Fire protection in nuclear power plants

International Nuclear Information System (INIS)

1979-01-01

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

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.

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

Science.gov (United States)

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

2015-01-01

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

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

Directory of Open Access Journals (Sweden)

Sumalika Biswas

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

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

Science.gov (United States)

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

2015-01-01

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

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...

46 CFR 176.810 - Fire protection.

Science.gov (United States)

2010-10-01

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

14 CFR 33.17 - Fire protection.

Science.gov (United States)

2010-01-01

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

Fire protection measures

International Nuclear Information System (INIS)

Bittner

1997-01-01

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

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

J. D. Bigbee

2000-06-21

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

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

J. D. Bigbee

2000-01-01

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

49 CFR 193.2611 - Fire protection.

Science.gov (United States)

2010-10-01

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

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

International Nuclear Information System (INIS)

Zitzelsberger, J.

1983-01-01

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

Fire protection at nuclear power plants

International Nuclear Information System (INIS)

1999-11-01

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

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

Fire protection maintenance at Browns Ferry Nuclear Plant

International Nuclear Information System (INIS)

Kern, J.R.

1989-01-01

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

Standpipe systems for fire protection

CERN Document Server

Isman, Kenneth E

2017-01-01

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

Aircraft Fire Protection Laboratory

Data.gov (United States)

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

Aging assessment for active fire protection systems

International Nuclear Information System (INIS)

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

1995-06-01

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

Sodium fire protection

International Nuclear Information System (INIS)

Raju, C.; Kale, R.D.

1979-01-01

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

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

Training of fire protection personnel in nuclear power plants

International Nuclear Information System (INIS)

Blaser, W.

1980-01-01

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

Decommissioning Handbook

International Nuclear Information System (INIS)

Cusack, J.G.; Dalfonso, P.H.; Lenyk, R.G.

1994-01-01

The Decommissioning Handbook provides technical guidance on conducting decommissioning projects. Information presented ranges from planning logic, regulations affecting decommissioning, technology discussion, health and safety requirements, an developing a cost estimate. The major focus of the handbook are the technologies -- decontamination technologies, waste treatment, dismantling/segmenting/demolition, and remote operations. Over 90 technologies are discussed in the handbook providing descriptions, applications, and advantages/disadvantages. The handbook was prepared to provide a compendium of available or potentially available technologies in order to aid the planner in meeting the specific needs of each decommissioning project. Other subjects presented in the Decommissioning Handbook include the decommissioning plan, characterization, final project configuration based planning, environmental protection, and packaging/transportation. These discussions are presented to complement the technologies presented in the handbook

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)

46 CFR 194.15-7 - Fire protection.

Science.gov (United States)

2010-10-01

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

46 CFR 169.311 - Fire protection.

Science.gov (United States)

2010-10-01

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

The importance of verifiable fire protection design

Energy Technology Data Exchange (ETDEWEB)

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

2004-07-01

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

Fire protection guidelines for nuclear power plants

International Nuclear Information System (INIS)

1976-06-01

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

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.)

10 CFR 36.27 - Fire protection.

Science.gov (United States)

2010-01-01

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

46 CFR 194.20-7 - Fire protection.

Science.gov (United States)

2010-10-01

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

Handbook for the calculation of reactor protections; Formulaire sur le calcul de la protection des reacteurs

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-07-01

This note constitutes the first edition of a Handbook for the calculation of reactor protections. This handbook makes it possible to calculate simply the different neutron and gamma fluxes and consequently, to fix the minimum quantities of materials necessary under general safety conditions both for the personnel and for the installations. It contains a certain amount of nuclear data, calculation methods, and constants corresponding to the present state of our knowledge. (authors) [French] Cette note constitue la premiere edition du 'Formulaire sur le calcul de la protection des reacteurs'. Ce formulaire permet de calculer de facon simple les difterents flux de neutrons et de gamma et, par suite, de fixer les quantites minima de materiaux a utiliser pour que les conditions generales de securite soient respectees, tant pour le personnel que pour les installations. Il contient un certain nombre de donnees nucleaires, de methodes de calcul et de constantes correspondant a l'etat actuel de nos connaissances. (auteurs)

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

International Nuclear Information System (INIS)

Bindon, F.J.L.

1987-01-01

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

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)

Report on task I: fire protection system study

International Nuclear Information System (INIS)

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

1977-02-01

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

Particular features of fire protection in nuclear power plants

International Nuclear Information System (INIS)

Krueger, W.

1985-01-01

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

46 CFR 153.460 - Fire protection systems.

Science.gov (United States)

2010-10-01

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

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.

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

International Nuclear Information System (INIS)

2012-04-01

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

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

International Nuclear Information System (INIS)

Chappellier, A.M.

1976-01-01

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

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

International Nuclear Information System (INIS)

Tian Deyuan

1999-01-01

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

Reserves protect against deforestation fires in the Amazon.

Directory of Open Access Journals (Sweden)

J Marion Adeney

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

Reserves Protect against Deforestation Fires in the Amazon

Science.gov (United States)

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

2009-01-01

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

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

1992-01-01

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

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

Science.gov (United States)

Dale Wade; Steven Miller; Johnny Stowe; James Brenner

2006-01-01

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

Fire protection countermeasures for containment ventilation systems

International Nuclear Information System (INIS)

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

1980-01-01

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

14 CFR 25.854 - Lavatory fire protection.

Science.gov (United States)

2010-01-01

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

Seismic design criteria of fire protection systems for DOE facilities

International Nuclear Information System (INIS)

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

1991-01-01

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

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

OpenAIRE

A. V. Zhovna

2008-01-01

The paper gives an analysis of economic results pertaining to organization of a system for fire-fighting protection of industrial enterprises in theRepublicofBelarus. Statistical data on operational conditions of technical means of fire-fighting protection, particularly, automatic systems for detection and extinguishing of fires, systems of internal fire-fighting water-supply.  Requirements and provisions  of normative and technical documents are thoroughly studied. Observance of these docume...

PG BN 1600 sodium fire protection system

International Nuclear Information System (INIS)

Bar, J.; Urbancik, L.

1978-12-01

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

Quality assurance through fire protection documentation

Energy Technology Data Exchange (ETDEWEB)

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

2010-07-01

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

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

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

International Nuclear Information System (INIS)

Oliveira Segabinaze, R. de

1994-01-01

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

Fire protection countermeasures for containment ventilation systems

International Nuclear Information System (INIS)

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

1980-01-01

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

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

International Nuclear Information System (INIS)

Mummert, Maxi; Traichel, Anke; Dilger, Matthias

2013-01-01

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

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

Science.gov (United States)

J. Keith Gilless; Jeremy S. Fried

1998-01-01

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

Still a hot issue. US fire protection 20 years on

International Nuclear Information System (INIS)

Hathaway, L.R.

1995-01-01

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

Analysis of fire protection in nuclear power plants

International Nuclear Information System (INIS)

Hosser, D.; Schneider, U.

1982-01-01

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

Fires: what plant locations should we really protect

International Nuclear Information System (INIS)

Berry, D.L.

1980-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-03-01

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

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

International Nuclear Information System (INIS)

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

1996-01-01

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

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

Science.gov (United States)

Rahman, Vinky; Stephanie

2018-03-01

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

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

International Nuclear Information System (INIS)

Berry, D.L.

1977-12-01

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

Fire protection guidelines for nuclear power plants, June 1976

International Nuclear Information System (INIS)

Anon.

1977-01-01

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

Safety study of fire protection for nuclear fuel cycle facility

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

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

Safety study of fire protection for nuclear fuel cycle facility

International Nuclear Information System (INIS)

2013-01-01

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

Radiological protection: a summary handbook of ICRP publications and recommendations

International Nuclear Information System (INIS)

Nagaratnam, A.

1995-01-01

The biological effects of radiation and potential risks therefrom far exceeds the knowledge of any other hazardous agent, whether in the industrial field, or in the general environment affecting members of the public. The International Commission on Radiological Protection (ICRP) has been playing a pioneering role for decades in this direction. The extensive database that has been established over the decades by the ICRP, the methodologies, techniques and the organizational structures that have been developed to control radiation hazards, and, above all, the philosophy of risk evaluation and management that has been evolved by ICRP, would serve as valuable guides not only to those concerned with radiological protection but to scientist, technologist and administrators involved in all facets of occupational and industrial safety, as well as those concerned with environmental protection. From 1959 to the end of 1993 ICRP has brought out 64 publications running to around 9000 pages. It is important that everyone connected with the uses of ionizing radiations should be familiar with at least the basic features of the thinking of ICRP as embodied in these publications. The present handbook attempts to give in a concise, consolidated and codified form the salient features of all the relevant information contained in the voluminous ICRP publications. The material has been presented in 7 parts, each dealing with one major aspect of the recommendations, and summarizing the various publications connected with it. A separate note following the preface gives a brief summary of the way the contents of the handbook have been arranged. refs., tabs., figs

Modern tools to evaluate and optimize fire protection systems

International Nuclear Information System (INIS)

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

1980-01-01

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

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)

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

International Nuclear Information System (INIS)

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

2010-01-01

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

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

International Nuclear Information System (INIS)

1994-01-01

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

Basing of a complex design measures for protection against fire

International Nuclear Information System (INIS)

Kryuger, V.

1983-01-01

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

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

Fire protection concept for power stations

International Nuclear Information System (INIS)

Zitzmann, H.

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

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

Science.gov (United States)

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

1987-01-01

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

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.

The principles of protection against fires in nuclear facilities

International Nuclear Information System (INIS)

Dupuy, Ph.; Gupta, O.

2000-01-01

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

Fire prevention and protection for trackless equipment

Energy Technology Data Exchange (ETDEWEB)

Burger, A.J.

1988-10-01

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

Safety and environmental health handbook

Science.gov (United States)

,

1989-01-01

This Safety Handbook (445-1-H.) supplements the Geological Survey Safety Management Program objectives set forth in Survey Manual 445.1. Specifically, it provides a compact source of basic information to assist management and employees in preventing motor vehicle accidents, personal injuries, occupational diseases, fire, and other property damage or loss. All work situations incidental to the Geological Survey cannot be discussed in a handbook, and such complete coverage is not intended in this document. However, a wide range of subjects are covered in which a "common sense" approach to safety has been expressed. These subjects have been organized such that Chapters 1-5 address administrative issues, Chapters 6-12 address activities usually conducted within a facility, and Chapters 13-20 address field activities. No information contained in the Handbook is intended to alter any provision of any Federal law or executive order, Department of the Interior or Survey directive, or collective bargaining agreement. Questions or suggestions regarding the content of the Safety Handbook may be directed to the Survey Safety Manager, Administrative Division, Office of Facilities and Management Services, National Center, Reston, Virginia, Mail Stop 246. The previous edition of the Safety Handbook is superseded.

Fire protection of nuclear power plant cable ducts

International Nuclear Information System (INIS)

Kandrac, J.; Lukac, L.

1987-01-01

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

Central Heating Plant Coal Use Handbook. Volume 1: Technical Reference.

Science.gov (United States)

1996-11-01

CHUTES LIFT TRUCKS MONORAILS , TRAMWAYS J p WEIGHING, 0 MEASURING SCALES COAL METERS HOPPERS SAMPLERS 9 FIRING EQUIPMENT (Source: Power, February...Defense (DOD) installations employ coal- fired central energy plants, the U.S. Army Construction Engineering Research Laboratories (USACERL) was... fired central heat plant operations cost by improving coal quality specifications. The Handbook is tailored for military installation industrial

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

Course in fire protection training for nuclear power plant personnel

International Nuclear Information System (INIS)

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

1979-01-01

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

Solution of Fire Protection in Historic Buildings

Science.gov (United States)

Iringová, Agnes; Idunk, Róbert

2016-12-01

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

Development of a Smart Residential Fire Protection System

Directory of Open Access Journals (Sweden)

Juhwan Oh

2013-01-01

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

Probabilistic evaluation of fire protection features found in nuclear power plants

International Nuclear Information System (INIS)

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

1985-01-01

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

Improvement of fire protection measures for nuclear power plants

International Nuclear Information System (INIS)

2012-01-01

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

Fire protection for launch facilities using machine vision fire detection

Science.gov (United States)

Schwartz, Douglas B.

1993-02-01

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

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

International Nuclear Information System (INIS)

Isaksson, S.

1995-06-01

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

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

International Nuclear Information System (INIS)

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

1985-09-01

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

Decommissioning Handbook

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

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

Science.gov (United States)

2010-07-01

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

Improvement of fire protection measures for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

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

Fire protection programme during construction of the Chashma nuclear power plant

International Nuclear Information System (INIS)

Mian Umer, M.

1998-01-01

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

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

International Nuclear Information System (INIS)

Bell, J.R.

1980-01-01

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

Diesel generator fire protection: getting the balance right

International Nuclear Information System (INIS)

Enzmann, Hans; Swiss Reinsurance Co., Zurich)

1986-01-01

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

Planning for fire control and protection of personnel

International Nuclear Information System (INIS)

Rule, A.V.

1989-01-01

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

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

International Nuclear Information System (INIS)

1994-01-01

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

The radiation protection units of the Austrian fire brigades

International Nuclear Information System (INIS)

Aspek, W.; Schoenhacker, S.

2009-01-01

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

Fire protection system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1995-12-01

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

Fire protection system operating experience review for fusion applications

Energy Technology Data Exchange (ETDEWEB)

Cadwallader, L.C.

1995-12-01

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

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...

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

International Nuclear Information System (INIS)

Dey, M.K.

1998-01-01

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

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

International Nuclear Information System (INIS)

Dey, M.K.

2000-01-01

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

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

Science.gov (United States)

Zhao, Mengmeng

2017-12-01

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

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

Directory of Open Access Journals (Sweden)

Ilyin Nikolay

2017-01-01

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

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

Science.gov (United States)

2010-07-01

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

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

Science.gov (United States)

2013-09-11

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

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

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

Science.gov (United States)

2013-07-29

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

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

Science.gov (United States)

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

2018-04-01

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

Fire protection of safe shutdown capability at commercial nuclear power plants

International Nuclear Information System (INIS)

Sullivan, K.

1993-01-01

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

New probabilistic decision-making tools for fire protection systems

International Nuclear Information System (INIS)

Ksobiech, C.; Mowrer, F.

1991-01-01

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

Fire protection of safe shutdown capability at commercial nuclear power plants

International Nuclear Information System (INIS)

Sullivan, K.

1993-01-01

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

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

Science.gov (United States)

2010-07-01

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

Consumer Handbook to Credit Protection Laws.

