DOE handbook electrical safety

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

Efforts to improve safety and reliability of nuclear power plants in Kyushu Electric Power

International Nuclear Information System (INIS)

Yamamoto, Satoshi

2014-01-01

After the Fukushima accident, Kyushu Electric Power Co. took emergency safety measures requested by government to ensure power supply, coolant supply pumps and cooling water so as to keep cooling fuels in the reactor and spent fuel storage pool in case of losses of ordinary cooling capability caused by earthquake and tsunami. In order to improve safety and reliability of nuclear power plants, further efforts based on lessons learned from the Fukushima accident had been made to diversify corresponding equipment of safety measures in terms of prevention of core damage, prevention of containment failure, mitigation of radioactive materials release, cooling of spent fuel pit and ensurance of power supply, and to enhance emergency response capability so as to make operational management more complete. Additional safety measures applicable to new regulatory requirements against severe accidents were in progress. This article introduced details of such activities. (T. Tanaka)

Electric power system basics for the nonelectrical professional

CERN Document Server

Blume, Steven W

2016-01-01

The second edition of Steven W. Blume’s bestseller provides a comprehensive treatment of power technology for the non-electrical engineer working in the electric power industry. This book aims to give non-electrical professionals a fundamental understanding of large interconnected electrical power systems, better known as the “Power Grid”, with regard to terminology, electrical concepts, design considerations, construction practices, industry standards, control room operations for both normal and emergency conditions, maintenance, consumption, telecommunications and safety. The text begins with an overview of the terminology and basic electrical concepts commonly used in the industry then it examines the generation, transmission and distribution of power. Other topics discussed include energy management, conservation of electrical energy, consumption characteristics and regulatory aspects to help readers understand modern electric power systems.

Managing electrical safety

CERN Document Server

Wiggins, James H, Jr

2001-01-01

Managing Electrical Safety provides an overview of electric basics, hazards, and established standards that enables you to understand the hazards you are likely to encounter in your workplace. Focusing on typical industrial environments-which utilize voltages much higher than household or office circuits-the author identifies the eight key components of an electrical safety program and examines each using a model safety management process. You'll learn how to identify electrical hazards, how to prescribe necessary electrical Personal Protective Equipment, how to ensure that equipment is de-ene

Evaluation of the safety of the operating nuclear power plants built to earlier standards

International Nuclear Information System (INIS)

Menteseoglu, S.

2001-01-01

The objective of this paper is to provide practical assistance on judging the safety of a nuclear power plant, on the basis of a comparison with current safety standards and operational practices. For nuclear power plants built to earlier standards for which there are questions about the adequacy of the maintenance of the plant design and operational practices, a safety review against current standards and practices can be considered a high priority. The objective of reviewing nuclear power plants built to earlier standards against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The safety significance of the issues identified should be judged according to their implications for plant design and operation in terms of basic safety concepts such as defence in depth and safety culture. In addition, this paper provides assistance on the prioritization of corrective measures and their implementation so as to approach an acceptable level of safety

Basic recognition on safety of nuclear electric power generation

International Nuclear Information System (INIS)

Miyazaki, Keiji

1995-01-01

The safety of nuclear electric power generation is not to inflict radiation damage on public. Natural radiation is about 1 mSv every year. As far as the core melting on large scale does not occur, there is not the possibility of exerting serious radiation effect to public. The way of thinking on ensuring the safety is defense in depth. The first protection is the prevention of abnormality, the second protection is the prevention of accidents, and the third protection is the relaxation of effect. As design base accidents, the loss of coolant accident due to the breakdown of inlet pipings of reactors and the breaking of fine tubes in steam generators are included. The suitability of location is evaluated. As the large scale accidents of nuclear power stations in the past, Chernobyl accident and Three Mile Island accident are explained. The features of the countermeasures to the accident in Mihama No. 2 plant are described. The countermeasures to severe accidents, namely accident management and general preventive maintenance are explained. The background of the nonconfidence feeling to nuclear electric power generation and the importance of opening information to public are shown. (K.I.)

Nuclear power plant safety

International Nuclear Information System (INIS)

Otway, H.J.

1974-01-01

Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

Reliability evaluation of the power supply of an electrical power net for safety-relevant applications

International Nuclear Information System (INIS)

Dominguez-Garcia, Alejandro D.; Kassakian, John G.; Schindall, Joel E.

2006-01-01

In this paper, we introduce a methodology for the dependability analysis of new automotive safety-relevant systems. With the introduction of safety-relevant electronic systems in cars, it is necessary to carry out a thorough dependability analysis of those systems to fully understand and quantify the failure mechanisms in order to improve the design. Several system level FMEAs are used to identify the different failure modes of the system and, a Markov model is constructed to quantify their probability of occurrence. A new power net architecture with application to new safety-relevant automotive systems, such as Steer-by-Wire or Brake-by-Wire, is used as a case study. For these safety-relevant loads, loss of electric power supply means loss of control of the vehicle. It is, therefore, necessary and critical to develop a highly dependable power net to ensure power to these loads under all circumstances

IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1980-01-01

This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

The electrical system of nuclear power plant

International Nuclear Information System (INIS)

Firman Silitonga; Gunarwan Prayitno

2009-01-01

In these system, electrical power system is supplied from two-offsite transmission system respective main transformer and house service transformer; and reserve transformer. The electrical load in these system consist of safety electrical system and non-safety electrical system, The safety electrical and non safety electrical systems consist of four 6,9 kV AC medium voltage bus and 480 V AC low voltage bus system. The DC power system consist of four safety 125 V DC power system and the two non-safety 125 DC power systems. The equipment in these electrical system is main turbine-generator; GTG safety; GTG alternate; uninterrupted power supply (UPS) and battery system. To protect electrical equipment and building to direct stroke and non direct stroke disturbances is installed netral grounding system and lightning protection and protection the personnel to touch-voltage is installed equipment grounding system and station grounding. The lightning arrester system is connected to station station grounding system. (author)

Nuclear power and safety

International Nuclear Information System (INIS)

Saunders, P.; Tasker, A.

1991-01-01

Nuclear power currently provides about a fifth of both Britain's and the world's electricity. It is the largest single source of electricity in Western Europe; in France three quarters of electricity is generated by nuclear power stations. This booklet is about the safety of those plants. It approaches the subject by outlining the basic principles and approaches behind nuclear safety, describing the protective barriers and safety systems that are designed to prevent the escape of radioactive material, and summarising the regulations that govern the construction and operation of nuclear power stations. The aim is to provide a general understanding of the subject by explaining the general principles of the Advanced Gas Cooled Reactor and setting out the UKAEA strategy for nuclear safety, the objective being always to minimize risk. (author)

The effects of electric power industry restructuring on the safety of nuclear power plants in the United States

Science.gov (United States)

Butler, Thomas S.

Throughout the United States the electric utility industry is restructuring in response to federal legislation mandating deregulation. The electric utility industry has embarked upon an extraordinary experiment by restructuring in response to deregulation that has been advocated on the premise of improving economic efficiency by encouraging competition in as many sectors of the industry as possible. However, unlike the telephone, trucking, and airline industries, the potential effects of electric deregulation reach far beyond simple energy economics. This dissertation presents the potential safety risks involved with the deregulation of the electric power industry in the United States and abroad. The pressures of a competitive environment on utilities with nuclear power plants in their portfolio to lower operation and maintenance costs could squeeze them to resort to some risky cost-cutting measures. These include deferring maintenance, reducing training, downsizing staff, excessive reductions in refueling down time, and increasing the use of on-line maintenance. The results of this study indicate statistically significant differences at the .01 level between the safety of pressurized water reactor nuclear power plants and boiling water reactor nuclear power plants. Boiling water reactors exhibited significantly more problems than did pressurized water reactors.

78 FR 41907 - Effluent Limitations Guidelines and Standards for the Steam Electric Power Generating Point...

Science.gov (United States)

2013-07-12

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 423 [EPA-HQ-OW-2009-0819. FRL-9832-7; EPA-HQ-RCRA-2013-0209] RIN 2040-AF14 Effluent Limitations Guidelines and Standards for the Steam Electric Power... proposed rule entitled, ``Effluent Limitations Guidelines and Standards for the Steam Electric Power...

Recent developments in the IAEA safety standards: design and operation of nuclear power plants

International Nuclear Information System (INIS)

Saito, Takehiko

2004-01-01

The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

Critical Review of Commercial Secondary Lithium-Ion Battery Safety Standards

Science.gov (United States)

Jones, Harry P.; Chapin, Thomas, J.; Tabaddor, Mahmod

2010-09-01

The development of Li-ion cells with greater energy density has lead to safety concerns that must be carefully assessed as Li-ion cells power a wide range of products from consumer electronics to electric vehicles to space applications. Documented field failures and product recalls for Li-ion cells, mostly for consumer electronic products, highlight the risk of fire, smoke, and even explosion. These failures have been attributed to the occurrence of internal short circuits and the subsequent thermal runaway that can lead to fire and explosion. As packaging for some applications include a large number of cells, the risk of failure is likely to be magnified. To address concerns about the safety of battery powered products, safety standards have been developed. This paper provides a review of various international safety standards specific to lithium-ion cells. This paper shows that though the standards are harmonized on a host of abuse conditions, most lack a test simulating internal short circuits. This paper describes some efforts to introduce internal short circuit tests into safety standards.

The electric power engineering handbook electric power generation, transmission, and distribution

CERN Document Server

Grigsby, Leonard L

2012-01-01

Featuring contributions from worldwide leaders in the field, the carefully crafted Electric Power Generation, Transmission, and Distribution, Third Edition (part of the five-volume set, The Electric Power Engineering Handbook) provides convenient access to detailed information on a diverse array of power engineering topics. Updates to nearly every chapter keep this book at the forefront of developments in modern power systems, reflecting international standards, practices, and technologies. Topics covered include: * Electric Power Generation: Nonconventional Methods * Electric Power Generation

Casebook on electric safety accidents

International Nuclear Information System (INIS)

1987-09-01

This book gives concentration on electric safety accidents in domestic and abroad, which introduces general electrical safety with property of electricity, safe equipment and maintenance and protection of electric shock. It lists the cases of accident caused of electricity in domestic like accident in power substation, utilization equipment, load system and another accident by electricity like death in electric shock another by electricity like death in electric shock in new building construction, the cases caused of electricity in abroad like damage in electric shock by high voltage electric transformer, electric shock in summer and earth fault accident by fault cooling tower.

Electric Power quality Analysis in research reactor: Impacts on nuclear safety assessment and electrical distribution reliability

International Nuclear Information System (INIS)

Touati, Said; Chennai, Salim; Souli, Aissa

2015-01-01

The increased requirements on supervision, control, and performance in modern power systems make power quality monitoring a common practise for utilities. Large databases are created and automatic processing of the data is required for fast and effective use of the available information. Aim of the work presented in this paper is the development of tools for analysis of monitoring power quality data and in particular measurements of voltage and currents in various level of electrical power distribution. The study is extended to evaluate the reliability of the electrical system in nuclear plant. Power Quality is a measure of how well a system supports reliable operation of its loads. A power disturbance or event can involve voltage, current, or frequency. Power disturbances can originate in consumer power systems, consumer loads, or the utility. The effect of power quality problems is the loss power supply leading to severe damage to equipments. So, we try to track and improve system reliability. The assessment can be focused on the study of impact of short circuits on the system, harmonics distortion, power factor improvement and effects of transient disturbances on the Electrical System during motor starting and power system fault conditions. We focus also on the review of the Electrical System design against the Nuclear Directorate Safety Assessment principles, including those extended during the last Fukushima nuclear accident. The simplified configuration of the required system can be extended from this simple scheme. To achieve these studies, we have used a demo ETAP power station software for several simulations. (authors)

Electric Power quality Analysis in research reactor: Impacts on nuclear safety assessment and electrical distribution reliability

Energy Technology Data Exchange (ETDEWEB)

Touati, Said; Chennai, Salim; Souli, Aissa [Nuclear Research Centre of Birine, Ain Oussera, Djelfa Province (Algeria)

2015-07-01

The increased requirements on supervision, control, and performance in modern power systems make power quality monitoring a common practise for utilities. Large databases are created and automatic processing of the data is required for fast and effective use of the available information. Aim of the work presented in this paper is the development of tools for analysis of monitoring power quality data and in particular measurements of voltage and currents in various level of electrical power distribution. The study is extended to evaluate the reliability of the electrical system in nuclear plant. Power Quality is a measure of how well a system supports reliable operation of its loads. A power disturbance or event can involve voltage, current, or frequency. Power disturbances can originate in consumer power systems, consumer loads, or the utility. The effect of power quality problems is the loss power supply leading to severe damage to equipments. So, we try to track and improve system reliability. The assessment can be focused on the study of impact of short circuits on the system, harmonics distortion, power factor improvement and effects of transient disturbances on the Electrical System during motor starting and power system fault conditions. We focus also on the review of the Electrical System design against the Nuclear Directorate Safety Assessment principles, including those extended during the last Fukushima nuclear accident. The simplified configuration of the required system can be extended from this simple scheme. To achieve these studies, we have used a demo ETAP power station software for several simulations. (authors)

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 1. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

International Nuclear Information System (INIS)

Nero, A.V. Jr.

