combining HYRISK, slope, soil erodibility, and a factor representing the likely increase in soil wetness due to removal of the vegetation. Sedimentation risk was a simple function of stream gradient. Composite surface erosion and sedimentation risk indices were calculated and compared across the 72 catchments in the study area.When evaluated on a catchment scale, two-thirds of the catchments had relatively little post-fire erosion risk. Steeper catchments with higher fuel loadings typically had the highest post-fire surface erosion risk. These were generally located along the major north-south mountain chains and, to a lesser extent, in west-central Colorado. Sedimentation risks were usually highest in the eastern part of the study area where a higher proportion of streams had lower gradients. While data to validate the predicted erosion and sedimentation risks are lacking, the results appear reasonable and are consistent with our limited field observations. The models and analytic procedures can be readily adapted to other locations and should provide useful tools for planning and management at both the catchment and landscape scale.

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

Science.gov (United States)

2010-04-01

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

Fire safety in nuclear power stations

International Nuclear Information System (INIS)

Kench, R.L.

1988-01-01

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

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

Risk-informed, performance-based safety-security interface

International Nuclear Information System (INIS)

Mrowca, B.; Eltawila, F.

2012-01-01

Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

The state of art of internal fire PSA in nuclear power plant

International Nuclear Information System (INIS)

Yu Xinli; Zhao Bo; Zheng Xiangyang

2010-01-01

The operational experiences of nuclear power plants (NPPs) show that the internal fires challenge effectively the nuclear safety of NPPs. Thus, the authorities having jurisdiction in the world have enhanced the supervision on fire safety in NPPs, asking the licensees to perform fire hazard analysis and evaluate the fire risk. This article mainly describes the state of art of internal fire probabilistic safety assessment (PSA) in the world, and compares the main methods and standards for internal fire PSA. (authors)

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

International Nuclear Information System (INIS)

Yamaguchi, Akira; Tajima, Yuji

2003-01-01

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

A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

International Nuclear Information System (INIS)

Brumburgh, G.

1994-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

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

Deriving forest fire ignition risk with biogeochemical process modelling.

Science.gov (United States)

Eastaugh, C S; Hasenauer, H

2014-05-01

Climate impacts the growth of trees and also affects disturbance regimes such as wildfire frequency. The European Alps have warmed considerably over the past half-century, but incomplete records make it difficult to definitively link alpine wildfire to climate change. Complicating this is the influence of forest composition and fuel loading on fire ignition risk, which is not considered by purely meteorological risk indices. Biogeochemical forest growth models track several variables that may be used as proxies for fire ignition risk. This study assesses the usefulness of the ecophysiological model BIOME-BGC's 'soil water' and 'labile litter carbon' variables in predicting fire ignition. A brief application case examines historic fire occurrence trends over pre-defined regions of Austria from 1960 to 2008. Results show that summer fire ignition risk is largely a function of low soil moisture, while winter fire ignitions are linked to the mass of volatile litter and atmospheric dryness.

Deriving forest fire ignition risk with biogeochemical process modelling☆

Science.gov (United States)

Eastaugh, C.S.; Hasenauer, H.

2014-01-01

Climate impacts the growth of trees and also affects disturbance regimes such as wildfire frequency. The European Alps have warmed considerably over the past half-century, but incomplete records make it difficult to definitively link alpine wildfire to climate change. Complicating this is the influence of forest composition and fuel loading on fire ignition risk, which is not considered by purely meteorological risk indices. Biogeochemical forest growth models track several variables that may be used as proxies for fire ignition risk. This study assesses the usefulness of the ecophysiological model BIOME-BGC's ‘soil water’ and ‘labile litter carbon’ variables in predicting fire ignition. A brief application case examines historic fire occurrence trends over pre-defined regions of Austria from 1960 to 2008. Results show that summer fire ignition risk is largely a function of low soil moisture, while winter fire ignitions are linked to the mass of volatile litter and atmospheric dryness. PMID:26109905

Lessons learned from IAEA fire safety missions

International Nuclear Information System (INIS)

Lee, S.P.

1998-01-01

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

Fire Safety During the Holiday Season | Poster

Science.gov (United States)

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

Risk assessment study of fire following an earthquake: a case study of petrochemical enterprises in China

Science.gov (United States)

Li, J.; Wang, Y.; Chen, H.; Lin, L.