Science.gov (United States)

Board of Governors of the Federal Reserve System, Washington, DC.

The five sections of this consumer handbook are The Cost of Credit, Applying for Credit, Credit Histories and Records, Correcting Credit Mistakes, and Complaining about Credit. Each section discusses relevant legislation: Truth in Lending, the Equal Credit Opportunity Act, and the Fair Credit Reporting Act. Topics discussed in section I include…

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

Directory of Open Access Journals (Sweden)

Ismail I.

2014-03-01

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

Cold Vacuum Drying facility fire protection system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

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

Numerical case studies of vertical wall fire protection using water spray

Directory of Open Access Journals (Sweden)

L.M. Zhao

2014-11-01

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

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

International Nuclear Information System (INIS)

Zhu, L.H.

1998-01-01

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

Newnes electronics assembly handbook

CERN Document Server

Brindley, Keith

2013-01-01

Newnes Electronics Assembly Handbook: Techniques, Standards and Quality Assurance focuses on the aspects of electronic assembling. The handbook first looks at the printed circuit board (PCB). Base materials, basic mechanical properties, cleaning of assemblies, design, and PCB manufacturing processes are then explained. The text also discusses surface mounted assemblies and packaging of electromechanical assemblies, as well as the soldering process. Requirements for the soldering process; solderability and protective coatings; cleaning of PCBs; and mass solder/component reflow soldering are des

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-15

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

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

International Nuclear Information System (INIS)

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

1991-01-01

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

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

International Nuclear Information System (INIS)

1991-10-01

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

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

International Nuclear Information System (INIS)

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

1984-01-01

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

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

International Nuclear Information System (INIS)

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

1983-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

SINGH, G.

2000-10-17

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

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

Science.gov (United States)

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-10-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-15

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

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

International Nuclear Information System (INIS)

Zhou Weihong

1999-12-01

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

Design guide for fire protection of grouped electrical cables

International Nuclear Information System (INIS)

Dungan, K.W.

1991-05-01

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

DOE handbook: Tritium handling and safe storage

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

DOE handbook: Tritium handling and safe storage

International Nuclear Information System (INIS)

1999-03-01

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance

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

International Nuclear Information System (INIS)

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

1999-01-01

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

Maximum permissible body burdens and maximum permissible concentrations of radionuclides in air and in water for occupational exposure. Recommendations of the National Committee on Radiation Protection. Handbook 69

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-06-05

The present Handbook and its predecessors stem from the Second International Congress of Radiology, held in Stockholm in 1928. At that time, under the auspices of the Congress, the International Commission on Radiological Protection (ICRP) was organized to deal initially with problems of X-ray protection and later with radioactivity protection. At that time 'permissible' doses of X-rays were estimated primarily in terms of exposures which produced erythema, the amount of exposure which would produce a defined reddening of the skin. Obviously a critical problem in establishing criteria for radiation protection was one of developing useful standards and techniques of physical measurement. For this reason two of the organizations in this country with a major concern for X-ray protection, the American Roentgen Ray Society and the Radiology Society of North America, suggested that the National Bureau of Standards assume responsibility for organizing representative experts to deal with the problem. Accordingly, early in 1929, an Advisory Committee on X-ray and Radium Protection was organized to develop recommendations on the protection problem within the United States and to formulate United States points of view for presentation to the International Commission on Radiological Protection. The organization of the U.S. Advisory Committee included experts from both the medical and physical science fields. The recommendations of this Handbook take into consideration the NCRP statement entitled 'Maximum Permissible Radiation Exposures to Man', published as an addendum to Handbook 59 on April 15, 1958. As noted above this study was carried out jointly by the ICRP and the NCRP, and the complete report is more extensive than the material contained in this Handbook.

Maximum permissible body burdens and maximum permissible concentrations of radionuclides in air and in water for occupational exposure. Recommendations of the National Committee on Radiation Protection. Handbook 69

International Nuclear Information System (INIS)

1959-01-01

The present Handbook and its predecessors stem from the Second International Congress of Radiology, held in Stockholm in 1928. At that time, under the auspices of the Congress, the International Commission on Radiological Protection (ICRP) was organized to deal initially with problems of X-ray protection and later with radioactivity protection. At that time 'permissible' doses of X-rays were estimated primarily in terms of exposures which produced erythema, the amount of exposure which would produce a defined reddening of the skin. Obviously a critical problem in establishing criteria for radiation protection was one of developing useful standards and techniques of physical measurement. For this reason two of the organizations in this country with a major concern for X-ray protection, the American Roentgen Ray Society and the Radiology Society of North America, suggested that the National Bureau of Standards assume responsibility for organizing representative experts to deal with the problem. Accordingly, early in 1929, an Advisory Committee on X-ray and Radium Protection was organized to develop recommendations on the protection problem within the United States and to formulate United States points of view for presentation to the International Commission on Radiological Protection. The organization of the U.S. Advisory Committee included experts from both the medical and physical science fields. The recommendations of this Handbook take into consideration the NCRP statement entitled 'Maximum Permissible Radiation Exposures to Man', published as an addendum to Handbook 59 on April 15, 1958. As noted above this study was carried out jointly by the ICRP and the NCRP, and the complete report is more extensive than the material contained in this Handbook

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

Energy Technology Data Exchange (ETDEWEB)

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

1982-07-20

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

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

International Nuclear Information System (INIS)

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

1982-01-01

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

Safety handbook

International Nuclear Information System (INIS)

1990-01-01

The purpose of the Australian Nuclear Science and Technology Organization's Safety Handbook is to outline simply the fundamental procedures and safety precautions which provide an appropriate framework for safe working with any potential hazards, such as fire and explosion, welding, cutting, brazing and soldering, compressed gases, cryogenic liquids, chemicals, ionizing radiations, non-ionising radiations, sound and vibration, as well as safety in the office. It also specifies the organisation for safety at the Lucas Heights Research Laboratories and the responsibilities of individuals and committees. It also defines the procedures for the scrutiny and review of all operations and the resultant setting of safety rules for them. ills

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

Science.gov (United States)

2010-07-01

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

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

Science.gov (United States)

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

2018-07-15

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

Radiation safety. Handbook for laboratory workers in the USA

International Nuclear Information System (INIS)

Hotte, E.D.; Krueger, D.J.; Connor, K.

2000-01-01

The aim of the Handbook is to provide a source of information on radiation safety for those who are involved in the use of ionizing radiation in the laboratory. The potential reader may be a laboratory worker in the university or biomedical setting or the safety professional who desires a basic understanding of radiation protection within the research environment. The Handbook may be used as a reference by the radiation protection specialist or Radiation Safety Officer. To this end, liberal use is made of Appendices to make the Handbook a source of reference for a wide spectrum of readership while avoiding complicating the main body of the text. Each chapter or appendix is designed to stand alone. A complete reading of the Handbook will show that topics may be covered more than once. For example, one may read about the hazards and protective measures on handling radioiodine in Chapter 5 on Practical Radiation Protection as well as in Appendix 19 on Safe Handling of 125 I. Extensive use of figures, rather than tables has been made to present data, in the belief that these produce a good visual representation to a level of precision which is sufficient for most purposes of radiation protection in laboratories. The reader must remember that this Handbook should be taken as a guide only to the applicable regulations. You must consult the appropriate state or federal regulation directly or receive advice of a qualified radiation safety professional. Also, some information in the Appendices, such as commercially available training institutions or radioactive waste brokers, may change with time. Telephone numbers are given for the reader to call directly and check the services provided

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

International Nuclear Information System (INIS)

Hasegawa, Takayasu; Miyakoshi, Hirohisa; Goto, Masami

2013-01-01

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

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

Directory of Open Access Journals (Sweden)

M. C. Yew

2014-01-01

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

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

International Nuclear Information System (INIS)

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

1981-01-01

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

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

Science.gov (United States)

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

2014-01-01

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

Nuclear fuel cycle facility accident analysis handbook

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

Nuclear fuel cycle facility accident analysis handbook

International Nuclear Information System (INIS)

1998-03-01

The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs

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

International Nuclear Information System (INIS)

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

1976-01-01

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

Chemical Solutions of Fire Protection Problems

Directory of Open Access Journals (Sweden)

Vakhitova, L.M.

2015-11-01

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

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

International Nuclear Information System (INIS)

Covalschi, V.

1998-01-01

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

Fire protection assessment in a WANO peer review

International Nuclear Information System (INIS)

Vella, R.

1998-01-01

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

Design guides for cell atmosphere controls, utilities and fire protection

International Nuclear Information System (INIS)

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

1981-01-01

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

Wildland Fire Research: Water Supply and Ecosystem Protection

Science.gov (United States)

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

FIRE

International Nuclear Information System (INIS)

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

1990-01-01

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

Handbook of Research on Environmental Taxation

DEFF Research Database (Denmark)

, their environmental and economic impact and, finally, the larger question of the role of taxation among other policy approaches to environmental protection. Intermixing theory with case studies, the Handbook offers readers lessons that can be applied around the world. It identifies key bodies of research for people......The Handbook of Research on Environmental Taxation captures the state of the art of research on environmental taxation. Written by 36 specialists in environmental taxation from 16 countries, it takes an interdisciplinary and international approach, focusing on issues that are universal to using...... taxation to achieve environmental goals. The Handbook explores the conceptual foundations of environmental taxation, essential elements for designing environmental tax measures, factors that influence the acceptance of environmental taxation, the variety of ways to implement environmental taxes...

Fuel Handbook[Wood and other renewable fuels

Energy Technology Data Exchange (ETDEWEB)

Stroemberg, Birgitta [TPS Termiska Processer AB, Nykoeping (SE)] (ed.)

2006-03-15

This handbook on renewable fuels is intended for power and heat producers in Sweden. This fuel handbook provides, from a plant owner's perspective, a method to evaluate different fuels on the market. The fuel handbook concerns renewable fuels (but does not include household waste) that are available on the Swedish market today or fuels that have potential to be available within the next ten years. The handbook covers 26 different fuels. Analysis data, special properties, operating experiences and literature references are outlined for each fuel. [Special properties, operating experiences and literature references are not included in this English version] The handbook also contains: A proposed methodology for introduction of new fuels. A recommendation of analyses and tests to perform in order to reduce the risk of problems is presented. [The recommendation of analyses and tests is not included in the English version] A summary of relevant laws and taxes for energy production, with references to relevant documentation. [Only laws and taxes regarding EU are included] Theory and background to evaluate a fuel with respect to combustion, ash and corrosion properties and methods that can be used for such evaluations. Summary of standards, databases and handbooks on biomass fuels and other solid fuels, and links to web sites where further information about the fuels can be found. The appendices includes: A methodology for trial firing of fuels. Calculations procedures for, amongst others, heating value, flue gas composition, key number and free fall velocity [Free fall velocity is not included in the English version]. In addition, conversion routines between different units for a number of different applications are provided. Fuel analyses are presented in the appendix. (The report is a translation of parts of the report VARMEFORSK--911 published in 2005)

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

Directory of Open Access Journals (Sweden)

V. V. Furyaev

2017-10-01

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

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

International Nuclear Information System (INIS)

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

2017-01-01

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

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

Directory of Open Access Journals (Sweden)

Dragsted Anders

2013-11-01

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

DOE handbook: Design considerations

International Nuclear Information System (INIS)

1999-04-01

The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline

DOE handbook: Design considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

The Design Considerations Handbook includes information and suggestions for the design of systems typical to nuclear facilities, information specific to various types of special facilities, and information useful to various design disciplines. The handbook is presented in two parts. Part 1, which addresses design considerations, includes two sections. The first addresses the design of systems typically used in nuclear facilities to control radiation or radioactive materials. Specifically, this part addresses the design of confinement systems and radiation protection and effluent monitoring systems. The second section of Part 1 addresses the design of special facilities (i.e., specific types of nonreactor nuclear facilities). The specific design considerations provided in this section were developed from review of DOE 6430.1A and are supplemented with specific suggestions and considerations from designers with experience designing and operating such facilities. Part 2 of the Design Considerations Handbook describes good practices and design principles that should be considered in specific design disciplines, such as mechanical systems and electrical systems. These good practices are based on specific experiences in the design of nuclear facilities by design engineers with related experience. This part of the Design Considerations Handbook contains five sections, each of which applies to a particular engineering discipline.

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

International Nuclear Information System (INIS)

Johnson, B.H.

1994-01-01

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

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

Science.gov (United States)

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

2009-01-01

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

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

International Nuclear Information System (INIS)

Maybee, W.W.

1979-01-01

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

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

Science.gov (United States)

2012-09-19

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

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

International Nuclear Information System (INIS)

1999-06-01

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

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

Science.gov (United States)

Nolte, Christoph; Agrawal, Arun

2013-02-01

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

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 protection devices in the controlled region of GKN nuclear power station

International Nuclear Information System (INIS)

Bernhardt, S.; Grauf, E.

1976-01-01

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

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

CERN Document Server

Singh, G

2000-01-01

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

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

International Nuclear Information System (INIS)

SINGH, G.

2000-01-01

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

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

Science.gov (United States)

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

2017-12-01

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

Dampers, fluidics and the failsafe fallacy [fire protection

International Nuclear Information System (INIS)

Dann, M.; Hodgson, T.

1989-01-01

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

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

NARCIS (Netherlands)

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

2009-01-01

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

National Fire Protection Association

Science.gov (United States)

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

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

International Nuclear Information System (INIS)

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

1980-01-01

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

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

Science.gov (United States)

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

1981-05-01

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

Handbook on care, handling and protection of nuclear medicine instruments

International Nuclear Information System (INIS)

2000-11-01

Instruments are fundamental to successful nuclear medicine practice. They must be properly installed in an environment in which they can give accurate and uninterrupted service. They have to be properly and carefully operated and supported throughout their life by regular care and maintenance. If something is wrong with a key instrument all well trained staff members are idle and all purchased radiopharmaceuticals become useless. Overall responsibility for instrumentation rests with the directors of nuclear medicine centres. They should support their electronic engineers, medical physicists, technologists and physicians to plan and implement the care and protection of nuclear medicine instruments, see that they are properly maintained, and kept in optimum working condition by regular checks. Protection should be considered, and provided for, before installing any new instrument. The protective devices are part of the new installation and should be well maintained along with the instrument throughout its life. Thus protection needs careful planning, particularly at the beginning of a new instrumentation programme. It can affect selection, procurement, acceptance testing, and the design of quality control and maintenance routines. These activities should be considered as important in their own right. They should not be mixed in with other functions or left to take care of themselves in the daily rush to get through routine work. Experience suggests that more than half of all failures of electronic equipment are due to damage by external electrical disturbances. Section 2 of this handbook aims to help instrument users in nuclear medicine centres to understand the nature of the various types of disturbance, and to protect against them. Section 3 shows how air conditioning can help to protect instrumentation. Section 4 lists some practical tips to avoid accidental damage due to mishandling. A computer program for use with Personal Computers, ''EPC Expert'' is described

Brazing handbook

CERN Document Server

American Welding Society

2007-01-01

By agreement between the American Welding Society C3 Committee on Brazing and Soldering and the ASM Handbook Committee, the AWS Brazing Handbook has been formally adopted as part of the ASM Handbook Series. Through this agreement, the brazing content in the ASM Handbook is significantly updated and expanded. The AWS Brazing Handbook, 5th Edition provides a comprehensive, organized survey of the basics of brazing, processes, and applications. Addresses the fundamentals of brazing, brazement design, brazing filler metals and fluxes, safety and health, and many other topics. Includes new chapters on induction brazing and diamond brazing.