1977-01-01

This report presents an overview of a project on the health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. In addition to presenting an executive summary of the project, it sets forth the main results of the four tasks of the project: to review the health impacts (and related standards) of these forms of power generation, to review the status of standards related to plant safety (with an emphasis on nuclear power), to consider the role of the California Energy Resources Conservation and Development Commission in selection of standards, and to set forth methodologies whereby that Commission may review the health and safety aspects of proposed sites and facilities

1E Qualification of Electrical Equipment - Requirement for Safety Nuclear Power Plants

International Nuclear Information System (INIS)

Geambasu, C.; Segarceanu, D.; Albu, J.

2002-01-01

The paper presents the qualification methods of the safety related equipment according to the safety class 1E. There are presented the qualification principles, procedure and documents, emphasis being laid on the qualification approach by type tests. This approach assumes the equipment test under both normal and accident conditions (design basis events) simulating the operational conditions and covers the largest part of electrical equipment from a nuclear power plant.The safety related equipment is to be qualified is subjected to a sequential test that will be detailed in the paper. (author)

Safety evaluation report related to the preliminary design of the Standard Reference System, RESAR-414

International Nuclear Information System (INIS)

1978-11-01

The safety evaluation for the Westinghouse Standard Reactor includes information on general reactor characteristics; design criteria for systems and components; reactor coolant system; engineered safety systems; instrumentation and controls; electric power systems; auxiliary systems; steam and power conversion system; radioactive waste management; radiation protection; conduct of operations; accident analyses; and quality assurance

Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

International Nuclear Information System (INIS)

Hirano, Masashi; Narumiya, Yoshiyuki

2010-01-01

The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

Safety critical systems handbook a straightforward guide to functional safety : IEC 61508 (2010 edition) and related standards

CERN Document Server

Smith, David J

2010-01-01

Electrical, electronic and programmable electronic systems increasingly carry out safety functions to guard workers and the public against injury or death and the environment against pollution. The international functional safety standard IEC 61508 was revised in 2010, and this is the first comprehensive guide available to the revised standard. As functional safety is applicable to many industries, this book will have a wide readership beyond the chemical and process sector, including oil and gas, power generation, nuclear, aircraft, and automotive industries, plus project, instrumentation, design, and control engineers. * The only comprehensive guide to IEC 61508, updated to cover the 2010 amendments, that will ensure engineers are compliant with the latest process safety systems design and operation standards* Helps readers understand the process required to apply safety critical systems standards* Real-world approach helps users to interpret the standard, with case studies and best practice design examples...

78 FR 2797 - Federal Motor Vehicle Safety Standards; Minimum Sound Requirements for Hybrid and Electric Vehicles

Science.gov (United States)

2013-01-14

... Sound Requirements for Hybrid and Electric Vehicles; Draft Environmental Assessment for Rulemaking To Establish Minimum Sound Requirements for Hybrid and Electric Vehicles; Proposed Rules #0;#0;Federal Register...-0148] RIN 2127-AK93 Federal Motor Vehicle Safety Standards; Minimum Sound Requirements for Hybrid and...

IEEE Std 382-1985: IEEE standard for qualification of actuators for power operated valve assemblies with safety-related functions for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions Part I describes the qualification process. Part II describes the standard qualification cases and their environmental parameters for the usual locations of safety-related equipment in a nuclear generating station. Part III describes the qualification tests outlined in 6.3.3

Ministry of ordinance determining the technical standard concerning atomic energy facilities for power generation

International Nuclear Information System (INIS)

1985-01-01

The ministerial ordinance provides for the technical standards for the power generation of nuclear facilities; i.e., electric power facilities generating electricity with nuclear energy for motive power, according to the Electricity Enterprises Act. The contents are as follows: protection against fires, aseismatic design, radiation protective barriers, structural protection for sitings, reactor installation, safety measures, materials and structures, safety valves, pressure resistance tests, reactor core, radiation shields, reactor cooling, emergency core cooling system, facility equipment, alarm system, reactor control system, reactor control room, fuel storage facility, fuel handling facility, ventilation equipment, radioactive contamination prevention, radioactive waste management facility, reactor containment facility, and so on. (Kubozono, M.)

Bohunice Nuclear Power Plant Safety Upgrading Program

International Nuclear Information System (INIS)

Toth, A.; Fagula, L.

1996-01-01

Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

Promoting safety in nuclear installations. The IAEA has established safety standards for nuclear reactors and provides expert review and safety services to assist Member States in their application

International Nuclear Information System (INIS)

2002-01-01

More than 430 nuclear power plants (NPPs) are currently operating in 30 countries around the world. The nuclear share of total electricity production ranges from about 20 percent in the Czech Republic and United States to nearly 78 percent in France and Lithuania. Worldwide, nuclear power generates about 16% of the total electricity. The safety of such nuclear installations is fundamental. Every aspect of a power plant must be closely supervised and scrutinized by national regulatory bodies to ensure safety at every phase. These aspects include design, construction, commissioning, trial operation, commercial operation, repair and maintenance, plant upgrades, radiation doses to workers, radioactive waste management and, ultimately, plant decommissioning. Safety fundamentals comprise defence-in-depth, which means having in place multiple levels of protection. nuclear facilities; regulatory responsibility; communicating with the public; adoption of the international convention on nuclear safety including implementation of IAEA nuclear safety standards. This publication covers topics of designing for safety (including safety concepts, design principles, and human factors); operating safety (including safety culture and advance in operational safety); risk assessment and management

Results of evaluation of periodic safety review for No. 1 plant in Mihama Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1994-01-01

No. 1 plant in Mihama Power Station started the commercial power generation in November, 1970, and has continued the operation for more than 23 years. During this period, the counter measures to troubles, periodic inspections and the maintenance by the electric power company have been carried out. These states of No. 1 plant in Mihama Power Station for more than 23 years are to be recollected from the view-points of the comprehensive evaluation of operation experiences and the reflection of latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Mihama Power Station made by Kansai Electric Power Co., and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor is 43.3% on the average of about 23 years, but in the last 10 years, it was improved to 69.4%. In the last five years, the rate of occurrence of unexpected shutoff was 0.6 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, and radioactive waste management have been carried out properly. The work plan for preventing disasters was established, and the experience of troubles and the latest technological knowledge were well reflected to improve the safety. (K.I.)

77 FR 24560 - National Highway Traffic Safety Administration Electric Vehicle Safety Technical Symposium

Science.gov (United States)

2012-04-24

... DEPARTMENT OF TRANSPORTATION National Highway Traffic Safety Administration Electric Vehicle... discuss safety considerations for electric vehicles powered by lithium-ion (Li-ion) batteries. The... vehicles. Electric vehicles show great promise as an innovative and fuel- efficient option for American...

Comparative health and safety assessment of the satellite power system and other electrical generation alternatives

International Nuclear Information System (INIS)

1980-12-01

The work reported here is an analysis of existing data on the health and safety risks of a satellite power system and six electrical generation systems: a combined-cycle coal power system with a low-Btu gasifier and open-cycle gas turbine; a light water fission power system without fuel reprocessing; a liquid-metal, fast-breeder fission reactor; a centralized and decentralized, terrestrial, solar-photovoltaic power system; and a first-generation design for a fusion power system. The systems are compared on the basis of expected deaths and person-days lost per year associated with 1000 MW of average electricity generation. Risks are estimated and uncertainties indicated for all phases of the energy production cycle, including fuel and raw material extraction and processing, direct and indirect component manufacture, on-site construction, and system operation and maintenance. Also discussed is the potential significance of related major health and safety issues that remain largely unquantifiable. The appendices provide more detailed information on risks, uncertainties, additional research needed, and references for the identified impacts of each system

Problems of standardizing and technical regulation in the electric power industry

Science.gov (United States)

Grabchak, E. P.

2016-12-01

A mandatory condition to ensure normal operation of a power system and efficiency in the sector is standardization and legal regulation of technological activities of electric power engineering entities and consumers. Compared to the times of USSR, the present-time technical guidance documents are not mandatory to follow in most cases, being of an advisory nature due to the lack of new ones. During the last five years, the industry has been showing a deterioration of the situation in terms of ensuring reliability and engineering controllability as a result of the dominant impact of short-term market stimuli and the differences in basic technological policies. In absence of clear requirements regarding the engineering aspects of such activities, production operation does not contribute to the preserving of technical integrity of the Russian power system, which leads to the loss of performance capability and controllability and causes disturbances in the power supply to consumers. The result of this problem is a high rate of accident incidence. The dynamics of accidents by the type of equipment is given, indicating a persisting trend of growth in the number of accidents, which are of a systematic nature. Several problematic aspects of engineering activities of electric power engineering entities, requiring standardization and legal regulation are pointed out: in the domestic power system, a large number of power electrotechnical and generating equipment operate along with systems of regulation, which do not comply with the principles and technical rules representing a framework where the Energy System of Russia is built and functioning

Safety standards for wind turbines; Sicherheitsnormen fuer Windenergieanlagen

Energy Technology Data Exchange (ETDEWEB)

Boyce, K. [Underwriters Laboratories Inc., Northbrook, IL (United States)

2012-08-15

As the global wind infrastructure sustains rapid growth, compliance with relevant standards provide validation of design principles and establish due diligence in addressing critical attributes such as safety. The IEC 61400 series of standards provides important information for addressing safety and performance of wind turbine systems. Efforts to address unique issues within the United States market has led to development of two safety standards, UL 6141 for large wind turbines and UL 6142 for small wind turbines. These standards, which are being published as American National Standards, contain key safety requirements for the electrical system, electrical safety and controls system, grid connection, and related safety issues. In the future, collaborative efforts will lead to continued exchange of best practices and opportunities for broader harmonization. Development of these standards, and their use by the manufacturing community in design and development of wind turbine products, supports maximal safety and performance of the burgeoning wind infrastructure. (orig.)

The IAEA safety standards

International Nuclear Information System (INIS)

Karbassioun, Ahmad

1995-01-01

During the development of the NUSS standards, wide consultation was carried out with all the Member States to obtain a consensus and the programme was supervised by a Senior Advisory Group consisting of senior safety experts from 13 countries. This group of senior regulators later became what is now known as the Nuclear Safety Standards Advisory Group (NUSSAG) and comprises of senior regulatory experts from 16 countries. The standards that were developed comprise of four types of documents: safety fundamentals; codes of practice; safety guides; and safety practices. The safety fundamentals set out the basic objectives, concepts and principles for nuclear safety in nuclear power plants. The codes of practice, are of a legislative nature, and establish the general objectives that must be fulfilled to ensure adequate nuclear power plant safety. They cover five areas: governmental organization; siting, design, operation and quality assurance. The safety guides, administrative in character, recommend procedures and acceptable technical solutions to implement the codes and guides by presenting further details gained from Member States, on the application and interpretation of individual concepts in the NUSS codes and guides. In total in the NUSS series there is currently one Fundamentals document, five Codes of Practice and fifty-six Safety Guides

Emergency power systems at nuclear power plants

International Nuclear Information System (INIS)

1991-01-01

This Safety Guide was prepared as part of the Nuclear Safety Standards programme for establishing Codes and Safety Guides relating to nuclear power plants (NPPs). The first edition of the present Safety Guide was developed in the early 1980s. The text has now been brought up-to-date, refined in several details and amended to include non-electrical diverse and independent power sources. This Guide applies to NPP for which the total power supply comprises a normal power supply and an emergency power supply (EPS), which may be electrical or a combination of electrical and non-electrical. The Guide provides general guidance for all types of EPS and specific guidance on the design safety requirements and the features of the electrical and non-electrical portions of the EPS. 9 figs, 2 tabs

76 FR 11415 - Federal Motor Vehicle Safety Standards; Power-Operated Window, Partition, and Roof Panel Systems

Science.gov (United States)

2011-03-02

... [Docket No. NHTSA-2011-0027] RIN 2127-AK52 Federal Motor Vehicle Safety Standards; Power-Operated Window, Partition, and Roof Panel Systems AGENCY: National Highway Traffic Safety Administration (NHTSA), Department... automatic reversal systems (ARS) for power windows and to make a final decision. The agency has decided not...

Nuclear power safety

International Nuclear Information System (INIS)

1991-11-01

This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

Standardized Curriculum for Electricity/Electronics.

Science.gov (United States)

Mississippi State Dept. of Education, Jackson. Office of Vocational, Technical and Adult Education.

Standardized vocational education course titles and core contents are provided for two courses in Mississippi: electricity/electronics I and II. The first course contains the following units: (1) orientation, safety, and leadership; (2) basic principles of electricity/electronics; (3) direct current (DC) theory; (4) magnetism and DC motors; (5)…

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

Consequences of electricity deregulation on nuclear safety

International Nuclear Information System (INIS)

Podjavorsek, M.