2014-04-01

After an earthquake, the fire risk of petrochemical enterprises is higher than that of other enterprises as it involves production processes with inflammable and explosive characteristics. Using Chinese petrochemical enterprises as the research object, this paper uses a literature review and case summaries to study, amongst others, the classification of petrochemical enterprises, the proportion of daily fires, and fire loss ratio. This paper builds a fire following an earthquake risk assessment model of petrochemical enterprises based on a previous earthquake fire hazard model, and the earthquake loss prediction assessment method, calculates the expected loss of the fire following an earthquake in various counties and draws a risk map. Moreover, this research identifies high-risk areas, concentrating on the Beijing-Tianjin-Tangshan region, and Shandong, Jiangsu, and Zhejiang provinces. Differences in enterprise type produce different levels and distribution of petrochemical enterprise earthquake fire risk. Furthermore, areas at high risk of post-earthquake fires and with low levels of seismic fortification require extra attention to ensure appropriate mechanisms are in place.

Hazard Identification and Risk Assessment in Water Treatment Plant considering Environmental Health and Safety Practice

Directory of Open Access Journals (Sweden)

Falakh Fajrul

2018-01-01

Full Text Available Water Treatment Plant (WTP is an important infrastructure to ensure human health and the environment. In its development, aspects of environmental safety and health are of concern. This paper case study was conducted at the Water Treatment Plant Company in Semarang, Central Java, Indonesia. Hazard identification and risk assessment is one part of the occupational safety and health program at the risk management stage. The purpose of this study was to identify potential hazards using hazard identification methods and risk assessment methods. Risk assessment is done using criteria of severity and probability of accident. The results obtained from this risk assessment are 22 potential hazards present in the water purification process. Extreme categories that exist in the risk assessment are leakage of chlorine and industrial fires. Chlorine and fire leakage gets the highest value because its impact threatens many things, such as industrial disasters that could endanger human life and the environment. Control measures undertaken to avoid potential hazards are to apply the use of personal protective equipment, but management will also be better managed in accordance with hazard control hazards, occupational safety and health programs such as issuing work permits, emergency response training is required, Very useful in overcoming potential hazards that have been determined.

Hazard Identification and Risk Assessment in Water Treatment Plant considering Environmental Health and Safety Practice

Science.gov (United States)

Falakh, Fajrul; Setiani, Onny

2018-02-01

Water Treatment Plant (WTP) is an important infrastructure to ensure human health and the environment. In its development, aspects of environmental safety and health are of concern. This paper case study was conducted at the Water Treatment Plant Company in Semarang, Central Java, Indonesia. Hazard identification and risk assessment is one part of the occupational safety and health program at the risk management stage. The purpose of this study was to identify potential hazards using hazard identification methods and risk assessment methods. Risk assessment is done using criteria of severity and probability of accident. The results obtained from this risk assessment are 22 potential hazards present in the water purification process. Extreme categories that exist in the risk assessment are leakage of chlorine and industrial fires. Chlorine and fire leakage gets the highest value because its impact threatens many things, such as industrial disasters that could endanger human life and the environment. Control measures undertaken to avoid potential hazards are to apply the use of personal protective equipment, but management will also be better managed in accordance with hazard control hazards, occupational safety and health programs such as issuing work permits, emergency response training is required, Very useful in overcoming potential hazards that have been determined.

Fire safety case study of a railway tunnel: Smoke evacuation

Directory of Open Access Journals (Sweden)

van Maele Karim

2007-01-01

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

Payload Safety: Risk and Characteristic-Based Control of Engineered Nanomaterials

Science.gov (United States)

Abou, Seraphin Chally; Saad, Maarouf

2013-09-01

In the last decade progress has been made to assist organizations that are developing payloads intended for flight on the International Space Station (ISS) and/or Space Shuttle. Collaboration programs for comprehensive risk assessment have been initiated between the U.S. and the European Union to generate requirements and data needed to comply with payloads safety and to perform risk assessment and controls guidance. Yet, substantial research gaps remain, as do challenges in the translation of these research findings to control for exposure to nanoscale material payloads, and the health effects. Since nanomaterial structures are different from traditional molecules, some standard material properties can change at size of 50nm or less. Changes in material properties at this scale challenge our understanding of hazards posed by nanomaterial payloads in the ISS realistic exposure conditions, and our ability to anticipate, evaluate, and control potential health issues, and safety. The research question addressed in this framework is: what kind of descriptors can be developed for nanomaterial payloads risks assessment? Methods proposed incorporate elements of characteristic- based risk an alysis: (1) to enable characterization of anthropogenic nanomaterials which can result in incidental from natural nanoparticles; and (2) to better understand safety attributes in terms of human health impacts from exposure to varying types of engineered nanomaterials.