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

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

Science.gov (United States)

2012-12-14

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

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

International Nuclear Information System (INIS)

Johnson, G.A.

1982-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-06-01

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

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

International Nuclear Information System (INIS)

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

1981-01-01

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

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.

Challenges to fire protection measures at Hamaoka Nuclear Power Station

International Nuclear Information System (INIS)

Narama, Takeshi

2015-01-01

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

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

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

Science.gov (United States)

2010-01-01

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

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

Science.gov (United States)

2010-01-01

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

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

Indian Academy of Sciences (India)

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

29 CFR 1915.507 - Land-side fire protection systems.

Science.gov (United States)

2010-07-01

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

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

International Nuclear Information System (INIS)

Bremer, Joerg; Kim, Duill; Wendt, Ruediger

2002-01-01

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

Thermal assault and polyurethane foam-evaluating protective mechanisms

International Nuclear Information System (INIS)

Williamson, C.L.; Iams, Z.L.

2004-01-01

Rigid polyurethane foam utilizes a variety of mechanisms to mitigate the thermal assault of a ''regulatory burn''. Polymer specific heat and foam k-factor are of limited usefulness in predicting payload protection. Properly formulated rigid polyurethane foam provides additional safeguards by employing ablative mechanisms which are effective even when the foam has been crushed or fractured as a result of trauma. The dissociative transitions from polymer to gas and char, and the gas transport of heat from inside the package out into the environment are also thermal mitigators. Additionally, the in-situ production of an intumescent, insulative, carbonaceous char, confers thermal protection even when a package's outer steel skin has been breached. In this test program, 19 liter, ''Five gallon'' steel pails are exposed on one end to the flame of an ''Oil Burner'' as described in the US Federal Aviation Administration (FAA) ''Aircraft Materials Fire Test Handbook''. When burning 2 diesel at a nominal rate of 8.39 kg (18.5 pounds)/hr, the burner generates a high emissivity flame that impinges on the pail face with the thermal intensity of a full scale pool-fire environment. Results of these tests, TGA and MDSC analysis on the subject foams are reported, and their relevance to full size packages and pool fires are discussed

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

Energy Technology Data Exchange (ETDEWEB)

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

2004-03-01

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

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Radioactivity Handbook

International Nuclear Information System (INIS)

Firestone, R.B.; Browne, E.

1985-01-01

The Radioactivity Handbook will be published in 1985. This handbook is intended primarily for applied users of nuclear data. It will contain recommended radiation data for all radioactive isotopes. Pages from the Radioactivity Handbook for A = 221 are shown as examples. These have been produced from the LBL Isotopes Project extended ENDSF data-base. The skeleton schemes have been manually updated from the Table of Isotopes and the tabular data are prepared using UNIX with a phototypesetter. Some of the features of the Radioactivity Handbook are discussed here

Incineration process fire and explosion protection

International Nuclear Information System (INIS)

Ziegler, D.L.

1975-01-01

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

Environmental regulations handbook for enhanced oil recovery

International Nuclear Information System (INIS)

Madden, M.P.; Blatchford, R.P.; Spears, R.B.

1991-12-01

This handbook is intended to assist owners and operators of enhanced oil recovery (EOR) operations in acquiring some introductory knowledge of the various state agencies, the US Environmental Protection Agency, and the many environmental laws, rules and regulations which can have jurisdiction over their permitting and compliance activities. It is a compendium of summarizations of environmental rules. It is not intended to give readers specific working details of what is required from them, nor can it be used in that manner. Readers of this handbook are encouraged to contact environmental control offices nearest to locations of interest for current regulations affecting them

Environmental regulations handbook for enhanced oil recovery

Energy Technology Data Exchange (ETDEWEB)

Madden, M.P. [National Inst. for Petroleum and Energy Research, Bartlesville, OK (United States); Blatchford, R.P.; Spears, R.B. [Spears and Associates, Inc., Tulsa, OK (United States)

1991-12-01

This handbook is intended to assist owners and operators of enhanced oil recovery (EOR) operations in acquiring some introductory knowledge of the various state agencies, the US Environmental Protection Agency, and the many environmental laws, rules and regulations which can have jurisdiction over their permitting and compliance activities. It is a compendium of summarizations of environmental rules. It is not intended to give readers specific working details of what is required from them, nor can it be used in that manner. Readers of this handbook are encouraged to contact environmental control offices nearest to locations of interest for current regulations affecting them.

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

International Nuclear Information System (INIS)

Shibata, Taku; Dasai, Katsumi

2014-01-01

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

Handbook for Policymackers

DEFF Research Database (Denmark)

Jensen, Ulla Højmark

2016-01-01

The purpose of the handbook is to support policy makers / decision makers by enabling them to make informed decisions about funding for second chance education or the adoption of its methods into mainstream education. The Handbook makes policy recommendations and provides guidelines to structure...... a quality assurance system that evidences success factors of second chance education and the value of informal learning. The handbook draws on the results of the literature review, the development of the quality assurance system (SMS system), the Teachers Handbook and the Organisational Handbook...

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

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

Science.gov (United States)

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

2015-03-18

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

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

International Nuclear Information System (INIS)

Dey, M.K.

1999-01-01

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

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

International Nuclear Information System (INIS)

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

2006-01-01

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

HyApproval - Handbook for the approval of hydrogen refuelling stations - First preliminary achievements

Energy Technology Data Exchange (ETDEWEB)

Wurster, R.; Vandendungen, G.; Guichard, J.; Molag, M.; Barron, J.; Reijalt, M.; Hill, H.J.; Landinger, H.

2007-05-15

The EU-funded project HyApproval [www.hyapproval.org] aims at developing a universal Handbook to facilitate the approval process of Hydrogen Refuelling Stations (HRS) in Europe. The main goal of the HyApproval partnership with 22 partners from Europe and one each from China, Japan and the USA is to provide a Handbook of technical and regulatory requirements to assist authorisation officials, companies and organisations in the safe implementation and operation of HRS. Achievements during the first 15 months: analyses of HRS technology concepts and of equipment and safety distances/ Intermediate Design Paper/ Regulations, Codes and Standards (RCS) review and comparison/ first Handbook draft and first review sessions with HySafe experts/ safety matrix/ identification of accident scenarios/ agreement on safety documentation/ critical review of reliability data from collections and risk studies/ risk assessment (RA) criteria definition and RA/ matrix of acceptability and awareness levels/ database of Fire Associations and First Responders/ calendar of hydrogen events/ general description of CGH{sub 2} interfaces. (au)

Handbook for the design, selection, and construction of a rock cover for retired uranium-mill tailings

International Nuclear Information System (INIS)

Parker, G.B.

1982-09-01

As part of a Nuclear Regulatory Commission (NRC) study to assess the long-term protection of retired uranium mill tailings, the Pacific Northwest Laboratory (PNL) is developing a Handbook to guide the design, selection, and construction of a rock cover (riprap) for decommissioned and reclaimed uranium-mill tailings. The rock cover is designed for long-term protection of mill tailings from wind and water erosion. The purpose of the Handbook is twofold. First, it can be used as a manual by the uranium mill operators for designing, selecting, and constructing a rock cover. Second, the Handbook can be used as a guide to help the NRC evaluate the decommissioning and reclamation plans submitted to them by mill operators. Although the Handbook is not site-specific, it is structured to allow the design of a rock cover for any NRC-licensed tailings impoundment

Electrical transformer handbook

Energy Technology Data Exchange (ETDEWEB)

Hurst, R.W.; Horne, D. (eds.)

2005-07-01

This handbook is a valuable user guide intended for electrical engineering and maintenance personnel, electrical contractors and electrical engineering students. It provides current information on techniques and technologies that can help extend the life of transformers. It discusses transformer testing, monitoring, design, commissioning, retrofitting and other elements involved in keeping electrical transformers in safe and efficient operation. It demonstrates how a power transformer can be put to use and common problems faced by owners. In addition to covering control techniques, testing and maintenance procedures, this handbook covers the power transformer; control electrical power transformer; electrical power transformer; electrical theory transformer; used electrical transformer; down electrical step transformer; electrical manufacturer transformer; electrical picture transformer; electrical transformer work; electrical surplus transformer; current transformer; step down transformer; voltage transformer; step up transformer; isolation transformer; low voltage transformer; toroidal transformer; high voltage transformer; and control power transformer. The handbook includes articles from leading experts on overcurrent protection of transformers; ventilated dry-type transformers; metered load factors for low-voltage, and dry-type transformers in buildings. The maintenance of both dry-type or oil-filled transformers was discussed with reference to sealing, gaskets, oils, moisture and testing. The adoption of dynamic load practices was also discussed along with the reclamation or recycling of used lube oil, transformer dielectric fluids and aged solid insulation. A buyer's guide and directory of transformer manufacturers and suppliers was also included. refs., tabs., figs.

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

International Nuclear Information System (INIS)

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

Security-by-design handbook.

Energy Technology Data Exchange (ETDEWEB)

Snell, Mark Kamerer; Jaeger, Calvin Dell; Scharmer, Carol; Jordan, Sabina Erteza; Tanuma, Koji [Japan Atomic Energy Agency, Tokai-mura, Ibaraki, Japan; Ochiai, Kazuya [Japan Atomic Energy Agency, Tokai-mura, Ibaraki, Japan; Iida, Toru [Japan Atomic Energy Agency, Tokai-mura, Ibaraki, Japan

2013-01-01

This document is a draft SecuritybyDesign (SeBD) handbook produced to support the Work Plan of the Nuclear Security Summit to share best practices for nuclear security in new facility design. The Work Plan calls on States to %E2%80%9Cencourage nuclear operators and architect/engineering firms to take into account and incorporate, where appropriate, effective measures of physical protection and security culture into the planning, construction, and operation of civilian nuclear facilities and provide technical assistance, upon request, to other States in doing so.%E2%80%9D The materials for this document were generated primarily as part of a bilateral project to produce a SeBD handbook as a collaboration between the Japan Atomic Energy Agency (JAEA) Nuclear Nonproliferation Science and Technology Center and Sandia National Laboratories (SNL), which represented the US Department Energy (DOE) National Nuclear Security Administration (NNSA) under a Project Action Sheet PASPP04. Input was also derived based on tours of the Savannah River Site (SRS) and Japan Nuclear Fuel Limited (JNFL) Rokkasho Mixed Oxide Fuel fabrication facilities and associated project lessonslearned. For the purposes of the handbook, SeBD will be described as the systemlevel incorporation of the physical protection system (PPS) into a new nuclear power plant or nuclear facility resulting in a PPS design that minimizes the risk of malicious acts leading to nuclear material theft; nuclear material sabotage; and facility sabotage as much as possible through features inherent in (or intrinsic to) the design of the facility. A fourelement strategy is presented to achieve a robust, durable, and responsive security system.

Semiconductors data handbook

CERN Document Server

Madelung, Otfried

2004-01-01

This volume Semiconductors: Data Handbook contains frequently used data from the corresponding larger Landolt-Börnstein handbooks in a low price book for the individual scientist working in the laboratory. The Handbook contain important information about a large number of semiconductors

Computer science handbook. Vol. 13.3. Environmental computer science. Computer science methods for environmental protection and environmental research

International Nuclear Information System (INIS)

Page, B.; Hilty, L.M.

1994-01-01

Environmental computer science is a new partial discipline of applied computer science, which makes use of methods and techniques of information processing in environmental protection. Thanks to the inter-disciplinary nature of environmental problems, computer science acts as a mediator between numerous disciplines and institutions in this sector. The handbook reflects the broad spectrum of state-of-the art environmental computer science. The following important subjects are dealt with: Environmental databases and information systems, environmental monitoring, modelling and simulation, visualization of environmental data and knowledge-based systems in the environmental sector. (orig.) [de

PSA Review Handbook

International Nuclear Information System (INIS)

Hallman, Anders; Nyman, Ralph; Knochenhauer, Michael

2004-05-01

The Swedish Nuclear Power Inspectorate (SKI) expresses requirements on the performance of PSAs as well as on PSA activities in general in the the regulatory document 'Regulations Concerning Safety in Certain Nuclear Facilities', SKlFS 1998:1. The follow-up of these activities is part of the inspection tasks of the SKI. In view or this, there is a need for documented guidelines on now to perform these inspections and reviews. The SKI PSA Review Handbook is intended to be a support in the SKI inspection and control of the PSA activities or the licensees. These PSA activities include both the organisation and working procedures of the licensee, the layout and contents of the PSA, and its areas of application. Using the regulation SKIFS 1998:1 as a starting point, the review handbook presents important aspects to be considered when judging whether a licensee fulfils the requirements on PSA activities, including the performance of PSA:s or PSA applications. The handbook shall also be a guidance for the review of PSA:s. However, the intention of the PSA Review Handbook is not to be a handbook for how a PSA is performed. The PSA Review Handbook is applicable to all types or initiating events and all operating conditions, and has been structured in a way, which stresses the integrated characteristics of PSA in the creation of the risk picture of a plant. The PSA Review Handbook has been based on the requirements for PSA of nuclear power plants, as this is the most extensive application. However, the relevant parts of it are also applicable when analysing other nuclear installations. The PSA Review Handbook is published as a research report as its contents are judged to be of general interest, and the SKI welcomes comments to the handbook. An update or the PSA Review Handbook may be required as experience with the use of the handbook is acquired and if general PSA requirements change

Fire protection concepts for Timber-Glass Composite façades

Directory of Open Access Journals (Sweden)

Schleicher Andreas

2016-01-01

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

Radiation safety handbook for ionizing and nonionizing radiation

International Nuclear Information System (INIS)

Kincaid, C.B.