2007-01-01

The evolution of deregulation of electricity market started a couple of years ago and has not been finished yet. Deregulation causes increased pressure to reduce the costs of electricity generation. This presents a new challenge to regulatory bodies. They have to assess the impact of these changes on the safety of nuclear power plants. Accordingly, it is important to identify the risks to the nuclear power industry resulting from the deregulation. Today's trend is that the number of electricity generating power companies will be reduced in Europe and also in Slovenia due to tough competition in the electricity market. The electricity price has decreased after the introduction of the deregulated market in most countries. This has been also the main reason for less investment to new generating capacities since the price has been lower than the generation costs. Investment problems are also present for the existing units, because of danger of inappropriate maintenance and reduction of the number of staff and their qualifications below the desired level that leads to loss of institutional memory. It is expected that only the biggest companies can stand the consequences of competition in electricity prices and consequential pressure to reduce the cost. In order to review the impact of deregulation of the electricity market some relevant points are discussed in this paper such as the need to cut costs of companies by reducing the number of their activities and increasing the efficiency in the remaining activities and /or outsourcing of activities, power station operating regime, safety culture, grid reliability, reliability and safety of operation, increased number of transients, ageing of components, outage duration, extended cycle and response of nuclear regulators. From a regulatory point of view the impact of deregulation on nuclear safety is an important issue. This paper also discusses analyses and evaluations of this impact and proposes some measures how to

Working group 1A - basis for the standard-safety

International Nuclear Information System (INIS)

Whipple, C.

1993-01-01

This paper presents a summary of the progress made by working group 1A (Basis for the Safety Standard) during the Electric Power Research Institute's EPRI Workshop on the technical basis of EPA HLW Disposal Criteria, March 1993. This group discussed the semantics of terms within the standard 40 CFR Part 191, the implementation of this standard, the advanced notice of rulemaking, the issue of emitting carbon-14 through a gaseous pathway, the strategy of dealing with standards for contamination of drinking water and groundwater, the 100,000 year time frame, and the analysis of specific comments. The specific comments dealt with the cost effectiveness of the standard, the dose histogram for populations and individuals, groundwater definition and the underlying technology driver for this standard

77 FR 12086 - Final Staff Guidance, Revision 4 to Standard Review Plan; Section 8.1 on Electric Power-Introduction

Science.gov (United States)

2012-02-28

... Plan; Section 8.1 on Electric Power--Introduction AGENCY: Nuclear Regulatory Commission. [[Page 12087... Nuclear Power Plants,'' Standard Review Plan (SRP) Section 8.1 on ``Electric Power--Introduction,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113640121), and the Branch...

Health protection and industrial safety. Nuclear power plants

International Nuclear Information System (INIS)

1987-03-01

The standard applies to components of the primary circuit including its auxiliary facilities, and of the secondary circuit of nuclear power plants with pressurized water reactors; to lifting gear and load take-ups for the transport of nuclear fuel and primary circuit components; to elevators within the containment, electrical installations, and piping and valves of radiation protection monitoring equipment. Part 1 defines the terms and specifies engineered safety requirements

Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

International Nuclear Information System (INIS)

Strohal, P.; Subasic, D.; Valcic, I.

1996-01-01

As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

A design of electric power supply system for gamma irradiator ISG-500

International Nuclear Information System (INIS)

Harno Garnito; Enggar; Harjani; Ari Satmoko; Sutomo Budihaharjo

2010-01-01

Reliability of electrical power system in Irradiator system is absolutely necessary during the life cycle. Electrical energy is used as the main supporting element for both Irradiator operation of mechanical system, lighting, as well as for instrumentation and control systems. The reliability of electrical power system in the system can be achieved by paying attention Irradiator safety, simplicity of operation, ease of maintenance and possible future development. Distribution network of the most commonly used is the Radial network system, for the simple and in accordance with the criteria demanded by a distribution system. In addition to the network system, to get the reliability of electric power supply system is the selection of equipment/materials that meet the standards, and the installation of which provide facilities for maintenance and repairs. (author)

Advance of technological innovations of electric power in 2012

International Nuclear Information System (INIS)

Mayumi, Akihiko; Tanaka, Masanori; Takebe, Toshiro

2013-01-01

Twelve companies in Japan reported on the technological innovations in 2012. The Japan Atomic Power Company mainly studied five projects; (1) control of wall thinning of the secondary system in PWR by injection of molybdic acid, (2) application of pipe test method using electromagnetic acoustic resonance to existing equipment, (3) developed high performance Co-60 crud removal resin for Tsuruga Power Station Unit 2, (4) improvement of technology for safety of core in FBR, and (5) improvement of technology for coolant of FBR by dispersing nano-particles in liquid sodium metal. Tokyo Electric Power Company developed mainly three projects; (1) the support for the mental health care activities by industry protection staff at the Fukushima Daiichi and Daini Nuclear Power Plant, (2) laboratory test method using non-radioactive cesium for performance of decontamination reagent, and (3) decontamination effects estimation code (DeConEP). Hokuriku Electric Power Company reported the operations management measures in accordance with the safety enhancement measures to Shika nuclear power station. Other nine reports are published by Hokkaido Electric Power Co., Inc. Tohoku Electric Power Co., Inc. Chubu Electric Power Co., Inc., The Kansai Electric Power Co., Inc., The Chugoku Electric Power Co., Inc., Shikoku Electric Power Co., Inc., Kyushu Electric Power Co., Inc., Okinawa Electric Power Company Inc. and J-Power. (S.Y.)

Nuclear power systems: Their safety

International Nuclear Information System (INIS)

Myers, L.C.

1993-01-01

Mankind utilizes energy in many forms and from a variety of sources. Canada is one of a growing number of countries which have chosen to embrace nuclear-electric generation as a component of their energy systems. As of August 1992 there were 433 power reactors operating in 35 countries and accounting for more than 15% of the world's production of electricity. In 1992, thirteen countries derived at least 25% of their electricity from nuclear units, with France leading at nearly 70%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 68 power reactors are under construction in 16 countries, enough to expand present generating capacity by close to 20%. No human endeavour carries the guarantee of perfect safety and the question of whether or not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor in the USSR has irrevocably changed all that. This disaster brought the matter of nuclear safety back into the public mind in a dramatic fashion. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents which have occurred to date. (author). 7 refs

IEEE Std 317-1972: IEEE standard for electric penetration assemblies in containment structures for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard prescribes the mechanical, electrical, and test requirements for the design, construction, and installation of electric penetration assemblies in containment structures for stationary nuclear power generating stations. The electric conductor and insulation characteristics of external circuits which connect to penetration assemblies are beyond the scope of these criteria. If there should be any conflict between this standard and those documents referenced herein, this standard shall take precedence over the referenced documents

Standard model for safety analysis report of hexafluoride power plants from natural uranium

International Nuclear Information System (INIS)

1983-01-01

The standard model for safety analysis report for hexafluoride production power plants from natural uranium is presented, showing the presentation form, the nature and the degree of detail, of the minimal information required by the Brazilian Nuclear Energy Commission - CNEN. (E.G.) [pt

French electric power balance sheet 2010

International Nuclear Information System (INIS)

Lartigau, Thierry; Riere, Alexia

2011-01-01

The mission of RTE, the French electricity Transportation grid, a public service assignment, is to balance the electricity supply and demand in real time. This report presents RTE's technical results for the year 2010: increase of RTE's investments and safety expenses for adapting the grid to the new electricity industry stakes and to meteorological hazards, decrease of power cuts frequency, rise of the French power consumption, strong increase of winter consumption peaks, increase of the French power generation, increase of the positive trade balance. New RTE's infrastructures, electricity quality data, and the evolution of market mechanisms are presented in appendixes

Nuclear power reactor safety

International Nuclear Information System (INIS)

Pon, G.A.

1976-10-01

This report is based on the Atomic Energy of Canada Limited submission to the Royal Commission on Electric Power Planning on the safety of CANDU reactors. It discusses normal operating conditions, postulated accident conditions, and safety systems. The release of radioactivity under normal and accident conditions is compared to the limits set by the Atomic Energy Control Regulations. (author)

CNE (Embalse nuclear power plant): probabilistic safety study. Electric power supply. Events sequence

International Nuclear Information System (INIS)

Figueroa, N.

1987-01-01

The plant response to the occurrence of the starting event 'total loss of electric power supply to class IV and class III' is analyzed. This involves the study of automatical actions of safety and process systems as well as the operator actions. The probabilistic evaluation of starting event frequency is performed through fault-tree techniques. The frequency of occurrence 'loss of electric power supply to class IV (λIV = 0.56/year) and the probability of failure to demand of 'reserve' generating groups (Pd III 6.79 x 10 -3 ) contribute to the mentioned frequency. As soon as the starting event occurs, the reactor power must be reduced to 0%, the fuel must be cooled through the thermo siphon and decay heat has to be removed. The events sequence analysis leads to the conclusion that the non shutting down of the reactor with any of the shutdown systems is 'incredible' (10 -6 /year). In all cases the fuel is cooled by building the thermo siphon except when a substantial inventory loss exist due to a closure failure of some valve of pressure and inventory control system. The order of magnitude of the failure of decay heat removal through the steam generators is 4 x 10 -4 . This removal would be assured by the emergency water system. Therefore, the frequency of the sequence of possible core meltdown, when the reactor does not shut down is: λ = 5 x 10 -9 /year and for the failure of heat removal: λ = 2 x 10 -6 /year. (Author)

Alteration in reactor installation (addition of Unit 2) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (inquiry)

International Nuclear Information System (INIS)

1983-01-01

An inquiry was made by the Ministry of International Trade and Industry to Nuclear Safety Commission on the addition of Unit 2 in Shimane Nuclear Power Station of The Chugoku Electric Power Co., Inc., concerning the technical capability of Chugoku Electric Power Co., Inc., and the plant safety. The NSC requested the Committee on Examination of Reactor Safety to make a deliberation on this subject. Both the technical capability and the safety of Unit 1 were already confirmed by MITI. Unit 2 to be newly added in the Shimane Nuclear Power Station is a BWR power plant with electric output of 820 MW. The examination made by MITI is described: the technical capability of Chugoku Electric Power Co., Inc., the safety of Unit 2 about its siting, reactor proper, reactor cooling system, radioactive waste management, etc. (J.P.N.)

High temperature reactor module power plant. Plant and safety concept June 1986 - 38.07126.2

International Nuclear Information System (INIS)

1986-06-01

The modular HTR power plant is a universally applicable energy source for the co-generation of electricity, process steam or district heating. The modular HTR concept is characterized by the fact that standardized reactor units with power ratings of 200 MJ/s (so-called modules) can be combined to form power plants with a higher power rating. Consequently the special safety features of small high-temperature reactors (HTR) are also available at higher power plant ratings. The safety features, the technical design and the mode of operation are briefly described in the following, taking a power plant with two HTR-Modules for the co-generation of electricity and process steam as an example. Due to its universal applicability and excellent safety features, the modular HTR power plant is suitable for erection on any site, but particularly on sites near other industrial plants or in densely populated areas. The co-generation of electricity and process steam or district heating with a modular HTR power plant as described here is primarily tailored to the requirements of industrial and communal consumers. The site for such a plant is a typical industrial one. The anticipated features of such sites were taken into consideration in the design of the modular HTR power plant

High temperature reactor module power plant. Plant and safety concept June 1986 - 38.07126.2

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-06-15

The modular HTR power plant is a universally applicable energy source for the co-generation of electricity, process steam or district heating. The modular HTR concept is characterized by the fact that standardized reactor units with power ratings of 200 MJ/s (so-called modules) can be combined to form power plants with a higher power rating. Consequently the special safety features of small high-temperature reactors (HTR) are also available at higher power plant ratings. The safety features, the technical design and the mode of operation are briefly described in the following, taking a power plant with two HTR-Modules for the co-generation of electricity and process steam as an example. Due to its universal applicability and excellent safety features, the modular HTR power plant is suitable for erection on any site, but particularly on sites near other industrial plants or in densely populated areas. The co-generation of electricity and process steam or district heating with a modular HTR power plant as described here is primarily tailored to the requirements of industrial and communal consumers. The site for such a plant is a typical industrial one. The anticipated features of such sites were taken into consideration in the design of the modular HTR power plant.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements

International Nuclear Information System (INIS)

2012-01-01

On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safer nuclear power. Strengthening training for operational safety at Paks nuclear power plant - Hungary

International Nuclear Information System (INIS)

2003-01-01

For a nuclear power plant, safety must always be paramount. There can be no compromise on safety to meet production targets or to reduce costs. For any reactor, and in particular where older type reactors are in place, their operational safety can be enhanced by upgrading the training of personnel responsible for operating and maintaining the plant. The Department of Technical Co-operation is sponsoring a programme with technical support from the Nuclear Energy and Nuclear Safety Departments to help improve facilities at the PAKS plant in Hungary and establish self sufficiency in training to the highest international standards for all levels of nuclear power plant manpower. The Model Project described will have a direct impact on the improvement of operational safety and performance at PAKS NPP. It will lead to a more efficient use of resources which in turn will result in lower electricity generation costs. The impact of the project is not expected to be limited to Hungary. WWER reactors are common in Eastern Europe and provide one third to one half of the electricity supply to the region. The training programmes and facilities at PAKS offer a possibility in the future to provide training to experts from other countries operating WWER units and serve as a model to be emulated. Slovakia and the Czech Republic have already expressed interest in using the PAKS experience

Staff report on the environmental qualification of safety-related electrical equipment

International Nuclear Information System (INIS)

1977-12-01

The current NRC safety review process for nuclear power plants includes criteria related to the qualification of certain electrical equipment. These criteria require that electrical equipment important to safety must be qualified to function in the environment that might result from various accident conditions. Although such criteria have been applied since the early days of commercial nuclear power, the details of these criteria have been changed over the years. The evolution of environmental qualification of safety-related electrical equipment is described in Appendix A

Nuclear power: Siting and safety

International Nuclear Information System (INIS)

Openshaw, S.