Behaviour of French electrical cables under fire conditions

Energy Technology Data Exchange (ETDEWEB)

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

2001-12-01

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

Modeling fire susceptibility to delineate wildland-urban interface for municipal-scale fire risk management.

Science.gov (United States)

Whitman, Ellen; Rapaport, Eric; Sherren, Kate

2013-12-01

The wildland-urban interface (WUI) is the region where development meets and intermingles with wildlands. The WUI has an elevated fire risk due to the proximity of development and residents to wildlands with natural wildfire regimes. Existing methods of delineating WUI are typically applied over a large region, use proxies for risk, and do not consider site-specific fire hazard drivers. While these models are appropriate for federal and provincial risk management, municipal managers require models intended for smaller regions. The model developed here uses the Burn-P3 fire behavior model to model WUI from local fire susceptibility (FS) in two study communities. Forest fuel code (FFC) maps for the study communities were modified using remote sensing data to produce detailed forest edges, including ladder fuels, update data currency, and add buildings and roads. The modified FFC maps used in Burn-P3 produced bimodal FS distributions for each community. The WUI in these communities was delineated as areas within community bounds where FS was greater than or equal to -1 SD from the mean FS value ([Formula: see text]), which fell in the trough of the bimodal distribution. The WUI so delineated conformed to the definition of WUI. This model extends WUI modeling for broader risk management initiatives for municipal management of risk, as it (a) considers site-specific drivers of fire behavior; (b) models risk, represented by WUI, specific to a community; and, (c) does not use proxies for risk.

Setting priorities for private land conservation in fire-prone landscapes: Are fire risk reduction and biodiversity conservation competing or compatible objectives?

Directory of Open Access Journals (Sweden)

Alexandra D. Syphard

2016-09-01

Full Text Available Although wildfire plays an important role in maintaining biodiversity in many ecosystems, fire management to protect human assets is often carried out by different agencies than those tasked for conserving biodiversity. In fact, fire risk reduction and biodiversity conservation are often viewed as competing objectives. Here we explored the role of management through private land conservation and asked whether we could identify private land acquisition strategies that fulfill the mutual objectives of biodiversity conservation and fire risk reduction, or whether the maximization of one objective comes at a detriment to the other. Using a fixed budget and number of homes slated for development, we simulated 20 years of housing growth under alternative conservation selection strategies, and then projected the mean risk of fires destroying structures and the area and configuration of important habitat types in San Diego County, California, USA. We found clear differences in both fire risk projections and biodiversity impacts based on the way conservation lands are prioritized for selection, but these differences were split between two distinct groupings. If no conservation lands were purchased, or if purchases were prioritized based on cost or likelihood of development, both the projected fire risk and biodiversity impacts were much higher than if conservation lands were purchased in areas with high fire hazard or high species richness. Thus, conserving land focused on either of the two objectives resulted in nearly equivalent mutual benefits for both. These benefits not only resulted from preventing development in sensitive areas, but they were also due to the different housing patterns and arrangements that occurred as development was displaced from those areas. Although biodiversity conflicts may still arise using other fire management strategies, this study shows that mutual objectives can be attained through land-use planning in this region

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

International Nuclear Information System (INIS)

N.M. Ruonavaara

2001-01-01

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

Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

International Nuclear Information System (INIS)

Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

1997-12-01

This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues

Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

Energy Technology Data Exchange (ETDEWEB)

Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

1997-12-01

This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

Risk-Based Predictive Maintenance for Safety-Critical Systems by Using Probabilistic Inference

Directory of Open Access Journals (Sweden)

Tianhua Xu

2013-01-01

Full Text Available Risk-based maintenance (RBM aims to improve maintenance planning and decision making by reducing the probability and consequences of failure of equipment. A new predictive maintenance strategy that integrates dynamic evolution model and risk assessment is proposed which can be used to calculate the optimal maintenance time with minimal cost and safety constraints. The dynamic evolution model provides qualified risks by using probabilistic inference with bucket elimination and gives the prospective degradation trend of a complex system. Based on the degradation trend, an optimal maintenance time can be determined by minimizing the expected maintenance cost per time unit. The effectiveness of the proposed method is validated and demonstrated by a collision accident of high-speed trains with obstacles in the presence of safety and cost constrains.