1976-10-01

The Handbook is directed primarily to users of radiation sources throughout the Food and Drug Administration. Specific precautions regarding the possession and use of radiation sources in meeting the Agency's objectives are an inherent responsibility of all employees. In addition, the increased emphasis on occupational safety and health and the responsibilities placed on the Department by Public Law and Executive Order make it mandatory that all organizational levels and activities conform to the intent of this Handbook. The policies and procedures described in this document apply to all Agency operators and activities and are intended to protect employees and the general public

Corrosion protection pays off for coal-fired power plants

Energy Technology Data Exchange (ETDEWEB)

Hansen, T.

2006-11-15

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

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

International Nuclear Information System (INIS)

1991-12-01

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

Mechanical engineer's handbook

CERN Document Server

Marghitu, Dan B

2001-01-01

The Mechanical Engineer's Handbook was developed and written specifically to fill a need for mechanical engineers and mechanical engineering students throughout the world. With over 1000 pages, 550 illustrations, and 26 tables the Mechanical Engineer's Handbook is very comprehensive, yet affordable, compact, and durable. The Handbook covers all major areas of mechanical engineering with succinct coverage of the definitions, formulas, examples, theory, proofs, and explanations of all principle subject areas. The Handbook is an essential, practical companion for all mechanic

Technical handbook on the National Arrangements for Incidents involving Radioactivity. NAIR technical handbook

International Nuclear Information System (INIS)

McColl, N.P.; Kruse, P.

2002-01-01

This Technical Handbook contains information for radiation specialists participating in the National Arrangements for Incidents involving Radioactivity (NAIR). Together with the NAIR Users Handbook 2000 edition, it updates and replaces the NAIR Handbook published in 1995. The Users Handbook was designed for those who might seek assistance through NAIR, principally the police or other emergency services. Both Handbooks are reproduced on the NRPB website (www.nrpb.org) and are available from NRPB

Technical resource documents and technical handbooks for hazardous-wastes management

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.; Bliss, T.M.

1986-07-01

The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

Wright, H.A.

1981-01-01

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

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

Science.gov (United States)

2010-01-01

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

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...

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

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

International Nuclear Information System (INIS)

Bernhardt, S.; Grauf, E.

1976-01-01

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

The electric motor handbook

Energy Technology Data Exchange (ETDEWEB)

Hurst, R.W.; Feltham, P. (eds.)

2004-05-01

This handbook outlines the important role that electric motors play in modern society. It covers the field of motor applications from various motor types to their use and repair. It also presents practical applications of electric motors and methods on motor efficiency. More than half of all electricity generated, and 75 per cent of all industrial electricity consumption is consumed by electric motors. Electrical personnel must be aware of all factors involved in electric motors in order to choose and apply the appropriate size of electric motor. These factors include efficiency, sizing and proper application. The efficient use and maximum life expectancy of electric motors depends on proper motor protection, control and maintenance. This handbook includes articles from leading experts on electric motors in modern electrical systems. The content includes: design considerations; proper electric motor sizing techniques; optimal electric motor application; electric motor protection technology; electric motor control principles; electric motor maintenance and troubleshooting; induction electric motors; electric motor bearing currents; electric motor bearing lubrication; electromagnetism; electric motor enclosures; electric motor testing; electric motor repair; DC electric motor; electric motor starters; electric motor brushes; industrial electric motors; electric motor diagrams; AC electric motors; electric motor wiring; electric motor service; electric motor rewinding; electric motor winding; diagram of electric motor wiring; electric motor kit; and, troubleshooting electric motors. A directory of motor manufacturers and suppliers was also included. refs., tabs., figs.

Nuclear materials management handbook. Safeguards, physical protection of nuclear material. 1995 ed.

International Nuclear Information System (INIS)

1995-01-01

Now, very safe and stable supply of electric power has become to be obtained by nuclear energy, and Japan has steadily promoted nuclear power as the basic energy that contributes to overcome the unstable structure of energy supply in Japan highly depending on foreign countries, as shown in the long term plan of the research, development and utilization of nuclear power. Great progress was observed in nuclear fuel recycling in Japan such as the attainment of initial criticality of the prototype FBR 'Monju' and the start of construction of the commercial fuel reprocessing plant in Rokkasho. Recently the recognition of the importance of nuclear substance management has heightened, and the measures for maintaining and strengthening the reliability of nuclear nonproliferation system are investigated. It is important that Japan strictly observes the nuclear nonproliferation system based on the NPT which was extended infinitely. In this handbook, the outline of the measures for nuclear nonproliferation and safeguard and the protection of nuclear substances, the treaties and agreements and the national laws related to these are described. (K.I.)

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

Directory of Open Access Journals (Sweden)

S. N. Sannikov

2017-10-01

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

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

International Nuclear Information System (INIS)

1989-01-01

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

Gen IV Materials Handbook Functionalities and Operation (2B) Handbook Version 2.0

International Nuclear Information System (INIS)

Ren, Weiju

2011-01-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Gen IV Materials Handbook Functionalities and Operation (4A) Handbook Version 4.0

Energy Technology Data Exchange (ETDEWEB)

Ren, Weiju [ORNL

2013-09-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Gen IV Materials Handbook Functionalities and Operation (2B) Handbook Version 2.0

Energy Technology Data Exchange (ETDEWEB)

Ren, Weiju [ORNL

2011-08-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

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

Science.gov (United States)

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

2016-03-01

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

Decision aiding handbooks for managing contaminated food production systems, drinking water and inhabited areas in Europe

DEFF Research Database (Denmark)

Nisbet, A.F.; Brown, J.; Howard, B.J.

2010-01-01

Three handbooks have been developed, in conjunction with a wide range of stakeholders to assist in the management of contaminated food production systems, inhabited areas and drinking water following a radiological incident. The handbooks are aimed at national and local authorities, central...... government departments and agencies, emergency services, radiation protection experts, the agriculture and food production sectors, industry and others who may be affected. The handbooks include management options for application in the different phases of an incident. Sources of contamination considered...

Permitting of Wind Energy Facilities: A Handbook

Energy Technology Data Exchange (ETDEWEB)

NWCC Siting Work Group

2002-08-01

This handbook has been written for individuals and groups involved in evaluating wind projects: decision-makers and agency staff at all levels of government, wind developers, interested parties and the public. Its purpose is to help stakeholders make permitting wind facility decisions in a manner which assures necessary environmental protection and responds to public needs.

Nuclear fuel cycle facility accident analysis handbook

International Nuclear Information System (INIS)

Ayer, J.E.; Clark, A.T.; Loysen, P.; Ballinger, M.Y.; Mishima, J.; Owczarski, P.C.; Gregory, W.S.; Nichols, B.D.

1988-05-01

The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

Crane handbook

CERN Document Server

Dickie, D E

1975-01-01

Crane Handbook offers extensive advice on how to properly handle a crane. The handbook highlights various safety requirements and rules. The aim of the book is to improve the readers' crane operating skills, which could eventually make the book a standard working guide for training operators. The handbook first reminds the readers that the machine should be carefully tested by a regulatory board before use. The text then notes that choosing the right crane for a particular job is vital and explains why this is the case. It then discusses how well-equipped and durable the crane should be. T

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

International Nuclear Information System (INIS)

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

2017-01-01

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

Subsurface Fire Hazards Technical Report

International Nuclear Information System (INIS)

Logan, R.C.

1999-01-01

The results from this report are preliminary and cannot be used as input into documents supporting procurement, fabrication, or construction. This technical report identifies fire hazards and proposes their mitigation for the subsurface repository fire protection system. The proposed mitigation establishes the minimum level of fire protection to meet NRC regulations, DOE fire protection orders, that ensure fire containment, adequate life safety provisions, and minimize property loss. Equipment requiring automatic fire suppression systems is identified. The subsurface fire hazards that are identified can be adequately mitigated

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

International Nuclear Information System (INIS)

Anon.

1997-01-01

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

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

Science.gov (United States)

2010-01-01

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

Fire Protection Informational Exchange

Science.gov (United States)

2016-07-01

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

Impact of fires on nuclear safety

International Nuclear Information System (INIS)

Skvarka, P.; Zmajkovic, I.

1990-01-01

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

Employee Handbook

Energy Technology Data Exchange (ETDEWEB)

Bello, Madelyn

2008-09-05

Welcome to Berkeley Lab. You are joining or are already a part of a laboratory with a sterling tradition of scientific achievement, including eleven Nobel Laureates and thirteen National Medal of Science winners. No matter what job you do, you make Berkeley Lab the outstanding organization that it is. Without your hard work and dedication, we could not achieve all that we have. We value you and thank you for choosing to be part of our community. This Employee Handbook is designed to help you navigate the Lab. With over 3,000 employees, an additional 3,000 guests visiting from countries around the world, a 200-acre campus and many policies and procedures, learning all the ins and outs may seem overwhelming, especially if you're a new employee. However, even if you have been here for a while, this Handbook should be a useful reference tool. It is meant to serve as a guide, highlighting and summarizing what you need to know and informing you where you can go for more detailed information. The general information provided in this Handbook serves only as a brief description of many of the Lab's policies. Policies, procedures and information are found in the Lab's Regulations and Procedures Manual (RPM), Summary Plan Descriptions, University of California policies, and provisions of Contract 31 between the Regents of the University and the U.S. Department of Energy. In addition, specific terms and conditions for represented employees are found in applicable collective bargaining agreements. Nothing in this Handbook is intended to supplant, change or conflict with the previously mentioned documents. In addition, the information in this Handbook does not constitute a contract or a promise of continued employment and may be changed at any time by the Lab. We believe employees are happier and more productive if they know what they can expect from their organization and what their organization expects from them. The Handbook will familiarize you with the

Safe handling of radioactive isotopes. Handbook 42

Energy Technology Data Exchange (ETDEWEB)

NONE

1949-09-15

With the increasing use of radioactive isotopes by industry, the medical profession, and research laboratories, it is essential that certain minimal precautions be taken to protect the users and the public. The recommendations contained in this handbook represent what is believed to be the best available opinions on the subject as of this date. As our experience with radioisotopes broadens, we will undoubtedly be able to improve and strengthen the recommendations for their safe handling and utilization. Through the courtesy of the National Research Council about a year ago, several hundred draft copies of this report were circulated to all leading workers and authorities in the field for comment and criticism. The present handbook embodies all pertinent suggestions received from these people. Further comment will be welcomed by the committee. One of the greatest difficulties encountered in the preparation of this handbook lay in the uncertainty regarding permissible radiation exposure levels - particularly for ingested radioactive materials. The establishment of sound figures for such exposure still remains a problem of high priority for many conditions and radioactive substances. Such figures as are used in this report represent the best available information today. If, in the future, these can be improved upon, appropriate corrections will be issued. The subject will be under continuous study by the two subcommittees mentioned above. The present Handbook has been prepared by the Subcommittee on the Handling of Radioactive Isotopes and Fission Products.

Safe handling of radioactive isotopes. Handbook 42

International Nuclear Information System (INIS)

1949-09-01

With the increasing use of radioactive isotopes by industry, the medical profession, and research laboratories, it is essential that certain minimal precautions be taken to protect the users and the public. The recommendations contained in this handbook represent what is believed to be the best available opinions on the subject as of this date. As our experience with radioisotopes broadens, we will undoubtedly be able to improve and strengthen the recommendations for their safe handling and utilization. Through the courtesy of the National Research Council about a year ago, several hundred draft copies of this report were circulated to all leading workers and authorities in the field for comment and criticism. The present handbook embodies all pertinent suggestions received from these people. Further comment will be welcomed by the committee. One of the greatest difficulties encountered in the preparation of this handbook lay in the uncertainty regarding permissible radiation exposure levels - particularly for ingested radioactive materials. The establishment of sound figures for such exposure still remains a problem of high priority for many conditions and radioactive substances. Such figures as are used in this report represent the best available information today. If, in the future, these can be improved upon, appropriate corrections will be issued. The subject will be under continuous study by the two subcommittees mentioned above. The present Handbook has been prepared by the Subcommittee on the Handling of Radioactive Isotopes and Fission Products

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

International Nuclear Information System (INIS)

Levinson, S.H.

1982-01-01

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

Fighting fires in nuclear plants

International Nuclear Information System (INIS)

Fantom, L.F.; Weldon, G.E.

1978-01-01

Since the Browns Ferry incident, the specter of fires at nuclear plants has been the focus of attention by NRC, the utilities, and the public. There are sophisticated hardware and software available - in the form of fire-protection systems and equipment and training and fire-protection programs. Potential fire losses at nuclear faclities can be staggering. Thus, it behooves all those involved to maximize fire-protection security while simultaneously minimizing the chance of human error, which cancels out the effectiveness of the most up-to-date protective systems and devices

Handbook of radiation shielding data

International Nuclear Information System (INIS)

Courtney, J.C.

1976-07-01

This handbook is a compilation of data on units, conversion factors, geometric considerations, sources of radiation, and the attenuation of photons, neutrons, and charged particles. It also includes related topics in health physics. Data are presented in tabular and graphical form with sufficient narrative for a least first-approximation solutions to a variety of problems in nuclear radiation protection. Members of the radiation shielding community contributed the information in this document from unclassified and uncopyrighted sources, as referenced

Entry-Control Systems Handbook

International Nuclear Information System (INIS)

1978-09-01

The function of an entry-control system in a total Physical Protection System is to allow the movement of authorized personnel and material through normal access routes, yet detect and delay unauthorized movement of personnel and material from uncontrolled areas. The ten chapters of this handbook cover: introduction, credentials, personnel identity verification systems, special nuclear materials monitors, metal detectors, explosives sensors, package search systems, criteria for selection of entry-control equipment, machine-aided manual entry-control systems, and automated entry-control systems. A system example and its cost are included as an appendix

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

Science.gov (United States)

Anthony Bova; Matthew Dickinson

2009-01-01

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

Metallic Fuels Handbook

Energy Technology Data Exchange (ETDEWEB)

Janney, Dawn E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Papesch, Cynthia A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Burkes, Douglas E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cole, James I. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Fielding, Randall S. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Frank, Steven M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hartmann, Thomas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hyde, Timothy A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Keiser, Jr., Dennis D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kennedy, J. Rory [Idaho National Lab. (INL), Idaho Falls, ID (United States); Maddison, Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mariani, Robert D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Middlemas, Scott C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); O' Holleran, Thomas P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sencer, Bulent H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Squires, Leah N. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-08-07

This is not a typical External Report--It is a Handbook. No Abstract is involved. This includes both Parts 1 and 2. The Metallic Fuels Handbook summarizes currently available information about phases and phase diagrams, heat capacity, thermal expansion, and thermal conductivity of elements and alloys in the U-Pu-Zr-Np-Am-La-Ce-Pr-Nd system. Although many sections are reviews and updates of material in previous versions of the Handbook [1, 2], this revision is the first to include alloys with four or more elements. In addition to presenting information about materials properties, the handbook attempts to provide information about how well each property is known and how much variation exists between measurements. Although it includes some results from models, its primary focus is experimental data.