1986-01-01

By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

Alternative off-site power supply improves nuclear power plant safety

International Nuclear Information System (INIS)

Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

2014-01-01

Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

Electric utilities deregulation and its impact on nuclear power generating stations

International Nuclear Information System (INIS)

Trehan, N.K.

1998-01-01

Under restructuring and deregulation, it is not clear as to who would have the responsibility, and what obligations the market participants would have to ensure that the electrical system reliability (stability) is maintained. Due to the dynamic nature of the electrical grid, especially with the implementation of restructuring and deregulation, vulnerabilities exist which may impact the reliability (stability) of the offsite electrical power system. In a nuclear power generating unit, an offsite electric power system and an onsite electric power system are required to permit the functioning of structures, systems, and components which are important to safety. The safety function for each system is to provide sufficient capacity and capability to assure that the containment integrity is maintained during power operation or in the event of a postulated accident. Analyses performed by the applicants must verify that the electrical grid remains stable in the event of a loss of the nuclear unit generator, the largest other unit on the grid or the most critical transmission line. The stability of the electric grid is assumed in the safety analyses and a change in it would impact those analyses. However, it may impact the availability of a stable electric power to the safety buses because of the limited number of available transmission lines. This paper discusses electrical power generation and demand, reserve margins, power transfer capability, development of new innovative technologies to compensate for lack of the construction of transmission lines, legislation for the formulation of a self regulation organization (SRO), grid disturbances that may lead to a voltage collapse, and the vulnerabilities which may impact the availability of a stable power to the nuclear power generating stations

Development on power distribution technologies of four electric power companies in Japan. The Kansai Electric Power Co. , Inc

Energy Technology Data Exchange (ETDEWEB)

1989-07-01

Since dependency upon electric power has been rising yearly with the development of industry and the progress of information-oriented society, various kinds of technical development are needed to supply electricity. Furthermore, amenity of people's living has been highly intended, and life style has varied. Consequently, customers' needs for energy including related services have varied remarkably, and each customer has selected energy more subjectively from the wide range of viewpoint such as reliability, handiness, cleanliness, safety, and economic efficiency. In such situation, the power distribution section of Kansai Electric Power settled four themes for major technical development and has been promoting them. Four themes are as follows; to develop a total automation system for power distribution, to promote 20kV/400V-class power distribution, to develop techniques to form facilities harmonizing with local amenity, and to make business management efficient with the advanced NC system. 3 figs., 4 tabs.

Electric power development in the USSR

International Nuclear Information System (INIS)

Rudenko, Y.N.

1993-01-01

The generation of electric power in the USSR is based on the Unified Electric Power System (UEPS) whose network cover most of the habitable territory of the country. Therefore, the development of the UEPS governs the overall evolution of the electric power generation in the country. At present, eleven out of thirteen joint electric power systems, which supply electricity to most of the USSR, are operating within the UEPS. The total electric power generation in the country reached 1728 billion kWh in 1990, of which the UEPS supplied approximately 90%. About 70% of installed capacity of the UEPS is fossil-fuelled power plants, about 12 % is nuclear power plants, and about 18% is hydroelectric power plants. The system-forming grid of the UEPS is made up of transmission lines of 220, 330, 500 and 750 kV. The on-line supervisory control of the UEPS is achieved by four-level automated system of dispatch control (UEPS, joint electric power systems, regional electric power systems, electric power plants, substations,electric grid regions). The development and extension of the UEPS in the USSR ensure higher reliability and quality of electric power supply to end-users, combined with higher efficiency. The principal problem facing the UEPS are as follows: the need to ensure environmental protection and efficiency of the steam power plants; to improve the safety and efficiency of nuclear power plants. The solution to these problems will define the conditions of the UEPS development, as well as electric power systems of other countries, at least for the coming two decades. This paper characterizes the peculiarities of the UEPS development over the last 20 years, including the installed capacity structure and the system-forming electric power grid. Special attention is paid to the environmental problems related to functioning and development of the UEPS and to the means of their solution. (author)

Standard compensation for power cuts. Working group report

International Nuclear Information System (INIS)

2002-07-01

The Working Group was commissioned to draw up a proposal in the form of a Government Bill for provisions to be included in the Electricity Market Act on imposing an obligation on the distribution net operator to pay a standard compensation to the users of electricity for the event that they get no access to electricity. The Working Group should consider especially a model of standard compensation presented in the final report by Mr. Jarl Forsten, Deputy Director General of the Technical Research Centre of Finland VTT, published on 30 April 2002 that the amount of standard compensation should not depend on the reason for the power cut. The Working Group proposes that the Electricity Market Act should be amended by provisions providing that a distribution net operator shall pay to the user of electricity a standard compensation for power cuts lasting over 12 hours. The amount of compensation shall be based on the annual network service fee and a sliding scale of compensation related to the duration of the power cut shall be applied. The maximum compensation shall be paid when the power cut lasts more than five days. The maximum amount of individual compensations shall be fixed at EUR 700. The proposed provisions on standard compensation in the event of power cuts are aimed at amending the provisions in Chapter 6a of the Electricity Market Act on price reduction and compensation because of fault in the supply of electricity. The aim of the introduction of standard compensation for power cuts is to persuade distribution net operators to make an effort to minimize the time for power cuts. (orig.)

APR1400 Electrical Power System Conformance to SECY-91-078

Energy Technology Data Exchange (ETDEWEB)

Ha, Che-Wung; Kim, Yun-Ho [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

In this paper, the APR1400 electric power system for NRC-DC was described. In addition, the conformance to SECY 91-078 was evaluated. Enclosure 1 of the SECY provides an overview of the issue and states that the staff concludes that feeding the safety buses from the offsite power sources through non-safety buses or from a common transformer winding with non-safety loads is not the most reliable configuration. Such an arrangement increases the difficulty in properly regulating voltage at the safety buses, subjects the safety loads to transients caused by the non-safety loads, and adds additional failure points between the offsite power sources and safety loads. Therefore, it is the staff’s position that at least one offsite circuit to each redundant safety division should be supplied directly from one of the offsite power sources with no intervening non-safety buses, in such a manner that the offsite source can power the safety buses upon a failure of any non-safety bus. The APR1400 does not have an intervening nonsafety bus in the current offsite to onsite electrical configuration; however, the design does include nonsafety and safety buses coming from the same secondary side 4.16 kV transformer winding. Nevertheless, the APR1400 has designed the electrical interface system between offsite and onsite power with enhanced reliability measures to ensure that the nonsafety system will not impact the safety loads. The design complies with GDC 17 and also conforms to SECY-91-078.

Study of aircraft electrical power systems

Science.gov (United States)

1972-01-01

The formulation of a philosophy for devising a reliable, efficient, lightweight, and cost effective electrical power system for advanced, large transport aircraft in the 1980 to 1985 time period is discussed. The determination and recommendation for improvements in subsystems and components are also considered. All aspects of the aircraft electrical power system including generation, conversion, distribution, and utilization equipment were considered. Significant research and technology problem areas associated with the development of future power systems are identified. The design categories involved are: (1) safety-reliability, (2) power type, voltage, frequency, quality, and efficiency, (3) power control, and (4) selection of utilization equipment.

Safety goals for nuclear power

International Nuclear Information System (INIS)

Fischhoff, B.

1984-02-01

The key policy question in managing hazardous technologies is often some variant of How safe is safe enough. The US Nuclear Regulatory Commission has recently broached this topic by adopting safety goals defining acceptable risk levels for nuclear power plants. These goals are analyzed here with a general theory of standard setting (Fischhoff, 1983) which asks: (1) Are standards an appropriate policy tool in this case. (2) Can the Commission's safety philosophy be defended. (3) Do the operational goals capture that philosophy. The anlaysis shows the safety goals proposal to be sophisticated in some respects, incomplete in others. More generally, it points to difficulties with the concept of acceptable risk and any attempt to build policy instruments around it. Although focused on the NRC's safety goals, the present analysis is a prototype of what can be learned by similarly detailed consideration of other standards, not only for nuclear power but also for other hazardous technologies, as well as for issues unrelated to safety

Modular Power Standard for Space Explorations Missions

Science.gov (United States)

Oeftering, Richard C.; Gardner, Brent G.

2016-01-01

Future human space exploration will most likely be composed of assemblies of multiple modular spacecraft elements with interconnected electrical power systems. An electrical system composed of a standardized set modular building blocks provides significant development, integration, and operational cost advantages. The modular approach can also provide the flexibility to configure power systems to meet the mission needs. A primary goal of the Advanced Exploration Systems (AES) Modular Power System (AMPS) project is to establish a Modular Power Standard that is needed to realize these benefits. This paper is intended to give the space exploration community a "first look" at the evolving Modular Power Standard and invite their comments and technical contributions.

Safety Framework for Nuclear Power Source Applications in Outer Space

International Nuclear Information System (INIS)

2009-01-01

Nuclear power sources (NPS) for use in outer space have been developed and used in space applications where unique mission requirements and constraints on electrical power and thermal management precluded the use of non-nuclear power sources. Such missions have included interplanetary missions to the outer limits of the Solar System, for which solar panels were not suitable as a source of electrical power because of the long duration of these missions at great distances from the Sun. According to current knowledge and capabilities, space NPS are the only viable energy option to power some space missions and significantly enhance others. Several ongoing and foreseeable missions would not be possible without the use of space NPS. Past, present and foreseeable space NPS applications include radioisotope power systems (for example, radioisotope thermoelectric generators and radioisotope heater units) and nuclear reactor systems for power and propulsion. The presence of radioactive materials or nuclear fuels in space NPS and their consequent potential for harm to people and the environment in Earth's biosphere due to an accident require that safety should always be an inherent part of the design and application of space NPS. NPS applications in outer space have unique safety considerations compared with terrestrial applications. Unlike many terrestrial nuclear applications, space applications tend to be used infrequently and their requirements can vary significantly depending upon the specific mission. Mission launch and outer space operational requirements impose size, mass and other space environment limitations not present for many terrestrial nuclear facilities. For some applications, space NPS must operate autonomously at great distances from Earth in harsh environments. Potential accident conditions resulting from launch failures and inadvertent re-entry could expose NPS to extreme physical conditions. These and other unique safety considerations for the use of

Safety analyses of the electrical systems on VVER NPP

International Nuclear Information System (INIS)

Andel, J.

2004-01-01

Energoprojekt Praha has been the main entity responsible for the section on 'Electrical Systems' in the safety reports of the Temelin, Dukovany and Mochovce nuclear power plants. The section comprises 2 main chapters, viz. Offsite Power System (issues of electrical energy production in main generators and the link to the offsite transmission grid) and Onsite Power Systems (AC and DC auxiliary system, both normal and safety related). In the chapter on the off-site system, attention is paid to the analysis of transmission capacity of the 400 kV lines, analysis of transient stability, multiple fault analyses, and probabilistic analyses of the grid and NPP power system reliability. In the chapter on the on-site system, attention is paid to the power balances of the electrical sources and switchboards set for various operational and accident modes, checks of loading and function of service and backup sources, short circuit current calculations, analyses of electrical protections, and analyses of the function and sizing of emergency sources (DG sets and UPS systems). (P.A.)

Electric Power Lines : Questions and Answers on Research into Health Effects.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1994-05-01

Most people know that electric power lines, like the wiring in our homes, can cause serious electric shocks if we`re not careful. Many people also want to know whether the electric and magnetic fields (EMF) produced by power lines and other electrical devices cause health effects. The purpose of this booklet is to answer some common questions that the Bonneville Power Administration (BPA) receives about the possible effects of power lines on health. First, some basic electrical terms are defined, and electric and magnetic fields are debed. Next, answers are given to several questions about recent scientific studies. Some important information about electrical safety follows. We then describe how BPA is addressing public concerns about potential health effects of power lines. The last section tells you how to obtain more detailed information about the health and safety issues summarized in this booklet.

Nuclear power plant safety, the merits of separation

International Nuclear Information System (INIS)

Helander, L.I.; Tiren, L.I.