Highway tunnel safety; Le gallerie infrastrutturali e la loro sicurezza

Energy Technology Data Exchange (ETDEWEB)

Sacripanti, A [ENEA, Divisione Robotica Informatica Avanzata, Rome (Italy)

2001-04-01

Guaranteeing an acceptable level of fire safety in tunnels requires the targeted and integrated use of innovative technologies and systems. However, their deployment to improve safety against a variable risk like fire must be based on a risk analysis capable of developing a dynamic vision of the tunnel. [Italian] Per assicurare un livello di sicurezza accettabile nei tunnel, in caso di incendio e' necessario l'uso mirato ed integrato di tecnologie e sistemi innovativi. Alla base, pero', ci deve essere una analisi di rischio in grado di sviluppare una visione dinamica della galleria, per migliorarne la sicurezza a fronte di un rischio variabile nel tempo.

Highway tunnel safety; Le gallerie infrastrutturali e la loro sicurezza

Energy Technology Data Exchange (ETDEWEB)

Sacripanti, A. [ENEA, Divisione Robotica Informatica Avanzata, Rome (Italy)

2001-04-01

Guaranteeing an acceptable level of fire safety in tunnels requires the targeted and integrated use of innovative technologies and systems. However, their deployment to improve safety against a variable risk like fire must be based on a risk analysis capable of developing a dynamic vision of the tunnel. [Italian] Per assicurare un livello di sicurezza accettabile nei tunnel, in caso di incendio e' necessario l'uso mirato ed integrato di tecnologie e sistemi innovativi. Alla base, pero', ci deve essere una analisi di rischio in grado di sviluppare una visione dinamica della galleria, per migliorarne la sicurezza a fronte di un rischio variabile nel tempo.

The aspects of fire safety at landfills

Directory of Open Access Journals (Sweden)

Aleshina Tat'yana Anatol'evna

2014-01-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

Effects of risk attitudes on extended attack fire management decisionmaking

Science.gov (United States)

Donald G. MacGregor; Armando González-Cabán

2009-01-01

Fire management inherently involves the assessment and management of risk, and decision making under uncertainty. Although organizational standards and guides are an important determinant of how decision problems are structured and framed, decision makers may view risk-based decisions from a perspective that is unique to their background and experience. Previous...

Application of risk-based methodologies to prioritize safety resources

International Nuclear Information System (INIS)

Rahn, F.J.; Sursock, J.P.; Hosler, J.

1993-01-01

The Electric Power Research Institute (EPRI) started a program entitled risk-based prioritization in 1992. The purpose of this program is to provide generic technical support to the nuclear power industry relative to its recent initiatives in the area of operations and maintenance (O ampersand M) cost control using state-of-the-art risk methods. The approach uses probabilistic risk assessment (PRA), or similar techniques, to allocate resources commensurate with the risk posed by nuclear plant operations. Specifically, those items or events that have high risk significance would receive the most attention, while those with little risk content would command fewer resources. As quantified in a companion paper,close-quote the potential O ampersand M cost reduction inherent in this approach is very large. Furthermore, risk-based methods should also lead to safety improvements. This paper outlines the way that the EPRI technical work complements the technical, policy, and regulatory initiatives taken by others in the industry and provides an example of the approach as used to prioritize motor-operated valve (MOV) testing in response to US Nuclear Regulatory Commission (NRC) Generic Letter 89-10

Fire danger rating over Mediterranean Europe based on fire radiative power derived from Meteosat

Science.gov (United States)

Pinto, Miguel M.; DaCamara, Carlos C.; Trigo, Isabel F.; Trigo, Ricardo M.; Feridun Turkman, K.

2018-02-01

We present a procedure that allows the operational generation of daily forecasts of fire danger over Mediterranean Europe. The procedure combines historical information about radiative energy released by fire events with daily meteorological forecasts, as provided by the Satellite Application Facility for Land Surface Analysis (LSA SAF) and the European Centre for Medium-Range Weather Forecasts (ECMWF). Fire danger is estimated based on daily probabilities of exceedance of daily energy released by fires occurring at the pixel level. Daily probability considers meteorological factors by means of the Canadian Fire Weather Index (FWI) and is estimated using a daily model based on a generalized Pareto distribution. Five classes of fire danger are then associated with daily probability estimated by the daily model. The model is calibrated using 13 years of data (2004-2016) and validated against the period of January-September 2017. Results obtained show that about 72 % of events releasing daily energy above 10 000 GJ belong to the extreme class of fire danger, a considerably high fraction that is more than 1.5 times the values obtained when using the currently operational Fire Danger Forecast module of the European Forest Fire Information System (EFFIS) or the Fire Risk Map (FRM) product disseminated by the LSA SAF. Besides assisting in wildfire management, the procedure is expected to help in decision making on prescribed burning within the framework of agricultural and forest management practices.