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

Science.gov (United States)

2011-11-14

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

Potentials and limitations of remote fire monitoring in protected areas.

Science.gov (United States)

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

2018-03-01

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

Handbook of energy

CERN Document Server

Cleveland, Cutler J

2013-01-01

Handbook of Energy, Volume II: Chronologies, Top Ten Lists, and Word Clouds draws together a comprehensive account of the energy field from the prestigious and award-winning authors of the Encyclopedia of Energy (2004), The Dictionary of Energy, Expanded Edition (2009), and the Handbook of Energy, Volume I (2013). Handbook of Energy, Volume II takes the wealth of information about historical aspects of energy spread across many books, journals, websites, disciplines, ideologies, and user communities and synthesizes the information in one central repository. This book meets the needs of a di

Fire protection in power plants

International Nuclear Information System (INIS)

Penot, J.

1986-01-01

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

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

Science.gov (United States)

Bahrani, Babak

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

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

Directory of Open Access Journals (Sweden)

Iraj Alimohammadi

2015-01-01

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

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

International Nuclear Information System (INIS)

Isaksson, S.

1996-01-01

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

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

International Nuclear Information System (INIS)

Good, D.E.

1994-09-01

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

EURANOS. The Handbook Users Group (HUG)

DEFF Research Database (Denmark)

Nisbet, A.F.; Andersson, Kasper Grann; Carlé, B.

Three handbooks to assist in the management of contaminated food production systems, inhabited areas and drinking water supplies have been developed in conjunction with a wide range of stakeholders in Europe. These handbooks are living documents that will require updating from time to time.......eu-neris.net) to facilitate information exchange. Emergency centres in Member States not involved in the development of the handbooks were invited to take part in demonstration activities to establish whether the handbooks were useful for the purposes of contingency planning and accident management. Results from...... to remain state-of-the-art. To address this need, a handbook users’ group (HUG) was established in 2007 to provide a platform for maintaining the handbooks and to build a network of users for both the generic handbooks and any subsequently customised versions. A web site was set up (www...

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

CERN Document Server

2017-01-01

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

Cookstove handbook

Energy Technology Data Exchange (ETDEWEB)

1985-01-01

Firewood has become a matter of serious concern due to dwindling forest resources coupled with excessive consumption resulting from wasteful and inefficient methods of cooking. Efforts are now being made by various researchers to design more efficient and less expensive cooking stoves. This handbook is a compendium of more than 40 different types of solid-fuel cooking stoves which can be manufactured using locally available materials and skills. The evolution of cooking stoves from open-fire cooking arrangements is described. One chapter is devoted to cooking-stove design considerations, including performance, combustion, oxygen requirements, surrounding air effects, near-by solid-surface effects, the excess-air concept, heat transfer, geometrical efficiency and stove components. The bulk of the document introduces traditionally used and improved cooking-stove designs for wood and charcoal burning in detail providing information on fuels, stove materials, and advantages and disadvantages. A description of 14 different laboratory investigations on efficiency aspects of cooking stoves is presented. Annexes are devoted to the composition and properties of wood, a summary of characteristics of the stoves described in the text, the efficiencies of commonly used cooking stoves with different fuels and a glossary. 82 references.

Handbook of systems toxicology

National Research Council Canada - National Science Library

Casciano, Daniel A; Sahu, Saura C

2011-01-01

"In the first handbook to comprehensively cover the emerging area of systems toxicology, the Handbook of Systems Toxicology provides an authoritative compilation of up-to-date developments presented...

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

International Nuclear Information System (INIS)

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

1997-12-01

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

The water handbook. 7. ed.

International Nuclear Information System (INIS)

Bryknar, F.Z.

1988-01-01

This 7th edition of the water handbook brings up to date the last available, sixth edition of 1982. The arrangement is the same as before: explanation of symbols and units; basic principles of water chemistry; behaviour of water and additives in nuclear power plant operation; chemical engineering aspects of water treatment; standard values for operating water; operating analysis; chemicals for water treatment; corrosion and corrosion protection in steam generators; water in nuclear facilities; cleaning and acid cleaning of steam generators; conservation of steam generators; tables and diagrams; bibliography; keyword index. New terms and measuring units have been worked in, and the tables on ion exchangers have been revised. Amendments of regulatory provisions have been included where appropriate (VGB rules, Radiation Protection Ordinance). (RB) [de

Cable fire tests in France

International Nuclear Information System (INIS)

Kaercher, M.

2000-01-01

Modifications are being carried out in all French nuclear power plants to improve fire safety. These modifications are based on a three level defense in depth concept: fire preventing, fire containing and fire controlling. Fire containing requires many modifications such as protection of cable races and assessment of fire propagation which both need R and D development. On one hand, cable wraps made with mineral wool were tested in all configurations including effect of aging, overheating and fire and qualified for the use as protection from common failure modes. On the other hand, cables races in scale one were subject to gas burner or solvent pool fire to simulate ignition and fire propagation between trays and flash over situations. These tests have been performed under several typical lay out conditions. The results of the tests can be used as input data in computer modelling for validation of fire protection measures. (orig.) [de

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

Science.gov (United States)

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

1975-01-01

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

Low-level-waste-treatment handbook

International Nuclear Information System (INIS)

Clinton, S.D.; Goeller, H.E.; Holladay, D.W.; Donaldson, T.L.

1982-01-01

The initial draft of the Low-Level Waste Treatment Handbook has been prepared and submitted to the DOE Low-Level Waste Management Program for review and comment. A revised draft is scheduled to be delivered to DOE Headquarters in December 1982. The Handbook is designed to be useful to all individuals and groups concerned with low-level wastes. It is one of several volumes that will ultimately comprise a Low-Level Waste Technology Handbook. The objective of the Low-Level Waste Treatment Handbook is to present an overview of current practices related to the segregation, classification, volume reduction, solidification, handling, packaging, and transportation of LLW for disposal in a shallow land burial facility. The Handbook is intended to serve as a guide to individuals interested in the treatment and handling of low-level radioactive waste. The Handbook will not explicitly tell the user how to design and operate LLW treatment facilities, but rather will identify (1) kinds of information required to evaluate the options, (2) methods that may be used to evaluate these options, and (3) limitations associated with the selection of the treatment options. The focus of the Handbook is providing guidance on how to do waste treatment for disposal by shallow land burial

Handbook of antenna technologies

CERN Document Server

Liu, Duixian; Nakano, Hisamatsu; Qing, Xianming; Zwick, Thomas

2016-01-01

The Handbook of Antenna Technologies aims to present the rapid development of antenna technologies, particularly in the past two decades, and also showcasing the newly developed technologies and the latest applications. The handbook will provide readers with the comprehensive updated reference information covering theory, modeling and optimization methods, design and measurement, new electromagnetic materials, and applications of antennas. The handbook will widely cover not only all key antenna design issues but also fundamentals, issues related to antennas (transmission, propagation, feeding structure, materials, fabrication, measurement, system, and unique design challenges in specific applications). This handbook will benefit the readers as a full and quick technical reference with a high-level historic review of technology, detailed technical descriptions and the latest practical applications.

Ewe (for Togo): Grammar Handbook. Peace Corps Language Handbook Series.

Science.gov (United States)

Kozelka, Paul R.

This handbook is composed of: (1) 20 grammar lessons; (2) an introduction to the handbook and to the Ewe language; (3) an appendix presenting the most important differences between Ewe and Mina, the lingua franca in the capital and in markets, offices, and work-sites throughout Togo; (4) answers to written summary exercises; (5) an Ewe-English…

FINODEX Handbook for Entrepreneurs

DEFF Research Database (Denmark)

The handbook provides short introductions to necessary knowledge for applicants in the two calls in October 2014 and June 2015 where they can present an idea for product development and apply for up to 10,000 Euro. Furthermore, the handbook is relevant for the next phase, where the selected approx....... 50 projects elaborate detailed technical and market plans. Last, the handbook provides links to further study and information about how to get help in later phases....

Energy Efficiency Governance: Handbook

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This handbook has been written to assist EE practitioners, government officials and stakeholders to establish effective EE governance structures for their country. The handbook provides readers with relevant information in an accessible format that will help develop comprehensive and effective governance mechanisms. For each of the specific topics dealt with (see Figure 1 in the Handbook), the IEA offers guidelines for addressing issues, or directs readers to examples of how such issues have been dealt with by specific countries.

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

Directory of Open Access Journals (Sweden)

Long Shi

2015-10-01

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

DOE handbook: Integrated safety management systems (ISMS) verification. Team leader's handbook

International Nuclear Information System (INIS)

1999-06-01

The primary purpose of this handbook is to provide guidance to the ISMS verification Team Leader and the verification team in conducting ISMS verifications. The handbook describes methods and approaches for the review of the ISMS documentation (Phase I) and ISMS implementation (Phase II) and provides information useful to the Team Leader in preparing the review plan, selecting and training the team, coordinating the conduct of the verification, and documenting the results. The process and techniques described are based on the results of several pilot ISMS verifications that have been conducted across the DOE complex. A secondary purpose of this handbook is to provide information useful in developing DOE personnel to conduct these reviews. Specifically, this handbook describes methods and approaches to: (1) Develop the scope of the Phase 1 and Phase 2 review processes to be consistent with the history, hazards, and complexity of the site, facility, or activity; (2) Develop procedures for the conduct of the Phase 1 review, validating that the ISMS documentation satisfies the DEAR clause as amplified in DOE Policies 450.4, 450.5, 450.6 and associated guidance and that DOE can effectively execute responsibilities as described in the Functions, Responsibilities, and Authorities Manual (FRAM); (3) Develop procedures for the conduct of the Phase 2 review, validating that the description approved by the Approval Authority, following or concurrent with the Phase 1 review, has been implemented; and (4) Describe a methodology by which the DOE ISMS verification teams will be advised, trained, and/or mentored to conduct subsequent ISMS verifications. The handbook provides proven methods and approaches for verifying that commitments related to the DEAR, the FRAM, and associated amplifying guidance are in place and implemented in nuclear and high risk facilities. This handbook also contains useful guidance to line managers when preparing for a review of ISMS for radiological

Fire protection in the nuclear power plant

International Nuclear Information System (INIS)

Takuma, Masao

1977-01-01

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

NASA Systems Engineering Handbook

Science.gov (United States)

Hirshorn, Steven R.; Voss, Linda D.; Bromley, Linda K.

2017-01-01

The update of this handbook continues the methodology of the previous revision: a top-down compatibility with higher level Agency policy and a bottom-up infusion of guidance from the NASA practitioners in the field. This approach provides the opportunity to obtain best practices from across NASA and bridge the information to the established NASA systems engineering processes and to communicate principles of good practice as well as alternative approaches rather than specify a particular way to accomplish a task. The result embodied in this handbook is a top-level implementation approach on the practice of systems engineering unique to NASA. Material used for updating this handbook has been drawn from many sources, including NPRs, Center systems engineering handbooks and processes, other Agency best practices, and external systems engineering textbooks and guides. This handbook consists of six chapters: (1) an introduction, (2) a systems engineering fundamentals discussion, (3) the NASA program project life cycles, (4) systems engineering processes to get from a concept to a design, (5) systems engineering processes to get from a design to a final product, and (6) crosscutting management processes in systems engineering. The chapters are supplemented by appendices that provide outlines, examples, and further information to illustrate topics in the chapters. The handbook makes extensive use of boxes and figures to define, refine, illustrate, and extend concepts in the chapters.

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

International Nuclear Information System (INIS)

Rodriguez Sanjuan, G.

1996-01-01

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

Learning fire-fighting lessons after Chernobyl

International Nuclear Information System (INIS)

Anon.

1990-01-01

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

EURANOS. Generic handbook for assisting in the management of contaminated food production systems in Europe following a radiological emergency

DEFF Research Database (Denmark)

Nisbet, A.F.; Howard, B.J.; Jones, A.

production sectors and others who may be affected. The handbook is a living document that requires updating from time to time to remain state-of-the-art and customisation of the generic handbook is an essential part of its use within individual countries. The handbook includes management options......The handbook for food production systems has been developed as a result of a series of UK and European initiatives involving a wide range of stakeholders. It is aimed at national and local authorities, central government departments and agencies, radiation protection experts, agriculture and food...... for application in the pre-release, emergency and longer term phases of an incident. Sources of contamination considered in the handbook are nuclear accidents, radiological dispersion devices and satellite accidents. Agricultural and domestic food production systems are considered, including the gathering of free...

Shallow-land-burial handbook

International Nuclear Information System (INIS)

Boegly, W.J. Jr.; Davis, E.C.