1977-01-01

The United States AEC General Design Criteria for Nuclear Power Plants are used worldwide as a basis for the assessment of nuclear plant safety. Several of these criteria require redundancy of safety systems, separation of protection and control systems, consideration of natural phenomena, etc. All these criteria point in one particular direction: the necessity for physically separating the various safety-related systems of a nuclear power plant, particularly with regard to single occurrences that may yield a multiple failure. Requirements in this regard have been amplified by the United States NRC Regulatory Guides and by IEEE Standards. The single occurrence that yields a multiple failure may be, for example, fire, pipe whip, missiles, flooding, hurricanes, or lightning. The paper discusses protection, against the quoted events and others, obtained through applying criteria regarding redundancy and separation of safety-related structures, systems and components. Such criteria affect nuclear plant design in many areas, such as building lay-out, arrangements for fire protection and ventilation, separation of mechanical systems and components, in particular emergency cooling systems, and separation of electric equipment and cables. Implementation of the ensuing design criteria for a BWR power plant is described. This design involves the separation of Emergency Cooling Systems into four 50% Capacity Systems which are independent and separated, including the distribution network for electric power from on-site standby diesel generators and the circuitry for the reactor protection system. The plant is subdivided into a number of fire zones each with its own independent ventilation system. The fire zones are further subdivided into a multitude of fire cells such that redundant subsystems are housed in separate cells. These design precautions with regard to fire are complemented by extensive fire fighting systems

Atomic power engineering under falsified safety standards

International Nuclear Information System (INIS)

Ackerman, A.J.

1974-01-01

In July 1970 the United States Department of Justice accused the American Society of Mechanical Engineers (ASME) of violating the Sherman Antitrust Act and of acting in restraint of trade by restricting the ASME Certificate of Authorization and the use of the Code Symbol Stamps to boilers and pressure vessels manufactured in the United States and Canada. During the succeeding two years attorneys for the parties in the case formulated a Consent Decree without a public confrontation in the Court. Furthermore, the membership of ASME was kept uninformed until October of 1972, after the Consent and Final Judgment had become effective and new procedures had been developed for allowing foreign manufacturers to apply the ASME Code Symbol Stamps to their products. As a consequence, a breakdown in engineered safety standards has been sanctioned and this is undermining the engineering profession's overriding reponsibility to protect the public health and safety. This breakdown of professional responsibility is especially serious in the new technology of atomic power. American insurance companies, which have traditionally written 100% insurance coverage for property damage and third party liability against explosions of high pressure steam boilers bearing the ASME Code Stamp, have refused to write such insurance coverage on nuclear reactors. In the author's opinion there is evidence that the Consent was formulated under collusive proceedings and he calls on the members and the Council of ASME to appeal for dismissal of the Consent Decree. 24 refs

Electric Power Lines : Questions and Answers on Research into Health Effects.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1993-11-01

Most people know that electric power lines, like the wiring in our homes, can cause serious electric shocks if we`re not careful. Many people also want to know whether the electric and magnetic fields (EMF) produced by power lines and other electrical devices cause health effects. The purpose of this pamphlet is to answer some common questions that the Bonneville Power Administration (BPA) receives about the possible effects of power lines on health. (BPA is the Pacific Northwest`s Federal electric power marketing agency.) First, some basic electrical terms are defined, and electric and magnetic fields are described. Next, answers are given to several questions about recent scientific studies. We then describe how BPA is addressing public concerns raised by these studies. Some important information about electrical safety follows. The last section tells you how to obtain more detailed information about the health and safety issues summarized in this pamphlet.

Standards for radiation protection instrumentation: design of safety standards and testing procedures

International Nuclear Information System (INIS)

Meissner, Frank

2008-01-01

This paper describes by means of examples the role of safety standards for radiation protection and the testing and qualification procedures. The development and qualification of radiation protection instrumentation is a significant part of the work of TUV NORD SysTec, an independent expert organisation in Germany. The German Nuclear Safety Standards Commission (KTA) establishes regulations in the field of nuclear safety. The examples presented may be of importance for governments and nuclear safety authorities, for nuclear operators and for manufacturers worldwide. They demonstrate the advantage of standards in the design of radiation protection instrumentation for new power plants, in the upgrade of existing instrumentation to nuclear safety standards or in the application of safety standards to newly developed equipment. Furthermore, they show how authorities may proceed when safety standards for radiation protection instrumentation are not yet established or require actualization. (author)

Nuclear power systems: Their safety. Current issue review

International Nuclear Information System (INIS)

Myers, L.C.

1994-04-01

Human beings utilize energy in many forms and from a variety of sources. A number of countries have chosen nuclear-electric generation as a component of their energy system. At the end of 1992, there were 419 power reactors operating in 29 countries, accounting for more than 15% of the world's production of electricity. In 1992, 13 countries derived at least 25% of their electricity from nuclear units, with Lithuania leading at just over 78%, followed closely by France at 72%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 53 power reactors are under construction in 14 countries outside the former USSR. Within the ex-USSR countries, six new reactors are currently under construction. No human endeavour carries the guarantee of perfect safety and the question of whether of not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986 in the then Soviet Union, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor irrevocably changed all that. This disaster brought the matter of nuclear safety into the public mind in a dramatic fashion. Subsequent opening of the ex-Soviet nuclear power program to outside scrutiny has done little to calm people's concerns about the safety of nuclear power in that part of the world. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents that have occurred to date, as well as more recent, less dramatic events touching on the safety issue. (author). 7 refs

International safety standards and regulatory practices and their application to Brazilian nuclear power plants - a realistic view

International Nuclear Information System (INIS)

Almeida, Claudio; Camargo, Claudio

1999-01-01

An international nuclear safety regime is being established through a series of binding safety conventions, voluntarily adopted international safety standards and an accompanying peer review process. The basis for the evaluation of each country performance within this international regime should be the international practices. However, local conditions should be taken into account to avoid undue stress of the limited resources available to countries with a limited nuclear power programme. This work reviews the current international nuclear safety and discusses the application of some international practices to the Brazilian situation, considering the peculiarities of the national nuclear power programme and the limitations of the available financial and human resources. (author)

Nuclear Power and Ghana's Future Electricity Generation

International Nuclear Information System (INIS)

Ennison, I.; Dzobo, M.

2011-01-01

One of the major challenges facing Ghana in her developmental efforts is the generation of adequate and affordable electricity to meet increasing demand. Problems with the dependency on hydro power has brought insecurity in electricity supply due to periodic droughts. Thermal power systems have been introduced into the electricity generation mix to complement the hydro power supply but there are problems associated with their use. The high price of crude oil on the international market has made them expensive to run and the supply of less expensive gas from Steps are being taken to run the thermal plants on less expensive gas from Nigeria has delayed due to conflicts in the Niger Delta region and other factors. The existing situation has therefore called for the diversification of the electricity generation mix so as to ensure energy security and affordable power supply. This paper presents the nuclear option as a suitable alternative energy source which can be used to address the energy supply problems facing the nation as well the steps being taken towards its introduction in the national energy mix. In addition, electricity demand projections using the MAED model as well as other studies are presented. The expected electricity demand of 350000 GWh (4000MWyr) in 2030, exceeds the total electricity supply capability of the existing hydropower system, untapped hydro resources and the maximum amount of gas that can be imported from Nigeria through the West Africa pipeline. Also presented is a technological assessment on the type of nuclear reactor to be used. The technological assessment which was done based on economics, grid size, technological maturity, passive safety and standardization of reactor design, indicate that a medium sized pressurized water reactor (i.e. a PWR with capacity 300MW to 700MW) is the most favourable type of reactor. In addition the challenges facing the implementation of the nuclear power programme in Ghana are presented. (author)

EHV AC undergrounding electrical power performance and planning

CERN Document Server

Benato, Roberto

2014-01-01

Analytical methods of cable performance in EHV AC electrical power are discussed in this comprehensive reference. Descriptions of energization, power quality, cable safety constraints and more, guide readers in cable planning and power network operations.

On-site electric power source facility for Japanese nuclear power plant

International Nuclear Information System (INIS)

Oohara, T.

1986-01-01

Trends of construction of nuclear power plants in Japan, occurrence rate of incidents/failures of electric facilities, major example of incidents/failures, their countermeasure to prevent recurrence are introduced. Furthermore, safety administration system of the Government, electric utilities and manufacturers, and various countermeasures to prevent incident/ failure of electrical facilities from the hardware and software sides are discussed. (author)

On-site electric power source facility for Japanese nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Oohara, T. [Incident/Failure Analysis and Evaluation Office, Nuclear Power Safety Information Research Centre, Nuclear Power Engineering Test Centre, 2nd Floor, Shuwa-Kamiyacho Bldg., 3-13, 4-Chome, Toranomon Minato-ku, Tokyo 105 (Japan)

1986-02-15

Trends of construction of nuclear power plants in Japan, occurrence rate of incidents/failures of electric facilities, major example of incidents/failures, their countermeasure to prevent recurrence are introduced. Furthermore, safety administration system of the Government, electric utilities and manufacturers, and various countermeasures to prevent incident/ failure of electrical facilities from the hardware and software sides are discussed. (author)

Electric Power Lines : Questions and Answers on Research into Health Effects.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1995-06-01

Most people know that electric power lines, like the wiring in our homes, can cause serious electric shocks if we`re not careful. Many people also want to know whether the EMF (electric and magnetic fields) produced by power lines and other electrical devices affect our health. Although no adverse health effects of electric power EMF have been confirmed, there is continued scientific uncertainty about this issue. Research on EMF is ongoing throughout the world. The purpose of this booklet is to answer some common questions that the BPA (Bonneville Power Administration) receives about the possible effects of power lines on health. First, some basic electrical terms are defined, and electric and magnetic fields are debed. Next, answers are given to several questions about recent scientific studies. Some important information about electrical safety follows. We then describe how BPA is addressing public concerns about potential health effects of power lines. The last section tells you how to obtain more detailed information about the health and safety issues summarized in this booklet.

Electrical, instrumentation, and control codes and standards

International Nuclear Information System (INIS)

Kranning, A.N.

1978-01-01

During recent years numerous documents in the form of codes and standards have been developed and published to provide design, fabrication and construction rules and criteria applicable to instrumentation, control and power distribution facilities for nuclear power plants. The contents of this LTR were prepared by NUS Corporation under Subcontract K5108 and provide a consolidated index and listing of the documents selected for their application to procurement of materials and design of modifications and new construction at the LOFT facility. These codes and standards should be applied together with the National Electrical Code, the ID Engineering Standards and LOFT Specifications to all LOFT instrument and electrical design activities

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Chinese Ed.)

International Nuclear Information System (INIS)

2012-01-01

On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (French Ed.)

International Nuclear Information System (INIS)

2012-01-01

On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Arabic Ed.)

International Nuclear Information System (INIS)

2012-01-01

On the basis of the principles included in the Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, this Safety Requirements publication establishes requirements applicable to the design of nuclear power plants. It covers the design phase and provides input for the safe operation of the power plant. It elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safety design of Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Ouyang Yu; Zhang Lian; Du Shenghua; Zhao Jiayu

1984-01-01

Safety issues have been greatly emphasized through the design of the Qinshan Nuclear Power Plant. Reasonable safety margine has been taken into account in the plant design parameters, the design incorporated various safeguard systems, such as engineering safety feature systems, safety protection systems and the features to resist natural catastrophes, e. g. earthquake, hurricanes, tide and so on. Preliminary safety analysis and environmental effect assessment have been done and anti-accident provisions and emergency policy were carefully considered. Qinshan Nuclear Power Plant safety related systems are designed in accordance with the common international standards established in the late 70's, as well as the existing engineering standard of China

Health protection and industrial safety. Nuclear power plants

International Nuclear Information System (INIS)

1987-03-01

The standard applies to primary circuit components including its auxiliary facilities, and of the secondary circuit of nuclear power plants with pressurized water reactors; to lifting gear and load take-ups for the transport of nuclear fuel and primary circuit components; to elevators within the containment, and to electrical installations. Part 3 specifies the behaviour of workers in conformity with safety provisions during operation, inspection, lifetime surveillance, functional testing, and maintenance. Special demands are made on the water regime and on elevators, lifting gear, and load take-ups

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2017-01-01

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

Safety policy in the production of electricity

International Nuclear Information System (INIS)

Siddall, E.

1982-01-01

When safety is properly understood, defined and quantified, it can be seen that the development of our present industrial civilization has resulted in a progressive improvement in human safety. Increased safety has come with increased wealth in such close association that a high degree of cause-and-effect relationship must be considered. The quantitative relationship between wealth production and safety improvement is derived from different sources of evidence. When this is applied to the wealth production from electricity generation in a standard module of population in an advanced society, a safety benefit is indicated which exceeds the assessed direct risk associated with the electricity generation by orders of magnitude. It appears that a goal or policy intended to confer the greatest safety benefit to the population would result in attitudes and actions diametrically opposite to those which are conventional at the moment

Electrical safety code manual a plan language guide to national electrical code, OSHA and NFPA 70E

CERN Document Server

Keller, Kimberley

2010-01-01

Safety in any workplace is extremely important. In the case of the electrical industry, safety is critical and the codes and regulations which determine safe practices are both diverse and complicated. Employers, electricians, electrical system designers, inspectors, engineers and architects must comply with safety standards listed in the National Electrical Code, OSHA and NFPA 70E. Unfortunately, the publications which list these safety requirements are written in very technically advanced terms and the average person has an extremely difficult time understanding exactly what they need to

Safety assessment of emergency power systems for nuclear power plants

International Nuclear Information System (INIS)

1992-01-01

This publication is intended to assist the safety assessor within a regulatory body, or one working as a consultant, in assessing the safety of a given design of the emergency power systems (EPS) for a nuclear power plant. The present publication refers closely to the NUSS Safety Guide 50-SG-D7 (Rev. 1), Emergency Power Systems at Nuclear Power Plants. It covers therefore exactly the same technical subject as that Safety Guide. In view of its objective, however, it attempts to help in the evaluation of possible technical solutions which are intended to fulfill the safety requirements. Section 2 clarifies the scope further by giving an outline of the assessment steps in the licensing process. After a general outline of the assessment process in relation to the licensing of a nuclear power plant, the publication is divided into two parts. First, all safety issues are presented in the form of questions that have to be answered in order for the assessor to be confident of a safe design. The second part presents the same topics in tabulated form, listing the required documentation which the assessor has to consult and those international and national technical standards pertinent to the topics. An extensive reference list provides information on standards. 1 tab

Safety provisions of nuclear power plants

International Nuclear Information System (INIS)

Niehaus, F.