Fire danger rating over Mediterranean Europe based on fire radiative power derived from Meteosat

Directory of Open Access Journals (Sweden)

M. M. Pinto

2018-02-01

Full Text Available We present a procedure that allows the operational generation of daily forecasts of fire danger over Mediterranean Europe. The procedure combines historical information about radiative energy released by fire events with daily meteorological forecasts, as provided by the Satellite Application Facility for Land Surface Analysis (LSA SAF and the European Centre for Medium-Range Weather Forecasts (ECMWF. Fire danger is estimated based on daily probabilities of exceedance of daily energy released by fires occurring at the pixel level. Daily probability considers meteorological factors by means of the Canadian Fire Weather Index (FWI and is estimated using a daily model based on a generalized Pareto distribution. Five classes of fire danger are then associated with daily probability estimated by the daily model. The model is calibrated using 13 years of data (2004–2016 and validated against the period of January–September 2017. Results obtained show that about 72 % of events releasing daily energy above 10 000 GJ belong to the extreme class of fire danger, a considerably high fraction that is more than 1.5 times the values obtained when using the currently operational Fire Danger Forecast module of the European Forest Fire Information System (EFFIS or the Fire Risk Map (FRM product disseminated by the LSA SAF. Besides assisting in wildfire management, the procedure is expected to help in decision making on prescribed burning within the framework of agricultural and forest management practices.

Establishing Fire Safety Skills Using Behavioral Skills Training

Science.gov (United States)

Houvouras, Andrew J., IV; Harvey, Mark T.

2014-01-01

The use of behavioral skills training (BST) to educate 3 adolescent boys on the risks of lighters and fire setting was evaluated using in situ assessment in a school setting. Two participants had a history of fire setting. After training, all participants adhered to established rules: (a) avoid a deactivated lighter, (b) leave the training area,…

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

Directory of Open Access Journals (Sweden)

Domen Kušar

2009-01-01

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

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 .

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...

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...

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

Science.gov (United States)

Timothy Ingalsbee; Joseph Fox; Patrick Withen

2007-01-01

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

Five Years of a Computer Based New Training Program in Safety and Radiation Protection

International Nuclear Information System (INIS)

Ben-Shachar, B.; Tshuva, M.; Fitussi, I.; Ankri, D.

2004-01-01

One of the main goals of the Department of Human Resources Development is to give employees fundamental knowledge, refreshing know-how and increasing safety awareness. In this regard safety deals with risks in operating nuclear facilities, including radiation, industrial risks and fire. Israeli Work Supervision (informing and training employees, 1992) (1) and work safety regulations (industrial safety and health for ionization radiation employees) state the need for training by the employer at least once a year. The employer also must take means to verify that the employees actually understand what they were trained for

A computer code SPHINCS for sodium fire safety evaluation

International Nuclear Information System (INIS)

Yamaguchi, Akira

2000-01-01

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

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

OpenAIRE

P.A. (Tony) Enright

2014-01-01

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

Evaluation Logic of Main Control Board Fire Risk

Energy Technology Data Exchange (ETDEWEB)

Kang, Dae Il; Kim, Kilyoo; Lim, Ho Gon [KAERI, Daejeon (Korea, Republic of)

2015-05-15

The main control board (MCB) is defined as the collection of control panels inside the main control room (MCR) of a nuclear power plant (NPP). As the MCB has the control and instrumentation circuits of redundant trains for almost all plant systems, small fires within the control panels may be detrimental to the safe shutdown capability. A big fire affecting many panels in the MCB can cause a forced MCR abandonment of the operators as well as function failures or spurious operations of the control and instrumentation-related components. If the MCR cannot be habitable, a safe shutdown from outside the MCR can be achieved and maintained at an alternate shutdown panel electrically and physically independent from the MCR. Because the MCB consist of many electrical panels, it may have internal barriers between them to prevent a fire from spreading from its origin to neighboring locations. However, most MCBs of domestic NPPs do not have internal barriers within them. If the MCB cabinets are not separated by a double wall with an air gap, the fire propagation of an MCB panel fire cannot be ruled out. Recently, Joglar et al. proposed a new evaluation logic for the MCB panel fires and mentioned that an MCB fire can be divided into propagation and non-propagating fires for abandonment and non-abandonment fire scenarios. However, they did not present the details on the fire modeling approaches and probability formulas for the fire scenarios. In this paper, a decision tree for evaluating the risk of an MCB fire is proposed to systematically determine the fire scenarios in terms of the fire modeling approaches. This paper proposed a decision tree for evaluating the risk of an MCB fire to systematically determine the fire scenarios in terms of fire modeling approaches.