1981-01-01

The initial draft of the Shallow-Land Burial Handbook has been prepared and submitted to the DOE Low-Level Waste Management Program for review and comment. The Handbook informs the reader of the current way in which low-level wastes are being handled, outlines the legal and institutional problems that would be involved in developing and licensing such a facility, and describes in some detail the considerations and data needs for siting, designing, operating, and closing such a facility. The initial draft is not a Handbook that provides answers to all questions, nor insures that following the steps detailed in the Handbook guarantees that the facility will be licensed. It does illustrate the types of actions that must be considered and the types of information required to achieve successful operations

Methodology - PSA Regulatory handbook. Comparisons to a modern PSA study

International Nuclear Information System (INIS)

Bostroem, Urban; Jung, Gunnar; Flodin, Yngve

2003-03-01

The regulatory handbook is applicable to all types of initiating events and all operating conditions. It should be noted that it does not make the traditional subdivision of PSA into internal and external events, level 1 and level 2 PSA, or power operation and shut-down. The reason for this is that this has given the regulatory handbook a more logical structure, and that this approach underlines the integrated character of PSA when it comes to creating the plan risk profile. The regulatory handbook has been structured following the requirements on a PSA for a nuclear power plant, as this is the most demanding application. However, it is applicable also to the analysis of other nuclear installations. The purpose of the comparative review presented in this report has been to, as part of a quality review establish the PSA Handbook, compare (parts of) the handbook and its criteria with a recent PSA analysis, and to identify major discrepancies. Considerable weight has also been allocated to a review of the plant model (Risk Spectrum event trees and fault trees). The results presented in the report are not based on a complete review of the PSA in question (or of the complete PSA Handbook). Following discussions between the SKI and SwedPower, and based on the experience of the SwedPower reviewers, the following issues were chosen to be the main parts of the project: 1) General comparison according to content and transparency - Levels of ambition in PSA Handbook, PSA method description and actual PSA report. 2) Detailed comparison of: Selected component failure data - Assumptions regarding room events - CCI frequencies, realism, identification, categorisation - Taking credit for non-safety classified systems - Event tree modelling - Presentation of results 3) Fault tree model, specifically - Time frame for crediting of battery capacity - Modelling of regulators - Modelling of dependencies for room events - general quality, like how the paper documentation and the logic

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

International Nuclear Information System (INIS)

Fredholm, Lotta

2010-02-01

The aim of this report has been to detect and describe differences between rules regarding fire safety and the interpretation of the rules and make suggestions on how all parties involved are able to develop a harmonized approach to the fire conditions and how fire requirements aspects can be optimized and modernized. International and national laws and requirements for fire protection are compared and analyzed with the content and structure of the USNRCs RG.1189, which is considered the document that has the most complete accounts of the fire requirements both in terms of structure and content. The national laws, rules and guidelines that have been studied are general fire protection rules as well as nuclear specific rules. The studied national rules also includes Safety Analysis Reports (SAR) and Technical Specifications (TS). This study shows that the Swedish SAR and TS are markedly different from each other in how the fire requirements are presented as well as the methodology and level of detail of how they are fulfilled. These differences make it difficult to compare the quality of the fire protection between different sites and it also makes it different to learn from each other. The main reason to the differences are the lack of national guidance of how to fulfil the general requirements. The main conclusion of the screening of national requirements, is that many of the references used in the SAR are not suited for operation at a nuclear plant. The differences are often the purpose, examples of purposes that are not necessarily met by complying with national laws, rules, advices are: - Prevent fire to influence redundant safety equipment in different fire cells. - Prevent fire to influence redundant safety equipment in the same fire cell. - Prevent extensive consequences of fire in cable rooms. - Prevent extensive consequences of fires in oil that are not included in the Swedish regulation for handling highly flammable liquids. The international regulations

Nuclear Power Plant Fire Protection Research Program

International Nuclear Information System (INIS)

Datta, A.

1985-07-01

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

Java EE 7 handbook

CERN Document Server

Pilgrim, Peter A

2013-01-01

Java EE 7 Handbook is an example based tutorial with descriptions and explanations.""Java EE 7 Handbook"" is for the developer, designer, and architect aiming to get acquainted with the Java EE platform in its newest edition. This guide will enhance your knowledge about the Java EE 7 platform. Whether you are a long-term Java EE (J2EE) developer or an intermediate level engineer on the JVM with just Java SE behind you, this handbook is for you, the new contemporary Java EE 7 developer!

Alternative approach for fire suppression of class A, B and C fires in gloveboxes

Energy Technology Data Exchange (ETDEWEB)

Rosenberger, Mark S [Los Alamos National Laboratory; Tsiagkouris, James A [Los Alamos National Laboratory

2011-02-10

Department of Energy (DOE) Orders and National Fire Protection Association (NFPA) Codes and Standards require fire suppression in gloveboxes. Several potential solutions have been and are currently being considered at Los Alamos National Laboratory (LANL). The objective is to provide reliable, minimally invasive, and seismically robust fire suppression capable of extinguishing Class A, B, and C fires; achieve compliance with DOE and NFPA requirements; and provide value-added improvements to fire safety in gloveboxes. This report provides a brief summary of current approaches and also documents the successful fire tests conducted to prove that one approach, specifically Fire Foe{trademark} tubes, is capable of achieving the requirement to provide reliable fire protection in gloveboxes in a cost-effective manner.

Gen IV Materials Handbook Implementation Plan

International Nuclear Information System (INIS)

Rittenhouse, P.; Ren, W.

2005-01-01

A Gen IV Materials Handbook is being developed to provide an authoritative single source of highly qualified structural materials information and materials properties data for use in design and analyses of all Generation IV Reactor Systems. The Handbook will be responsive to the needs expressed by all of the principal government, national laboratory, and private company stakeholders of Gen IV Reactor Systems. The Gen IV Materials Handbook Implementation Plan provided here addresses the purpose, rationale, attributes, and benefits of the Handbook and will detail its content, format, quality assurance, applicability, and access. Structural materials, both metallic and ceramic, for all Gen IV reactor types currently supported by the Department of Energy (DOE) will be included in the Gen IV Materials Handbook. However, initial emphasis will be on materials for the Very High Temperature Reactor (VHTR). Descriptive information (e.g., chemical composition and applicable technical specifications and codes) will be provided for each material along with an extensive presentation of mechanical and physical property data including consideration of temperature, irradiation, environment, etc. effects on properties. Access to the Gen IV Materials Handbook will be internet-based with appropriate levels of control. Information and data in the Handbook will be configured to allow search by material classes, specific materials, specific information or property class, specific property, data parameters, and individual data points identified with materials parameters, test conditions, and data source. Details on all of these as well as proposed applicability and consideration of data quality classes are provided in the Implementation Plan. Website development for the Handbook is divided into six phases including (1) detailed product analysis and specification, (2) simulation and design, (3) implementation and testing, (4) product release, (5) project/product evaluation, and (6) product

A Poetry Handbook.

Science.gov (United States)

Oliver, Mary

Intended to impart the basic ways a poem is constructed, this concise handbook is a prose guide to writing poetry. The handbook talks about meter and rhyme, form and diction, sound and sense, iambs and trochees, couplets and sonnets, and how and why this should matter to any person writing or reading poetry. Interspersing history and analysis with…

Manual fire fighting tactics at Nuclear Power Plant

International Nuclear Information System (INIS)

Jee, Moon Hak; Moon, Chan Kook

2012-01-01

The general requirements of fire protection at nuclear power plant (NPP) are fire protection program, fire hazard analysis, and fire prevention features. In addition, specific fire protection requirements such as water supplies, fire detection, fire protection of safe related equipment, and safe shutdown capabilities must be provided. Particularly, manual fire fighting is required as specific requirements with the provisions to secure manual fire suppression, fire brigade and its training, and administrative controls for manual fire fighting. If a fire is alarmed and confirmed to be a real fire, the fire brigade must take manual fire fighting activities as requested at fire protection program. According to the present requirements in itself, there is not any specific manual fire fighting ways or practical strategies. In general, fire zones or compartments at NPPs are built in a confined condition. In theory, the fire condition will change from a combustible-controlled fire to a ventilation-governing fire with the time duration. In case of pool fire with the abundant oxygen and flammable liquid, it can take just a few minutes for the flash-over to occur. For the well-confined fire zone, it will change from a flame fire to a smoldering state before the entrance door is opened by the fire brigade. In this context, the manual fire fighting activities must be based on a quantitative analysis and a fire risk evaluation. At this paper, it was suggested that the fire zones at NPPs should be grouped on the inherent functions and fire characteristics. Based on the fire risk characteristics and the fire zone grouping, the manual fire fighting tactics are suggested as an advanced fire fighting solution

Development of a Smart Residential Fire Protection System

OpenAIRE

Juhwan Oh; Zhongwei Jiang; Henry Panganiban

2013-01-01

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

The SKI-project External events - Phase 2. Estimation of fire frequencies per plant and per building

International Nuclear Information System (INIS)

Poern, K.

1996-08-01

The Swedish-Finnish handbook for initiating event frequencies, I-Book, does not contain any fire frequencies. This matter of fact is not defensible considering the substantial risk contribution caused by fires. In the PSAs performed hitherto the initiating fire frequencies have been determined from case to case. Because data are usually very scarce in these areas it is very important to develop unique definitions, to systematically utilize both international and national experiences and to establish an appropriate statistical estimation method. It is also important to present the accumulated experience such that it can be used for different purposes, not only within PSA but also in the concrete fire preventive work. During phase 1 of the project External Events an inventory was made of existing methods for probabilistic fire analysis in general. During phase 2 of the project it was decided to initialize the work on a complementary handbook, called X-Book, in order to encompass the frequencies of system external events, i.e. initiating events that are caused by events occurring outside the system boundaries. In Version 1 of the X-Book the attention is mainly focussed on the estimation of initiating fire frequencies, per plant and per building. This estimation is basically founded on reports that the power companies have collected for this specific purpose. This report describes the statistical model and method that have been used in the estimation process. The methodological results achieved may, possibly after some modification, be applicable also to other types of system external events

76 FR 60474 - Commercial Item Handbook

Science.gov (United States)

2011-09-29

... DEPARTMENT OF DEFENSE Defense Acquisition Regulations System Commercial Item Handbook AGENCY.... SUMMARY: DoD has updated its Commercial Item Handbook. The purpose of the Handbook is to help acquisition personnel develop sound business strategies for procuring commercial items. DoD is seeking industry input on...

Development of a security-by-design handbook

International Nuclear Information System (INIS)

Olson, David L.; Snell, Mark Kamerer; Iida, Toru; Ochiai, Kazuya; Tanuma, Koji

2010-01-01

There is an increasing awareness that efficient and effective nuclear facility design is best achieved when requirements from the 3S disciplines Safety, Safeguards, and Security - are balanced and intrinsic to the facility design. This can be achieved when policy, processes, methods, and technologies are understood and applied in these areas during all phases of the design process. For the purposes of this paper, Security-by-design will be defined as the system level incorporation of the physical protection system (PPS) into a new or retrofitted nuclear power plant (NPP) or nuclear facility (NF) resulting in intrinsic security. Security-by-design can also be viewed as a framework to achieve robust and durable security systems. This paper reports on work performed to date to create a Security-by-Design Handbook, under a bilateral agreement between the United States and Japan, specifically, a review of physical protection principles and best practices, and a decommissioning to better understand where these principles and practices can be applied. This paper describes physical protection principles and best practices to achieve security-by- design that were gathered from International, Japanese, and U.S. sources. Principles are included for achieving security early in the design process where security requirements are typically less costly and easier to incorporate. The paper then describes a generic design process that covers the entire facility lifecycle from scoping and planning of the project to decommissioning and decontamination. Early design process phases, such as conceptual design, offer opportunities to add security features intrinsic to the facility design itself. Later phases, including design engineering and construction, are important for properly integrating security features into a coherent design and for planning for and assuring the proper performance of the security system during the operation and decommissioning of the facility. The paper also

Fire protection at the Mochovce nuclear power plant

International Nuclear Information System (INIS)

Molnarova, Zuzana; Zeman, Peter

2009-01-01

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

Fire detection in warehouse facilities

CERN Document Server

Dinaburg, Joshua

2013-01-01

Automatic sprinklers systems are the primary fire protection system in warehouse and storage facilities. The effectiveness of this strategy has come into question due to the challenges presented by modern warehouse facilities, including increased storage heights and areas, automated storage retrieval systems (ASRS), limitations on water supplies, and changes in firefighting strategies. The application of fire detection devices used to provide early warning and notification of incipient warehouse fire events is being considered as a component of modern warehouse fire protection.Fire Detection i

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

Science.gov (United States)

2010-01-01

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

30 CFR 75.1103-6 - Automatic fire sensors; actuation of fire suppression systems.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Automatic fire sensors; actuation of fire... Protection § 75.1103-6 Automatic fire sensors; actuation of fire suppression systems. Point-type heat sensors or automatic fire sensor and warning device systems may be used to actuate deluge-type water systems...

Gen IV Materials Handbook Functionalities and Operation

International Nuclear Information System (INIS)

Ren, Weiju

2009-01-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

Gen IV Materials Handbook Functionalities and Operation

Energy Technology Data Exchange (ETDEWEB)

Ren, Weiju [ORNL

2009-12-01

This document is prepared for navigation and operation of the Gen IV Materials Handbook, with architecture description and new user access initiation instructions. Development rationale and history of the Handbook is summarized. The major development aspects, architecture, and design principles of the Handbook are briefly introduced to provide an overview of its past evolution and future prospects. Detailed instructions are given with examples for navigating the constructed Handbook components and using the main functionalities. Procedures are provided in a step-by-step fashion for Data Upload Managers to upload reports and data files, as well as for new users to initiate Handbook access.

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

International Nuclear Information System (INIS)

1984-01-01

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

Impacts of fire, fire-fighting chemicals and post-fire stabilization techniques on the soil-plant system

OpenAIRE

Fernández Fernández, María

2017-01-01

Forest fires, as well as fire-fighting chemicals, greatly affect the soil-plant system causing vegetation loss, alterations of soil properties and nutrient losses through volatilization, leaching and erosion. Soil recovery after fires depends on the regeneration of the vegetation cover, which protects the soil and prevents erosion. Fire-fighting chemicals contain compounds potentially toxic for plants and soil organisms, and thus their use might hamper the regeneration of burnt ecosystems. In...

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

International Nuclear Information System (INIS)

Good, D.E.

1995-09-01

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

Procurement Career Management Handbook.

Science.gov (United States)

Department of the Treasury, Washington, DC.

This handbook is the result of the Treasury Department's efforts to increase professionalism among its procurement employees nationwide through its Procurement Career Management Program. First, the scope and objectives of the Procurement Career Management Program are discussed. The remaining sections of the handbook deal with the following program…

Idaho National Engineering and Environmental Laboratory Wildland Fire Management Environmental Assessment

Energy Technology Data Exchange (ETDEWEB)

Irving, John S

2003-04-01

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

Forest Fire Occurrence in Southern Counties, 1966-1975

Science.gov (United States)

M.L. Doolittle

1977-01-01

Forest fire occurrence data for individual protection units generally are unavailable outside particular state organization. Number of fires, area protected and fire occurrence rate (fires per 1,000,000 acres) from 1966 to 1975, are presented in tables for the 993 counties under protection in 13 southern states. These data are compared with data for the preceeding...

Nuclear power plant fire protection: philosophy and analysis

International Nuclear Information System (INIS)

Berry, D.L.

1980-05-01

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

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

Directory of Open Access Journals (Sweden)

Aiming Zhou

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

32 CFR 644.140 - Physical protection.

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Physical protection. 644.140 Section 644.140... ESTATE HANDBOOK Acquisition Acquisition by Leasing § 644.140 Physical protection. It is essential that the Division or District Engineer make provision for the physical protection for all facilities under...

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.)