1994-01-01

Safety of nuclear power plants is determined by a deterministic approach complemented by probabilistic considerations. Much use has been made of the wealth of information from more than 6000 years of reactor operation. Design, construction and operation is governed by national and international safety standards and practices. The IAEA has prepared a set of Nuclear Safety Standards as recommendations to its Member States, covering the areas of siting, design, operations, quality assurance, and governmental organisations. In 1988 the IAEA published a report by the International Nuclear Safety Advisory Group on Basic Safety Principles for Nuclear Power Plants, summarizing the underlying objectives and principles of excellence in nuclear safety and the way in which its aspects are interrelated. The paper will summarize some of the key safety principles and provisions, and results and uses of Probabilistic Safety Assessments. Some comments will be made on the safety of WWER 440/230 and WWER-1000 reactors which are operated on Bulgaria. 8 figs

Multi-reactor power system configurations for multimegawatt nuclear electric propulsion

Science.gov (United States)

George, Jeffrey A.

1991-01-01

A modular, multi-reactor power system and vehicle configuration for piloted nuclear electric propulsion (NEP) missions to Mars is presented. Such a design could provide enhanced system and mission reliability, allowing a comfortable safety margin for early manned flights, and would allow a range of piloted and cargo missions to be performed with a single power system design. Early use of common power modules for cargo missions would also provide progressive flight experience and validation of standardized systems for use in later piloted applications. System and mission analysis are presented to compare single and multi-reactor configurations for piloted Mars missions. A conceptual design for the Hydra modular multi-reactor NEP vehicle is presented.

Slovak Electric, plc, Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

1999-01-01

In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

Safety policy in the production of electricity

International Nuclear Information System (INIS)

Siddall, E.

1983-01-01

When safety is properly understood, defined and quantified, it can be seen that the development of our present industrial civilization has resulted in a progressive and great improvement in human safety which is still continuing. Increased safety has come with increased wealth in such close association that a high degree of cause-and-effect relationship must be considered. The quantitative relationship between wealth production and safety improvement is derived from different sources of evidence. When this is applied to the wealth production from electricity generation in a standard module of population in an advanced society, a safety benefit is indicated which exceeds the assessed direct risk associated with the electricity generation by orders of magnitude. It appears that a goal or policy intended to confer the greatest safety benefit to the population would result in attitudes and actions diametrically opposite to those which are conventional at the moment

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Evaluation of the induced electric field and compliance procedure for a wireless power transfer system in an electrical vehicle

International Nuclear Information System (INIS)

Laakso, Ilkka; Hirata, Akimasa

2013-01-01

In this study, an induced electric field in a human body is evaluated for the magnetic field leaked from a wireless power transfer system for charging an electrical vehicle. The magnetic field from the wireless power transfer system is modelled computationally, and its effectiveness is confirmed by comparison with the field measured in a previous study. The induced electric field in a human standing around the vehicle is smaller than the allowable limit prescribed in international guidelines, although the magnetic field strength in the human body is locally higher than the allowable external field strength. Correlation between the external magnetic field and the induced electric field is confirmed to be reasonable at least in the standing posture, which is the case discussed in the international standard. Based on this finding, we discussed and confirmed the applicability of a three-point magnetic field measurement at heights of 0.5, 1.0, and 1.5 m for safety compliance. (paper)

Evaluation of the induced electric field and compliance procedure for a wireless power transfer system in an electrical vehicle.

Science.gov (United States)

Laakso, Ilkka; Hirata, Akimasa

2013-11-07

In this study, an induced electric field in a human body is evaluated for the magnetic field leaked from a wireless power transfer system for charging an electrical vehicle. The magnetic field from the wireless power transfer system is modelled computationally, and its effectiveness is confirmed by comparison with the field measured in a previous study. The induced electric field in a human standing around the vehicle is smaller than the allowable limit prescribed in international guidelines, although the magnetic field strength in the human body is locally higher than the allowable external field strength. Correlation between the external magnetic field and the induced electric field is confirmed to be reasonable at least in the standing posture, which is the case discussed in the international standard. Based on this finding, we discussed and confirmed the applicability of a three-point magnetic field measurement at heights of 0.5, 1.0, and 1.5 m for safety compliance.

Changing An Electrical Safety Culture - The Importance of Understanding Why.

Energy Technology Data Exchange (ETDEWEB)

Waters, Richard Thomas [Idaho National Laboratory

2015-12-01

Abstract – Electrical workers, regardless of experience, are faced with a major barrier when first introduced to NFPA 70E, “The Standard for Electrical Safety in the Workplace,” and an erroneous electrical safety culture pre-exists. This paper describes, from the author’s point of view, the barrier that he and other electrical workers have experienced and his insight into overcoming the barrier. The author in conclusion will present a series of techniques that can be used to assist other electrical workers in overcoming the barrier.

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 4, In-vehicle safety

Energy Technology Data Exchange (ETDEWEB)

Mark, J.

1992-11-01

This report is the last of four volumes that identify and assess the environmental, health, and safety issues that may affect the commercial-scale use of sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles. The reports are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers the in-vehicle safety issues of electric vehicles powered by Na/S batteries. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, and private industry. It has three major goals: (1) to identify the unique hazards associated with electric vehicle (EV) use; (2) to describe the existing standards, regulations, and guidelines that are or could be applicable to these hazards; and (3) to discuss the adequacy of the existing requirements in addressing the safety concerns of EVs.

Slovak Electric, plc, Bohunice Nuclear Power Plant

International Nuclear Information System (INIS)

1999-01-01

A brief account of activities carried out by the Bohunice Nuclear Power Plant in 1998 is presented. These activities are reported under the headings: (1) Operation and electric power generation; (2) Nuclear and radiation safety; (3) Maintenance and scheduled refuelling out-gages; (4) Investment and WWER units upgrading; (5) Power Plants Personnel; (6) Public relations

Comparison of vibration damping of standard and PDCPD housing of the electric power steering system

Science.gov (United States)

Płaczek, M.; Wróbel, A.; Baier, A.

2017-08-01

A comparison of two different types of electric power steering system housing is presented. The first considered type of the housing was a standard one that is made of an aluminium alloy. The second one is made of polydicyclopentadiene polymer (PDCPD) and was produced using the RIM technology. Considered elements were analysed in order to verify their properties of vibrations damping. This property is very important taking into account noise generated by elements of a car’s power steering system. During the carried out tests vibrations of analysed power steering housings were measured using Marco Fiber Composite (MFC) piezoelectric transducers. Results obtained for both considered power steering housings in case of the same parameters of vibrations excitations were measured and juxtaposed. Obtained results were analysed in order to verify if the housing made of PDCPD polymer has better properties of vibration damping than the standard one.

Electricity supplies in a French nuclear power station

International Nuclear Information System (INIS)

2011-01-01

As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

International Nuclear Information System (INIS)

Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

2003-04-01

The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

Utility regulation-The scope and structure of electrical safety regulation

International Nuclear Information System (INIS)

Abbott, Malcolm; Cohen, Bruce

2011-01-01

As a consequence of policies in Australia and New Zealand to increase competition in the utilities sector, regulatory agencies have been created in each state to provide independent and authorative advice on matters such as electricity pricing, access to infrastructure, service quality and security of supply. In addition arrangements have been established to maintain safety standards in the industry. The purpose of this paper is to discuss the major issues that have arisen in the creation of regulatory agencies responsible for electrical safety standards in Australia and New Zealand, and how they have impacted on liberalised electricity markets. - Highlights: → Policies in Australia and New Zealand to increase competition have led to the creation of electrical safety agencies. → These agencies have been created in response to perceived market failures. → There is a variance in agencies in terms of their independence and industry coverage. → These agencies have been created at a time of falling fatalities.

Safety and nuclear power

International Nuclear Information System (INIS)

Gittus, John; Gunning, Angela.

1988-01-01

Representatives of the supporters and opponents of civil nuclear power put forward the arguments they feel the public should consider when making up their mind about the nuclear industry. The main argument in favour of nuclear power is about the low risk in comparison with other risks and the amount of radiation received on average by the population in the United Kingdom from different sources. The aim is to show that the nuclear industry is fully committed to the cause of safety and this has resulted in a healthy workforce and a safe environment for the public. The arguments against are that the nuclear industry is deceitful, secretive and politically motivated and thus its arguments about safety, risks, etc, cannot be trusted. The question of safety is considered further - in particular the perceptions, definitions and responsibility. The economic case for nuclear electricity is not accepted. (U.K.)

Summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant

International Nuclear Information System (INIS)

Choi, S. Y.; Han, S. H.

2004-01-01

The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA of Korean nuclear power plants. We have performed a study to develop the component reliability DB and S/W for component reliability analysis. Based on the system, we had have collected the component operation data and failure/repair data during plant operation data to 1998/2000 for YGN 3,4/UCN 3,4 respectively. Recently, we have upgraded the database by collecting additional data by 2002 for Korean standard nuclear power plants and performed component reliability analysis and Bayesian analysis again. In this paper, we supply the summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant and describe the plant specific characteristics compared to the generic data

Verification Results of Safety-grade Optical Modem for Core Protection Calculator (CPC) in Korea Standard Nuclear Power Plant (KSNP)

Energy Technology Data Exchange (ETDEWEB)

Kim, Jangyeol; Son, Kwangseop; Lee, Youngjun; Cheon, Sewoo; Cha, Kyoungho; Lee, Jangsoo; Kwon, Keechoon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-05-15

We confirmed that the coverage criteria for a safety-grade optical modem of a Core Protection Calculator is satisfactory using a traceability analysis matrix between high-level requirements and lower-level system test case data set. This paper describes the test environment, test components and items, a traceability analysis, and system tests as a result of system verification and validation based on Software Requirement Specifications (SRS) for a safety-grade optical modem of a Core Protection Calculator (CPC) in a Korea Standard Nuclear Power Plant (KSNP), and Software Design Specifications (SDS) for a safety-grade optical modem of a CPC in a KSNP. All tests were performed according to the test plan and test procedures. Functional testing, performance testing, event testing, and scenario based testing for a safety-grade optical modem of a Core Protection Calculator in a Korea Standard Nuclear Power Plant as a thirty-party verifier were successfully performed.

Electric power distribution. Elektrische Energieverteilung

Energy Technology Data Exchange (ETDEWEB)

Fricke, H; Frohne, H; Vaske, P

1982-01-01

The first chapter on electric power supply networks discusses transmitting media, their characteristic values, and the dimensioning of electric lines and networks; cables are given particular attention. High-voltage d.c. transmission and reactive power compensation are discussed. The next chapter describes the calculation of short-circuits and earth leakages for various neutral circuits on the basis of symmetric components. The newly introduced mesh current method for complex calculation of electric networks makes use of the potential of pocket computers. Chapter 3 discusses protective devices, i.e. earth systems and electronic protection. The next two chapters describe switch gear and power plants, including recent technical changes. The final chapter, which discusses the electric power industry, has been rewritten and extended. Methods of calculation, e.g. annual cost and cash value, are applied to transmitting media and plants. There is an extensive appendix with characteristic values of cables and overhead lines, graphical symbols, distinguishing signs of wiring diagrams, a bibliography of books, DIN standards, VDE specifications, and formulas.

Status of electrical safety in Indira Gandhi Centre for Atomic Research

International Nuclear Information System (INIS)

Kandasamy, S.; Karthikeyan, S.V.; Senthilkumar, B.; Shunmugam, U.; Kannan, S.E.

1999-01-01

Electrical Systems in Indira Gandhi Centre for Atomic Research (IGCAR), comprising of facilities such as Fast Breeder Test Reactor (FBTR) and various Research and Development laboratories form a complex network providing practically uninterrupted power supply to all the facilities meeting their energy demands. The safety record of the Centre for the past 25 years has been very good and the number of electrical accidents in the Centre has been less. This paper brings out the status of the electrical safety in IGCAR and indicates the steps to be taken to improve the safety culture. It also utilizes the measure to be provided for improving the electrical safety in the works executed by contractors

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

Report on assessment of electrical equipment aging for nuclear power plant (AEA), FY2011

International Nuclear Information System (INIS)

Minakawa, T.