The preservation management handbook a 21st-century guide for libraries, archives, and museums

CERN Document Server

Harvey, Ross

2014-01-01

Cultural heritage professionals - museum curators, museum professionals, archivists and librarians - work with their specialized knowledge to prioritize the needs of their collections. Preservation managers draw on experts in climate control, fire safety, pest management and more in developing the large overview of a collection and its needs. And all the special materials within the collections have their experts too. Here, in one volume, The Preservation Management Handbook offers a wide range of topic-specific expertise that comprises both an enduring text for preservation students as well a

Warehouse Sanitation Workshop Handbook.

Science.gov (United States)

Food and Drug Administration (DHHS/PHS), Washington, DC.

This workshop handbook contains information and reference materials on proper food warehouse sanitation. The materials have been used at Food and Drug Administration (FDA) food warehouse sanitation workshops, and are selected by the FDA for use by food warehouse operators and for training warehouse sanitation employees. The handbook is divided…

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

Directory of Open Access Journals (Sweden)

Suryoputro M. Ragil

2018-01-01

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

Travel time data collection handbook

Science.gov (United States)

1998-03-01

This Travel Time Data Collection Handbook provides guidance to transportation : professionals and practitioners for the collection, reduction, and presentation : of travel time data. The handbook should be a useful reference for designing : travel ti...

Recommendations for waste disposal of phosphorus-32 and iodine-131 for medical users. Handbook 49

Energy Technology Data Exchange (ETDEWEB)

NONE

1951-11-02

With the increasing use of radioactive isotopes by industry, the medical profession, and research laboratories, it is essential that certain minimal precautions be taken to protect the users and the public. The recommendations contained in this Handbook represent what is believed to be the best available opinions on the subject as of this date. As our experience with radioisotopes broadens, we will undoubtedly be able to improve and strengthen the recommendations for their safe handling, utilization, and disposal of wastes. Comments on those recommendations will be welcomed by the committee. One of the greatest difficulties encountered in the preparation of this Handbook lay in the uncertainty regarding permissible radiation exposure levels, particularly for ingested radioactive materials. The establishment of sound figures for such exposure still remains a problem of high priority for many conditions and radioactive substances. Such figures as are used in this report represent the best available information today. If, in the future, these can be improved upon, appropriate corrections will be issued. The subject will be under continuous study by the subcommittees mentioned above. The best available information on permissible radiation levels and permissible quantities of ingested radioactive material may be found in the Recommendations of the International Commission on Radiological Protection and the Supplement to these recommendations in NBS Handbook 47. It should be borne in mind, however, that even the values given in that Handbook may be subject to change. As the problem of the disposal of radioactive wastes varies over such wide limits, depending upon the usage to which the isotopes are put, the committee has decided that it will not be feasible to incorporate in one volume broad recommendations covering all situations and materials. This is the first of a series of such reports. The present Handbook has been prepared by the Subcommittee on Waste Disposal and

Recommendations for waste disposal of phosphorus-32 and iodine-131 for medical users. Handbook 49

International Nuclear Information System (INIS)

1951-01-01

With the increasing use of radioactive isotopes by industry, the medical profession, and research laboratories, it is essential that certain minimal precautions be taken to protect the users and the public. The recommendations contained in this Handbook represent what is believed to be the best available opinions on the subject as of this date. As our experience with radioisotopes broadens, we will undoubtedly be able to improve and strengthen the recommendations for their safe handling, utilization, and disposal of wastes. Comments on those recommendations will be welcomed by the committee. One of the greatest difficulties encountered in the preparation of this Handbook lay in the uncertainty regarding permissible radiation exposure levels, particularly for ingested radioactive materials. The establishment of sound figures for such exposure still remains a problem of high priority for many conditions and radioactive substances. Such figures as are used in this report represent the best available information today. If, in the future, these can be improved upon, appropriate corrections will be issued. The subject will be under continuous study by the subcommittees mentioned above. The best available information on permissible radiation levels and permissible quantities of ingested radioactive material may be found in the Recommendations of the International Commission on Radiological Protection and the Supplement to these recommendations in NBS Handbook 47. It should be borne in mind, however, that even the values given in that Handbook may be subject to change. As the problem of the disposal of radioactive wastes varies over such wide limits, depending upon the usage to which the isotopes are put, the committee has decided that it will not be feasible to incorporate in one volume broad recommendations covering all situations and materials. This is the first of a series of such reports. The present Handbook has been prepared by the Subcommittee on Waste Disposal and

The fire course and consequences to be drawn from the fire in the Browns Ferry nuclear power station

International Nuclear Information System (INIS)

Hoffmeister, N.

1977-01-01

After a short description of the fire course and the fire fighting measures during the cable fire at Browns Ferry nuclear power station, the effects on the safety system are given in chronological order, and consequences are drawn for a general fire protection programme for nuclear power plants. In this context, the licensing guideline of the NRC for fire protection in nuclear power plants is mentioned, which took particular account of the consequences to be drawn from the Browns Ferry fire. (ORU) [de

The importance of fire simulation in fire prediction

Directory of Open Access Journals (Sweden)

Jevtić Radoje B.

2014-01-01

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

Mobile retroreflectivity best practices handbook.

Science.gov (United States)

2009-07-01

This handbook documents best practices related to proper use of the mobile retroreflectometer, sampling of : sites for data collection, and handling of mobile retroreflectivity data. The best practices described in this : handbook are derived from th...

CRC handbook of modern telecommunications

CERN Document Server

Morreale, Patricia A

2001-01-01

This authoritative handbook, contributed to by a team of international experts, covers the most dynamic areas in the changing telecommunications landscape. Written for telecommunications specialists who implement the new technologies, The CRC Handbook of Modern Telecommunications is an excellent companion volume to the authors' The Telecommunications Handbook, but stands well on its own, as it extends the range of topics to include voice over Internet, traffic management, quality of service, and other dominant future trends. It is an indispensable reference for all professionals working in the

Fire simulation of pool fire with effects of a ventilation controlled compartment by using a fire model, CFAST

International Nuclear Information System (INIS)

Hattori, Yasuo; Suto, Hitoshi; Shirai, Koji; Eguchi, Yuzuru; Matsuyama, Ken

2015-01-01

The basic performance for numerical analysis of fire parameters in a compartment by using a zone model, CFAST (Consolidated model of Fire growth And Smoke Transport), which has been widely applied for fire protection design of buildings, was examined. Special attentions were paid to the effects of compartment geometry under poor ventilation conditions with mechanical systems. The simulations were carried out under conditions corresponding to previous experiments, in which fire parameters have been precisely measured. The comparison between numerical simulations and experiments indicated that the CFAST principally has a capability to represent the time-histories of air-temperature in the high air-temperature layer generated in the vicinity of ceiling of the compartment, by applying the proper boundary conditions. These results suggest that numerical analysis for time-series of air temperature and smoke concentration in compartments must be a powerful tool for discussion on validity of fire protection schemes. (author)

Fire hazard analysis for fusion energy experiments

International Nuclear Information System (INIS)

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

1979-01-01

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

Overview of the 2014 Edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook)

Energy Technology Data Exchange (ETDEWEB)

John D. Bess; J. Blair Briggs; Jim Gulliford; Ian Hill

2014-10-01

The International Reactor Physics Experiment Evaluation Project (IRPhEP) is a widely recognized world class program. The work of the IRPhEP is documented in the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook). Integral data from the IRPhEP Handbook is used by reactor safety and design, nuclear data, criticality safety, and analytical methods development specialists, worldwide, to perform necessary validations of their calculational techniques. The IRPhEP Handbook is among the most frequently quoted reference in the nuclear industry and is expected to be a valuable resource for future decades.

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

Science.gov (United States)

Jia, S.; Gillespie, T. W.

2016-12-01

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

Intumescent paint as fire protection coating

Directory of Open Access Journals (Sweden)

R. B. R.S. OLIVEIRA

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

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

Science.gov (United States)

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

2017-09-01

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

Present status of Japanese Criticality Safety Handbook

International Nuclear Information System (INIS)

Okuno, Hiroshi

1999-01-01

A draft of the second edition of Nuclear Criticality Safety Handbook has been finalized, and it is under examination by reviewing committee for JAERI Report. Working Group designated for revising the Japanese Criticality Safety Handbook, which is chaired by Prof. Yamane, is now preparing for 'Guide on Burnup Credit for Storage and Transport of Spent Nuclear Fuel' and second edition of 'Data Collection' part of Handbook. Activities related to revising the Handbook might give a hint for a future experiment at STACY. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

IRPhEP-handbook, International Handbook of Evaluated Reactor Physics Benchmark Experiments

International Nuclear Information System (INIS)

Sartori, Enrico; Blair Briggs, J.

2008-01-01

1 - Description: The purpose of the International Reactor Physics Experiment Evaluation Project (IRPhEP) is to provide an extensively peer-reviewed set of reactor physics-related integral data that can be used by reactor designers and safety analysts to validate the analytical tools used to design next-generation reactors and establish the safety basis for operation of these reactors. This work of the IRPhEP is formally documented in the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments,' a single source of verified and extensively peer-reviewed reactor physics benchmark measurements data. The IRPhE Handbook is available on DVD. You may request a DVD by completing the DVD Request Form available at: http://irphep.inl.gov/handbook/hbrequest.shtml The evaluation process entails the following steps: 1. Identify a comprehensive set of reactor physics experimental measurements data, 2. Evaluate the data and quantify overall uncertainties through various types of sensitivity analysis to the extent possible, verify the data by reviewing original and subsequently revised documentation, and by talking with the experimenters or individuals who are familiar with the experimental facility, 3. Compile the data into a standardized format, 4. Perform calculations of each experiment with standard reactor physics codes where it would add information, 5. Formally document the work into a single source of verified and peer reviewed reactor physics benchmark measurements data. The International Handbook of Evaluated Reactor Physics Benchmark Experiments contains reactor physics benchmark specifications that have been derived from experiments that were performed at various nuclear experimental facilities around the world. The benchmark specifications are intended for use by reactor physics personal to validate calculational techniques. The 2008 Edition of the International Handbook of Evaluated Reactor Physics Experiments contains data from 25 different

Power electronics handbook components, circuits and applications

CERN Document Server

Mazda, F F

1993-01-01

Power Electronics Handbook: Components, Circuits, and Applications is a collection of materials about power components, circuit design, and applications. Presented in a practical form, theoretical information is given as formulae. The book is divided into three parts. Part 1 deals with the usual components found in power electronics such as semiconductor devices and power semiconductor control components, their electronic compatibility, and protection. Part 2 tackles parts and principles related to circuits such as switches; link frequency chargers; converters; and AC line control, and Part 3

The electric power engineering handbook power systems

CERN Document Server

2012-01-01

Power Systems, Third Edition (part of the five-volume set, The Electric Power Engineering Handbook) covers all aspects of power system protection, dynamics, stability, operation, and control. Under the editorial guidance of L.L. Grigsby, a respected and accomplished authority in power engineering, and section editors Andrew Hanson, Pritindra Chowdhuri, Gerry Sheble, and Mark Nelms, this carefully crafted reference includes substantial new and revised contributions from worldwide leaders in the field. This content provides convenient access to overviews and detailed information on a diverse arr

Fires, ecological effects of

Science.gov (United States)

W. J. Bond; Robert Keane

2017-01-01

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

Harwell emergency handbook

International Nuclear Information System (INIS)

1986-12-01

The Harwell Laboratory Emergency Handbook 1987 contains emergency procedures to deal with any incident which might occur at AERE Harwell involving radioactive or toxic material releases. The Handbook gives details of the duties of members of the Site Emergency Organization and other key members of staff, the methods by which incidents are controlled, the communication links and liaison arrangements with other organizations and the possible consequences and actions that may be needed following an emergency. (UK)

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

Directory of Open Access Journals (Sweden)

Martin Friebe

2014-12-01

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

Nuclear hazard/fire hazard: an elusive and important linkage

International Nuclear Information System (INIS)

Mariani, L.P.

1977-01-01

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

The development of a packaging handbook

International Nuclear Information System (INIS)

Shappert, L.B.

1994-01-01

The Packaging Handbook, dealing with the development of packagings designed to carry radioactive material, is being written for DOE's Transportation and Packaging Safety Division. The primary goal of the Handbook is to provide sufficient technical information and guidance to improve the quality of Safety Analysis Reports on Type B Packagings (SARPs) that are submitted to DOE for certification. This paper provides an update on the status of the Handbook

FIRE PERMIT NOW ON EDH!

CERN Multimedia

TIS General Safety Group or

2001-01-01

The electronic version of the Fire Permit form is now active. The aim of the Fire Permit procedure is to reduce the risk of fire or explosion. It is mandatory when performing 'hot work' (mainly activities which involve the use of naked flames or other heat sources - e.g. welding, brazing, cutting, grinding, etc.). Its use is explained in the CERN Fire Protection Code E. (Fire Protection) The new electronic form, which is substantially unchanged from the previous authorizing procedure, will be available on the Electronic Document Handling system (https://edh.cern.ch/) as of 1st September 2001. From this date use of the paper version should be discontinued.

LMFBR plant design features for sodium spill and fire protection

International Nuclear Information System (INIS)

Palm, R.E.

1982-01-01

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

Fire hazards analysis for the uranium oxide (UO3) facility

International Nuclear Information System (INIS)

Wyatt, D.M.

1994-01-01

The Fire Hazards Analysis (FHA) documents the deactivation end-point status of the UO 3 complex fire hazards, fire protection and life safety systems. This FHA has been prepared for the Uranium Oxide Facility by Westinghouse Hanford Company in accordance with the criteria established in DOE 5480.7A, Fire Protection and RLID 5480.7, Fire Protection. The purpose of the Fire Hazards Analysis is to comprehensively and quantitatively assess the risk from a fire within individual fire areas in a Department of Energy facility so as to ascertain whether the objectives stated in DOE Order 5480.7, paragraph 4 are met. Particular attention has been paid to RLID 5480.7, Section 8.3, which specifies the criteria for deactivating fire protection in decommission and demolition facilities

Petra Governance Handbook - WP7 – Governance structures & business models : D7.3: Governance Handbook

NARCIS (Netherlands)

Veeneman, W.; Hirschhorn, F.; Klievink, A.J.; Steenhuisen, B.M.; van der Voort, H.G.

2017-01-01

This document represents the governance handbook on mobility data platforms for the PETRA project. The governance handbook provides metropolitan authorities contemplating the implementation of a mobility data platform in line with the PETRA project about governance issues and design.
The

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

Science.gov (United States)

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

2010-02-01

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

Handbook for value-impact assessment

International Nuclear Information System (INIS)

Heaberlin, S.W.; Burnham, J.B.; Gallucci, R.H.V.