2012-11-01

Electrical components with safety function used in nuclear power plants, such as cables, medium voltage motors, low voltage motors, electrical penetration of reactor containment vessel, motor operated valve, pressure transmitter, temperature detector, etc, are required to be operational under the environment of design basis event (DBE) to shut down a reactor safely and to prevent radioactive materials from being leaked to outside. Polymer materials used as parts of these equipments are gradually degraded by thermal and radiation environment in the normal operation. In addition, the degradation is thought to progress rapidly when they are exposed to the DBE environment and a decrease in performance of the equipment may be caused. From these reason, electrical components with safety function are tested for long-term integrity in accordance with IEEE standard. However, conventional method of accelerated aging which assumes thermal and radiation aging during normal operation is said to have uncertainty in simulating the degradation given in actual operating environment. To address this issue, the project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) was carried out and 'Guide for Cable Environmental Qualification Test for Nuclear Power Plant' was developed. The need for developing an aging evaluation method for other electrical and I and C components was pointed out in the 'Strategy maps 2007', prepared by the cooperation among government, industry and academia. Under the circumstance, the project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008. In this study, parts of electrical and I and C component with safety function used in nuclear power plant whose aging needs to be considered are employed as specimens, and their aging characteristics under the thermal environment and the combined radiation and thermal environment are obtained (herein after referred to as 'critical part test

Principles of electrical safety

CERN Document Server

Sutherland, Peter E

2015-01-01

Principles of Electrical Safety discusses current issues in electrical safety, which are accompanied by series' of practical applications that can be used by practicing professionals, graduate students, and researchers. .  Provides extensive introductions to important topics in electrical safety Comprehensive overview of inductance, resistance, and capacitance as applied to the human body Serves as a preparatory guide for today's practicing engineers

Radiological safety of nuclear power plants in India

International Nuclear Information System (INIS)

Sathish, A.V.

2015-01-01

Safety in nuclear power plants (NPPs) is often less understood and more talked about, thus the author wanted to share the facts to clear the myths. Safety is accorded overriding priority in all the activities. All nuclear facilities are sited, designed, constructed, commissioned and operated in accordance with strict quality and safety standards. Principles of defence in depth, redundancy and diversity are followed in the design of all nuclear facilities and their systems/components. PPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, approved standard operating and maintenance procedures, a well-defined waste management methodology, periodically rehearsed emergency preparedness and disaster management plans. The regulatory framework in the country is robust, with the independent Atomic Energy Regulatory Board (AERB) having powers to frame the policies, laying down safety standards, monitoring and enforcing all the safety provisions. As a result, India's safety record has been excellent in over 400 reactor years of operation of power reactors

Measures for reinforcing safety at the Ohma Nuclear Power Plant

International Nuclear Information System (INIS)

Ishikawa, Hiroyasu; Iwata, Kichisa; Koga, Kaoru

2013-01-01

Electric Power Development Co., Ltd. ('J-POWER') has been moving ahead with the Ohma Nuclear Power Project at Ohma-machi, Shimokita-gun in Aomori Prefecture and commenced the construction of an Advanced Boiling Water Reactor (ABWR) in May 2008. In light of the Fukushima Daiichi Nuclear Power Station Incident, J-POWER has undertaken an investigation of various measures for reinforcing safety at the Ohma nuclear power plant. These measures include a range of anti-tsunami measures, measures to ensure emergency power sources and ultimate heat removal functions, and responses for severe accidents. While consistently and properly reflecting the necessary measures, J-POWER will continue to ensure the creation of a safe power plant. J-POWER intends to appropriately reflect at all times new standards of technology established by the Nuclear Regulation Authority and makes concerted efforts to build a safe nuclear power plant in which the local community can have confidence. (author)

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

Electric power in Canada 1993

International Nuclear Information System (INIS)

1994-01-01

The electric power industry in Canada in 1993 is reviewed. Items discussed include: the international context of Canadian electricity; regulatory structures; electricity and the environment; electricity consumption; electricity generation; generating capacity and reserve; electricity trade; transmission; electric utility investment and financing; costing and pricing; electricity outlook; demand-side management; and non-utility generation. Information is appended on installed capacity and electrical energy consumption in Canada, installed generating capacity, conventional thermal capacity by principal fuel type, provincial electricity imports and exports, Canadian electricity exports by exporter and importer, generation capacity by type, installed generating capacity expansion in Canada by station, federal environmental standards and guidelines, and prices paid by major electric utilities for non-utility generation. 26 figs., 90 tabs

IAEA Safety Standards

International Nuclear Information System (INIS)

2016-09-01

The IAEA Safety Standards Series comprises publications of a regulatory nature covering nuclear safety, radiation protection, radioactive waste management, the transport of radioactive material, the safety of nuclear fuel cycle facilities and management systems. These publications are issued under the terms of Article III of the IAEA’s Statute, which authorizes the IAEA to establish “standards of safety for protection of health and minimization of danger to life and property”. Safety standards are categorized into: • Safety Fundamentals, stating the basic objective, concepts and principles of safety; • Safety Requirements, establishing the requirements that must be fulfilled to ensure safety; and • Safety Guides, recommending measures for complying with these requirements for safety. For numbering purposes, the IAEA Safety Standards Series is subdivided into General Safety Requirements and General Safety Guides (GSR and GSG), which are applicable to all types of facilities and activities, and Specific Safety Requirements and Specific Safety Guides (SSR and SSG), which are for application in particular thematic areas. This booklet lists all current IAEA Safety Standards, including those forthcoming

The safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

Do nuclear power plants present an unjustifiable risk Can there be confidence in their safety The Uranium Institute invited a group of senior safety experts from eight different Western countries operating different types of reactors to provide an authoritative explanation for non-specialists of the basic principles of reactor safety, their application and their implications. The report presents the group's opinion on the level of safety achieved in the Western nuclear power plants with which the authors are directly familiar. Although many of the points made may well also be true for non-Western reactors, the report does not cover them except where specifically stated. It does describe and discuss the causes of the Chernobyl disaster. It does not compare nuclear power with other fuels, nor does it deal with its benefits, since however great the benefits from the peaceful use of nuclear power, and its own advantages over other fuels, they could not compensate for lack of safety. The conclusion reached is that the risk associated with electricity production at nuclear power plants can be kept very low. Proper use of the extensive knowledge available today can guarantee operation of nuclear power plants at very high safety levels, carrying very low risks, both to health and of contamination of the environment: risks that are continually lowered by upgrading existing plants and their operation, and by the design of future power plants. (author).

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2017-01-01

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

Power Sales to Electric Utilities

Energy Technology Data Exchange (ETDEWEB)

None

1989-02-01

The Public Utilities Regulatory Policies Act (PURPA) of 1979 requires that electrical utilities interconnect with qualifying facilities and purchase electricity at a rate based upon their full avoided costs (i.e., costs of providing both capacity and energy). Qualifying facilities (QF) include solar or geothermal electric units, hydropower, municipal solid waste or biomass-fired power plants, and cogeneration projects that satisfy maximum size, fuel use, ownership, location, and/or efficiency criteria. In Washington State, neither standard power purchase prices based upon a proxy ''avoided plant'', standard contracts, or a standard offer process have been used. Instead, a variety of power purchase contracts have been negotiated by developers of qualifying facilities with investor-owned utilities, public utility districts, and municipally-owned and operated utilities. With a hydro-based system, benefits associated with resource acquisition are determined in large part by how compatible the resource is with a utility's existing generation mix. Power purchase rates are negotiated and vary according to firm energy production, guarantees, ability to schedule maintenance or downtime, rights of refusal, power plant purchase options, project start date and length of contract; front-loading or levelization provisions; and the ability of the project to provide ''demonstrated'' capacity. Legislation was also enacted which allows PURPA to work effectively. Initial laws established ownership rights and provided irrigation districts, PUDs, and municipalities with expanded enabling powers. Financial processes were streamlined and, in some cases, simplified. Finally, laws were passed which are designed to ensure that development proceeds in an environmentally acceptable manner. In retrospect, PURPA has worked well within Washington. In the state of Washington, 20 small-scale hydroelectric projects with a combined generating capacity of

Results of evaluation of periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, Tokyo Electric Power Co., Inc

International Nuclear Information System (INIS)

1994-01-01

No. 1 plant in Fukushima No. 1 Nuclear Power Station started the commercial power generation in March, 1971, and has continued the operation for more than 23 years. During this period, the countermeasures to troubles, periodic inspections, and the maintenance by the electric power company have been carried out. These states are to be recollected from the viewpoints of the comprehensive evaluation of the operation experiences and the reflection of the latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor was 50.1% on the average of about 23 years, but in the last 10 years, it was improved to 59.7%. In the last five years, the rate of occurrence of unexpected shutdown was 0.4 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, radioactive waste management and the reflection of the experience of troubles and the latest technological knowledge to the improvement of safety have been carried out properly. The work plan for disaster prevention was established. (K.I.)

An engineer-constructor's view of nuclear power plant safety

International Nuclear Information System (INIS)

Landis, J.W.; Jacobs, S.B.

1984-01-01

At SWEC we have been involved in the development of safety features of nuclear power plants ever since we served as the engineer-constructur for the first commerical nuclear power station at Shippingport, Pennsylvania, in the 1950s. Our personnel have pioneered a number of safety innovations and improvements. Among these innovations is the subatmospheric containment for pressurized water reactor (PWR) power plants. This type of containment is designed so that leakage will terminate within 1 to 2 hours of the worst postulated loss of coolant accident. Other notable contributions include first use of reinforced-concrete atmospheric containments for PWR power plants and of reinforced-concrete, vapor-suppression containments for boiling water reactor (BWR) power plants. Both concepts meet rigorous U.S. safety requirements. SWEC has performed a substantial amount of work on developing standardized plant designs and has developed standardized engineering and construction techniques and procedures. Standardization concepts are being developed in Canada, France, USSR, and Germany, as well as in the United States. The West German convoy concept, which involves developing a number of standardized plants in a common effort, has been quite successful. We believe standardization contributes to safety in a number of ways. Use of standardized designs, procedures, techniques, equipment, and methods increases efficiency and results in higher quality. Standardization also reduces the design variations with which plant operators, emergency teams, and regulatory personnel must be familiar, thus increasing operator capability, and permits specialized talents to be focused on important safety considerations. (orig./RW)

New reactor technology: safety improvements in nuclear power systems.

Science.gov (United States)

Corradini, M L

2007-11-01

Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

Slovak Electric, plc, Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

2000-01-01

In this popular scientific brochure a brief description of history construction of Bohunice Nuclear Power Plant is presented. The chart of electricity generation in WWER 440/V-213 nuclear power plant is described. Operation and safety improvements at Mochovce NPP as well as environment protection are presented. Basic data of Mochovce NPP are included

Environmental qualification test of electrical penetration for nuclear power stations

International Nuclear Information System (INIS)

Kooziro, Tetsuya; Nakagawa, Akitoshi; Toyoda, Shigeru; Uno, Shunpei

1979-01-01

Environmental qualification test was conducted according to IEEE Std. 323-1974 in order to evaluate the safety and reliability of electrical penetration of PWR type nuclear power station. Electrical penetration is the assemblies of electric cables attached to the containment vessel and penetrate through the vessel. Since it is a part of the vessel, it is deemed to be one of the primary safety equipments that are important for the safety and reliability of nuclear power stations. Environmental tests were conducted continuously as to heat cycle, vibration and LOCA with the full size specimens of bushing type, pigtail type and triaxial cable type and at the same time thermal life and irradiation tests were conducted on the insulation materials used, in order to obtain the comprehensive evaluation of their electrical and mechanical characteristics. As the result, they all satisfied the requirements for the circuits for actual use during and after various environmental qualification tests according to IEEE Std. 323. (author)

Radiation protection aspects of design for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Electric power in Canada 1993

International Nuclear Information System (INIS)

1994-01-01

The electric power industry in Canada in 1993 is reviewed. Items discussed include: the international context of Canadian electricity; regulatory structures; electricity and the environment; electricity consumption; electricity generation; generating capacity and reserve; electricity trade; transmission; electric utility investment and financing; costing and pricing; electricity outlook; demand-side management; and non-utility generation. Appended information is presented on installed capacity and electrical energy consumption in Canada, installed generating capacity, conventional thermal capacity by principal fuel type, provincial electricity imports and exports, Canadian electricity exports by exporter and importer, generation capacity by type, installed generating capacity expansion in Canada by station, federal environmental standards and guidelines, and prices paid by major electric utilities for non-utility generation. 23 figs., 95 tabs

Electric power in Canada 1992

International Nuclear Information System (INIS)

1993-01-01

The electric power industry in Canada in 1991 is reviewed. Items discussed include: the international context of Canadian electricity; regulatory structures; electricity and the environment; electricity consumption; electricity generation; generating capacity and reserve; electricity trade; transmission; electric utility investment and financing; costing and pricing; electricity outlook; demand-side management; and non-utility generation. Appended information is presented on installed capacity and electrical energy consumption in Canada, installed generating capacity, conventional thermal capacity by principal fuel type, provincial electricity imports and exports, Canadian electricity exports by exporter and importer, generation capacity by type, installed generating capacity expansion in Canada by station, federal environmental standards and guidelines, and prices paid by major electric utilities for non-utility generation. 26 figs., 90 tabs

Power amplifier circuits for functional electrical stimulation systems

Directory of Open Access Journals (Sweden)