1983-12-01

The basic purpose of this handbook is to document a set of systematic procedures for providing information that can be used in performing value-impact assessments of Nuclear Regulatory Commission (NRC) regulatory actions. The handbook describes a structured but flexible process for performing the assessment. Chapter 1 is an introduction to the value-impact assessment process. Chapter 2 describes the attributes most frequently affected by proposed NRC actions, provides guidance concerningthe appropriate level of effort to be devoted to the assessment, suggests a standard format for documenting the assessment, and discusses the treatment of uncertainty. Chapter 3 contains detailed methods for evaluating each of the attributes affected by a regulatory action. The handbook has five appendixes containing background information, technical data, and example applications of the value-impact assessment procedures. This edition of the handbook focuses primarily on assessing nuclear power reactor safety issues

WIPP Project Records Management Handbook

International Nuclear Information System (INIS)

1991-01-01

The Waste Isolation Pilot Plant (WIPP) Records Management Handbook provides the WIPP Project Records Management personnel with a tool to use to fulfill the requirements of the WIPP Records Program and direct their actions in the important area of records management. The handbook describes the various project areas involved in records management, and how they function. The handbook provides the requirements for Record Coordinators and Master Record Center (MRC) personnel to follow in the normal course of file management, records scheduling, records turnover, records disposition, and records retrieval. More importantly, the handbook provides a single reference which encompasses the procedures set fourth in DOE Order 1324.2A, ''Records Disposition'' ASME NQA-1, ''Quality Assurance Program Requirements for Nuclear Facilities'' and DOE-AL 5700.6B, ''General Operations Quality Assurance.'' These documents dictate how an efficient system of records management will be achieved on the WIPP Project

Handbook of probability

CERN Document Server

Florescu, Ionut

2013-01-01

THE COMPLETE COLLECTION NECESSARY FOR A CONCRETE UNDERSTANDING OF PROBABILITY Written in a clear, accessible, and comprehensive manner, the Handbook of Probability presents the fundamentals of probability with an emphasis on the balance of theory, application, and methodology. Utilizing basic examples throughout, the handbook expertly transitions between concepts and practice to allow readers an inclusive introduction to the field of probability. The book provides a useful format with self-contained chapters, allowing the reader easy and quick reference. Each chapter includes an introductio

NAIR: handbook on the national arrangements for incidents involving radioactivity

International Nuclear Information System (INIS)

1987-01-01

A revised handbook on the national arrangements for incidents involving radioactivity (NAIR) has been published. Following brief introductory sections on the administrative aspects and operational aspects, the main part of the handbook is devoted to operational and call-out lists including an index of police forces served by NAIR, an index of establishments providing assistance under NAIR, sources of stage 1 and stage 2 assistance for each police constabulary, hospitals prepared to accept contaminated casualties and to assist with decontamination of personnel, and hospitals prepared to advise on the treatment and admission of casualties exposed to large doses of radiation. Technical appendices are also given on radiological protection in NAIR incidents, instruments and equipment, radionuclide data and a guide to suitable detectors, package and source identification and disposal of radioactive materials involved in NAIR accidents. (U.K.)

14 CFR 121.308 - Lavatory fire protection.

Science.gov (United States)

2010-01-01

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

Organization of radiation protection in German nuclear power stations

International Nuclear Information System (INIS)

1989-01-01

Using the operating handbooks of the nuclear power stations in West Germany, an examination was carried out of how far the existing organisational structure for radiation protection fulfils the requirements for protection and whether a standardisation of the organisation would provide improvements for the protection of the personnel and for the practicability of the radiation protection organisation. In particular, the parts 'Personnel operating organisation', 'Radiation protection order' and 'Maintenance order' of the operating handbook were evaluated and an audit was made of the radiation protection organisation. In general, the result of the assessment is that the organisation of radiation protection does not contradict the orders, guidelines and regulations in any of the nuclear power stations examined. Corresponding to the possibilities of regulating details of the radiation protection organisation within the undertaking, the target of 'protection of the personnel against radioactive irradiation' is achieved by the various organisation structures which are largely equal to the given example. (orig./HP) [de

Handbook of metaheuristics

CERN Document Server

Potvin, Jean-Yves

2010-01-01

“… an excellent book if you want to learn about a number of individual metaheuristics." (U. Aickelin, Journal of the Operational Research Society, Issue 56, 2005, on the First Edition) The first edition of the Handbook of Metaheuristics was published in 2003 under the editorship of Fred Glover and Gary A. Kochenberger. Given the numerous developments observed in the field of metaheuristics in recent years, it appeared that the time was ripe for a second edition of the Handbook. When Glover and Kochenberger were unable to prepare this second edition, they suggested that Michel Gendreau and Jean-Yves Potvin should take over the editorship, and so this important new edition is now available. Through its 21 chapters, this second edition is designed to provide a broad coverage of the concepts, implementations and applications in this important field of optimization. Original contributors either revised or updated their work, or provided entirely new chapters. The Handbook now includes updated chapters on the b...

THE REACTION TO FIRE TEST FOR FIRE RETARDANT AND FOR COMBUSTIBLE MATERIAL

Directory of Open Access Journals (Sweden)

Adelaida FANFAROVÁ

2016-12-01

Full Text Available Currently the natural materials become popular building material for houses, buildings and recreational property. The risk of fires in residential timber construction or eco houses cannot be completely ruled out, therefore there is a need for proper and correct implementing preventive measures and application of all available solutions, which may reduce the risk of fire as far as possible, to slow down the combustion process, to protect the life of people, animals and also the building itself until arrival members of the Fire and Rescue Services. Fireproofing of combustible materials is a specific area of fire protection. For scientific research as well as for real-life practice, not only their structural and physical properties, but also fire-technical characteristics are really important. The present researchers mostly focus on fire-retardant treatment of wood that is why the authors of this contribution focused on a different combustible material. This research article presents the experimental testing and examination of the reaction to fire test of the selected thermal insulation of hemp fiber that was impregnated by the selected fire retardant in laboratory conditions.

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

Fire prevention in nuclear power plants

International Nuclear Information System (INIS)

1993-01-01

The causes and frequency of fires at nuclear power plants in various countries are briefly given. Methods are described of fire hazard assessment at nuclear power plants, such as Gretener's method and the probabilistic methods. Approaches to the management of nuclear reactor fire protection in various countries as well as the provisions to secure such protection are dealt with. An overview and the basic characteristics of fire detection and extinguishing systems is presented. (Z.S.). 1 tab

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

Reference handbook: Level detectors

International Nuclear Information System (INIS)

1990-01-01

The purpose of this handbook is to provide Rocky Flats personnel with the information necessary to understand level measurement and detection. Upon completion of this handbook you should be able to do the following: List three reasons for measuring level. Describe the basic operating principles of the sight glass. Demonstrate proper techniques for reading a sight glass. Describe the basic operating principles of a float level detector. Describe the basic operating principles of a bubbler level indicating system. Explain the differences between a wet and dry reference leg indicating system, and describe how each functions. This handbook is designed for use by experienced Rocky Flats operators to reinforce and improve their current knowledge level, and by entry-level operators to ensure that they possess a minimum level of fundamental knowledge. Level Detectors is applicable to many job classifications and can be used as a reference for classroom work or for self-study. Although this reference handbook is by no means all-encompassing, you will gain enough information about this subject area to assist you in contributing to the safe operation of Rocky Flats Plant

Millennials in the Fire Service: The Effectiveness of Fire Service Recruiting, Testing, and Retention

Science.gov (United States)

2017-12-01

Administration/US-fire-department-profile. 50 Taro Yamane, Statistics : An Introductory Analysis, 2nd ed. (New York: Harper and Rowe, 1967), 886. 15...241096018-Is-there-a-better-approach-for-fire-department-testing/. Yamane, Taro. Statistics : An Introductory Analysis, 2nd ed. New York: Harper and...Fire Protection Association, January 2016), 21, http://www.nfpa.org/News-and-Research/Fire- statistics - and-reports/Fire- statistics /The-fire-service

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)

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

International Nuclear Information System (INIS)

1997-06-01

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

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

Science.gov (United States)

Dade County Public Schools, Miami, FL.

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

Practical electronics handbook

CERN Document Server

Sinclair, Ian R

1988-01-01

Practical Electronics Handbook, Second Edition covers information useful in electronics, with focus on mathematical conventions. The handbook discusses the passive (resistors, capacitors, band coding, and inductors) and active discrete (diodes, transistors and negative feedback) components; discrete component circuits; and transferring digital data. Linear I.C.s, which are the single-chip arrangements of amplifier circuits that are intended to be biased and operated in a linear way, and digital I.C.s, which process signals and consist of two significant voltage levels, are also considered. T

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 ...

Handbook of unmanned aerial vehicles

CERN Document Server

Vachtsevanos, George

2015-01-01

The Handbook of Unmanned Aerial Vehicles is a reference text for the academic and research communities, industry, manufacturers, users, practitioners, Federal Government, Federal and State Agencies, the private sector, as well as all organizations that are and will be using unmanned aircraft in a wide spectrum of applications. The Handbook covers all aspects of UAVs, from design to logistics and ethical issues. It is also targeting the young investigator, the future inventor and entrepreneur by providing an overview and detailed information of the state-of-the-art as well as useful new concepts that may lead to innovative research. The contents of the Handbook include material that addresses the needs and ‘know how’ of all of the above sectors targeting a very diverse audience. The Handbook offers a unique and comprehensive treatise of everything one needs to know about unmanned aircrafts, from conception to operation, from technologies to business activities, users, OEMs, reference sources, conferences, ...

Integrated Circuit Electromagnetic Immunity Handbook

Science.gov (United States)

Sketoe, J. G.

2000-08-01

This handbook presents the results of the Boeing Company effort for NASA under contract NAS8-98217. Immunity level data for certain integrated circuit parts are discussed herein, along with analytical techniques for applying the data to electronics systems. This handbook is built heavily on the one produced in the seventies by McDonnell Douglas Astronautics Company (MDAC, MDC Report E1929 of 1 August 1978, entitled Integrated Circuit Electromagnetic Susceptibility Handbook, known commonly as the ICES Handbook, which has served countless systems designers for over 20 years). Sections 2 and 3 supplement the device susceptibility data presented in section 4 by presenting information on related material required to use the IC susceptibility information. Section 2 concerns itself with electromagnetic susceptibility analysis and serves as a guide in using the information contained in the rest of the handbook. A suggested system hardening requirements is presented in this chapter. Section 3 briefly discusses coupling and shielding considerations. For conservatism and simplicity, a worst case approach is advocated to determine the maximum amount of RF power picked up from a given field. This handbook expands the scope of the immunity data in this Handbook is to of 10 MHz to 10 GHz. However, the analytical techniques provided are applicable to much higher frequencies as well. It is expected however, that the upper frequency limit of concern is near 10 GHz. This is due to two factors; the pickup of microwave energy on system cables and wiring falls off as the square of the wavelength, and component response falls off at a rapid rate due to the effects of parasitic shunt paths for the RF energy. It should be noted also that the pickup on wires and cables does not approach infinity as the frequency decreases (as would be expected by extrapolating the square law dependence of the high frequency roll-off to lower frequencies) but levels off due to mismatch effects.

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

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

2003-04-30

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

Springer Handbook of Acoustics

CERN Document Server

Rossing, Thomas D

2007-01-01

Acoustics, the science of sound, has developed into a broad interdisciplinary field encompassing the academic disciplines of physics, engineering, psychology, speech, audiology, music, architecture, physiology, neuroscience, and others. The Springer Handbook of Acoustics is an unparalleled modern handbook reflecting this richly interdisciplinary nature edited by one of the acknowledged masters in the field, Thomas Rossing. Researchers and students benefit from the comprehensive contents spanning: animal acoustics including infrasound and ultrasound, environmental noise control, music and human speech and singing, physiological and psychological acoustics, architectural acoustics, physical and engineering acoustics, signal processing, medical acoustics, and ocean acoustics. This handbook reviews the most important areas of acoustics, with emphasis on current research. The authors of the various chapters are all experts in their fields. Each chapter is richly illustrated with figures and tables. The latest rese...

32 CFR 644.319 - Protection of wetlands.

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Protection of wetlands. 644.319 Section 644.319... ESTATE HANDBOOK Disposal § 644.319 Protection of wetlands. The requirements of Executive Order 11990, Protection of Wetlands, 42 FR 26961, (24 May 1977) are applicable to the disposal of Federal lands and...

Review of the IAEA fire symposium

International Nuclear Information System (INIS)

Fischer, J.

1991-01-01

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

Handbook of radioimmunoassay

International Nuclear Information System (INIS)

Abraham, G.E.

1977-01-01

This handbook provides clear, detailed descriptions of ways to set up radioimmunoassay procedures for a variety of polypeptides and low molecular weight compounds. It covers extensively the subjects of statistical evaluation of radioimmunoassay, instrumentation in radioimmunoassay, and radiation safety in the performance of radioimmunoassay. Related nonconventional methods are also discussed. Contributors to this handbook have presented their own procedures for performing the radioimmunoassay and their rationale for choosing particular reagents and conditions. Emphasis is on providing sufficient information to enable relatively inexperienced immunoassayists to set up assay systems with a minimum of difficulty

The small library manager's handbook

CERN Document Server

Graves, Alice

2014-01-01

The Small Library Manager's Handbook is for librarians working in all types of small libraries. It covers the everyday nuts-and-bolts operations that all librarians must perform. This handbook, written by experts who are small librarians themselves, will help all small librarians to do multiple jobs at the same time.

Handbook for TEAC Auditors, 2011

Science.gov (United States)

Teacher Education Accreditation Council, 2011

2011-01-01

This handbook is primarily for the Teacher Education Accreditation Council (TEAC) auditor. It is intended to help in preparing for audits of "Inquiry Briefs" and "Inquiry Brief Proposals" and to contribute to the writing of the audit report. This handbook contains a full description of the audit process, the responsibilities of…

Handbook of Technical Communication

OpenAIRE

Mehler , Alexander; Romary , Laurent; Gibbon , Dafydd

2012-01-01

International audience; The handbook "Technical Communication" brings together a variety of topics which range from the role of technical media in human communication to the linguistic, multimodal enhancement of present-day technologies. It covers the area of computer-mediated text, voice and multimedia communication as well as of technical documentation. In doing so, the handbook takes professional and private communication into account. Special emphasis is put on technical communication bas...

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-04-19

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-08

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