Delmar Carvalho de Souza

Full Text Available Abstract Introduction: Functional electrical stimulation (FES is a technique that has been successfully employed in rehabilitation treatment to mitigate problems after spinal cord injury (SCI. One of the most relevant modules in a typical FES system is the power or output amplifier stage, which is responsible for the application of voltage or current pulses of proper intensity to the biological tissue, applied noninvasively via electrodes, placed on the skin surface or inside the muscular tissue, closer to the nervous fibers. The goals of this paper are to describe and discuss about the main power output designs usually employed in transcutaneous functional electrical stimulators as well as safety precautions taken to protect patients. Methods A systematic review investigated the circuits of papers published in IEEE Xplore and ScienceDirect databases from 2000 to 2016. The query terms were “((FES or Functional electric stimulator and (circuit or design” with 274 papers retrieved from IEEE Xplore and 29 from ScienceDirect. After the application of exclusion criteria the amount of papers decreased to 9 and 2 from IEEE Xplore and ScienceDirect, respectively. One paper was inserted in the results as a technological contribution to the field. Therefore, 12 papers presented power stage circuits suitable to stimulate great muscles. Discussion The retrieved results presented relevant circuits with different electronic strategies and circuit components. Some of them considered patient safety strategies or aimed to preserve muscle homeostasis such as biphasic current application, which prevents charge accumulation in stimulated tissues as well as circuits that dealt with electrical impedance variation to keep the electrode-tissue interface within an electrochemical safe regime. The investigation revealed a predominance of design strategies using operational amplifiers in power circuits, current outputs, and safety methods to reduce risks of electrical

Safety and shielding management for pulse power lab at IPR

International Nuclear Information System (INIS)

Upadhyay, Shweta; Faldu, Akash; Koshti, Rahul; Kumar, Rajesh

2016-01-01

Experiments in pulsed power lab works with very high voltage and high current regime for the nanosecond to microsecond time scale. This produces lot of electromagnetic noise, which can cause interference or malfunctioning of equipment. Laboratory Safety and protection are a very important aspect of science and engineering. Without it, practical performance could result in very serious injury, if not death. To reduce its effect electromagnetic shielding and grounding has to be enforced effectively. Pulse power lab deals with many safety issues like Radiation safety (shielding), High voltage safety, electrical and mechanical safety, etc. In this paper radiation all the safety aspects in pulse power lab is described. (author)

India's power program and its concern over environmental safety

International Nuclear Information System (INIS)

Prasad, G.E.; Mittra, J.

2001-01-01

India's need of electrical power is enormous and per capita consumption of power is to be increased at least by ten times to reach the level of world average. Thermal Power generation faces two fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India's self reliant, three stage, 'closed-fuel-cycle' nuclear power program is promising better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating necessary safety features in the design, operational safety through structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from nuclear power program. Based on latest technology, as available in case of nuclear power option, it is quite possible to meet high energy requirement with least impact on the environment.. (authors)

Power quality in power systems and electrical machines

CERN Document Server

Fuchs, Ewald

2015-01-01

The second edition of this must-have reference covers power quality issues in four parts, including new discussions related to renewable energy systems. The first part of the book provides background on causes, effects, standards, and measurements of power quality and harmonics. Once the basics are established the authors move on to harmonic modeling of power systems, including components and apparatus (electric machines). The final part of the book is devoted to power quality mitigation approaches and devices, and the fourth part extends the analysis to power quality solutions for renewable

Nuclear reactors. Use of the protection system for non-safety purposes (International Electrotechnical Commission Standard Publication 639:1979)

International Nuclear Information System (INIS)

Stefanik, J.

1996-01-01

This standard applies to the protection system of a nuclear reactor and, more especially, to all interconnections between a reactor protection system (as defined and explained in International Electrotechnical Commission Publication 231 A, first supplement to Publication 231, General Principles of Nuclear Reactor Instrumentation) and all other systems and equipment not part of the protection system, except: a) the physical connection between sensors of the protection system and the physical variables that they monitor, such as for example, thermo wells, moderating medium for neutron sensors, etc.; b) the electrical connection between the protection system and the reactor control rods or other safety mechanism; c) the electrical and pneumatic connections to the power distribution system (mains) and pneumatic supplies that supply power to the protection system. Although many clauses relate to all reactor protection systems, this standard applies mainly to protection systems in nuclear power reactors

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

Driving Control for Electric Power Assisted Wheelchair Based on Regenerative Brake

Science.gov (United States)

Seki, Hirokazu; Takahashi, Kazuki; Tadakuma, Susumu

This paper describes a novel safety driving control scheme for electric power assisted wheelchairs based on the regenerative braking system. “Electric power assisted wheelchair” which assists the driving force by electric motors is expected to be widely used as a mobility support system for elderly people and disabled people, however, the safe and secure driving performance especially on downhill roads must be further improved because electric power assisted wheelchairs have no braking devices. The proposed control system automatically switches the driving mode, from “assisting mode” to “braking mode”, based on the wheelchair's velocity and the declined angle and smoothly suppresses the wheelchair's acceleration based on variable duty ratio control in order to realize the safety driving and to improve the ride quality. Some experiments on the practical roads and subjective evaluation show the effectiveness of the proposed control system.

IR-360 nuclear power plant safety functions and component classification

International Nuclear Information System (INIS)

Yousefpour, F.; Shokri, F.; Soltani, H.

2010-01-01

The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

IR-360 nuclear power plant safety functions and component classification

Energy Technology Data Exchange (ETDEWEB)

Yousefpour, F., E-mail: fyousefpour@snira.co [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of); Shokri, F.; Soltani, H. [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of)

2010-10-15

The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

Safety standards of IAEA for management systems

International Nuclear Information System (INIS)

Vincze, P.

2005-01-01

IAEA has developed a new series of safety standards which are assigned for constitution of the conditions and which give the instruction for setting up the management systems that integrate the aims of safety, health, life environment and quality. The new standard shall replace IAEA 50-C-Q - Requirements for security of the quality for safety in nuclear power plants and other nuclear facilities as well as 14 related safety instructions mentioned in the Safety series No. 50-C/SG-Q (1996). When developing of this complex, integrated set of requirements for management systems, the IAEA requirements 50-C-Q (1996) were taken into consideration as well as the publications developed within the International organisation for standardization (ISO) ISO 9001:2000 and ISO14001: 1996. The experience of European Union member states during the development, implementation and improvement of the management systems were also taken into consideration

Safety Design for Smart Electric Vehicle Charging with Current and Multiplexing Control

Energy Technology Data Exchange (ETDEWEB)

Chung, Ching-Yen; Youn, Edward; Chynoweth, Joshua; Qiu, Charlie; Chu, Chi-Cheng; Gadh, Rajit

2013-10-21

As Electric Vehicles (EVs) increase, charging infrastructure becomes more important. When during the day there is a power shortage, the charging infrastructure should have the options to either shut off the power to the charging stations or to lower the power to the EVs in order to satisfy the needs of the grid. This paper proposes a design for a smart charging infrastructure capable of providing power to several EVs from one circuit by multiplexing power and providing charge control and safety systems to prevent electric shock. The safety design is implemented in different levels that include both the server and the smart charging stations. With this smart charging infrastructure, the shortage of energy in a local grid could be solved by our EV charging management system.

IEEE Std 382-1980: IEEE standard for qualification of safety-related valve actuators

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of all safety-related functions of power-driven valve actuators

Technique applied in electrical power distribution for Satellite Launch Vehicle

Directory of Open Access Journals (Sweden)

João Maurício Rosário

2010-09-01

Full Text Available The Satellite Launch Vehicle electrical network, which is currently being developed in Brazil, is sub-divided for analysis in the following parts: Service Electrical Network, Controlling Electrical Network, Safety Electrical Network and Telemetry Electrical Network. During the pre-launching and launching phases, these electrical networks are associated electrically and mechanically to the structure of the vehicle. In order to succeed in the integration of these electrical networks it is necessary to employ techniques of electrical power distribution, which are proper to Launch Vehicle systems. This work presents the most important techniques to be considered in the characterization of the electrical power supply applied to Launch Vehicle systems. Such techniques are primarily designed to allow the electrical networks, when submitted to the single-phase fault to ground, to be able of keeping the power supply to the loads.

A Concept Plane using electric distributed propulsion Evaluation of advanced power architecture

OpenAIRE

Ridel , M.; Paluch , B.; Doll , C.; Donjat , D.; Hermetz , J.; Guigon , A.; Schmollgruber , P.; Atinault , O.; Choy , P.; Le Tallec , P.; Dessornes , O.; Lefebvre , T.

2015-01-01

International audience; Starting from electrical distributed propulsion system concept, the ONERA’s engineers demonstrated the viability of an all electrical aircraft for a small business aircraft. This paper describes the advanced power architecture considering energy conversion and power distribution. The design of this advanced power architecture requires the multi-physic integration of different domains as flight performances, safety and environmental requirements (thermal, electric, elec...

ASSESSMENT OF THE ELECTRIC POWER QUALITY ON THE POLISH FISHING BOATS

Directory of Open Access Journals (Sweden)

Dariusz TARNAPOWICZ

2015-07-01

Full Text Available Power quality is an important problem for electrical systems. Electricity receivers should operate at nominal conditions. Each deviation from nominal values may cause the malfunction of electrical devices, decreasing their durability and per-manently damage the appliance. The importance of electric power quality for technical systems and individual electrical devices on fishing boats is fundamental. Utilization of equipment powered by electrical energy with a reduced quality resulting in economical losses and the treat to the screw's safety. Researches of the electrical energy's quality were carried out almost any type of fishing boats. This article presents the results of researches concerning the quality of electrical energy performed on a representative type of fishing boats. It shortly evaluates the results of tests and suggests solutions to improve the power quality parameters.

IAEA safety standards and approach to safety of advanced reactors

International Nuclear Information System (INIS)

Gasparini, M.

2004-01-01

The paper presents an overview of the IAEA safety standards including their overall structure and purpose. A detailed presentation is devoted to the general approach to safety that is embodied in the current safety requirements for the design of nuclear power plants. A safety approach is proposed for the future. This approach can be used as reference for a safe design, for safety assessment and for the preparation of the safety requirements. The method proposes an integration of deterministic and risk informed concepts in the general frame of a generalized concept of safety goals and defence in depth. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor including small and medium sized reactors with innovative safety features.(author)

System Description of the Electrical Power Supply System for the ATLAS Integral Test Loop

International Nuclear Information System (INIS)

Moon, S. K.; Park, J. K.; Kim, Y. S.; Song, C. H.; Baek, W. P.

2007-02-01

An integral effect test loop for pressurized water reactors (PWRs), the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), is constructed by Thermal-Hydraulics Safety Research Team in Korea Atomic Energy Research Institute (KAERI). The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400. This report describes the design and technical specifications of the electrical power supply system which supplies the electrical powers to core heater rods, other heaters, various pumps and other systems. The electrical power supply system had acquired the final approval on the operation from the Korea Electrical Safety Corporation. During performance tests for the operation and control, the electrical power supply system showed completely acceptable operation and control performance

IEEE Std 383-1974: IEEE standard for type test of Class IE electric cables, field splices, and connections for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class IE Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices. This guide does not cover cables for service within the reactor vessel

Radiological and nuclear safety- evolution, standards and similarity

International Nuclear Information System (INIS)

Soman, S.D.

1996-01-01

With the realisation of potential for severe health affects after the discovery of x-rays and radioactivity, the radiation protection aspect became focus of interest for medical users from the beginning of this century. With the activities of International Commission on Radiological Protection (ICRP), the standards evolved during all these years based on epidemiological data and radio-biological research. The current standards are the ICRP recommendations of 1990. Based on these, internationally harmonised standards for protection against ionising radiation and safety of radioactive sources were brought out by IAEA in 1994. The nuclear safety (implies safety of nuclear power plants) came into prominence when large scale units were designed and operated since mid 1950s. The philosophy in nuclear safety has evolved in past 2-3 decades taking into account the lessons learned from accidents, mainly Three Mile Island (1979) and Chernobyl-4 (1986). These current nuclear safety standards are incorporated in INSAG reports, particularly INSAG-3. This paper brings out salient features of these evolutions, current standards and similarity of radiation and nuclear safety standards in their present form. (author). 7 refs., 10 tabs

Radiation protection aspects in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Canadian approach to nuclear power safety

International Nuclear Information System (INIS)

Atchison, R.J.; Boyd, F.C.; Domaratzki, Z.

1983-01-01

The development of the Canadian nuclear power safety philosophy and practice is traced from its early roots at the Chalk River Nuclear Laboratories to the licensing of the current generation of power reactors. Basic to the philosophy is a recognition that the licensee is primarily responsible for achieving a high standard safety. As a consequence, regulatory requirements have emphasized numerical safety goals and objectives and minimized specific design or operating rules. In this article the Canadian licensing process is described with a discussion of some of the difficulties encountered. Examples of specific licensing considerations for each phase of a project are included

Safety of Nuclear Power Plants: Commissioning and Operation

International Nuclear Information System (INIS)

2011-01-01

The safety of a nuclear power plant is ensured by means of proper site selection, design, construction and commissioning, and the evaluation of these, followed by proper management, operation and maintenance of the plant. In a later phase, a proper transition to decommissioning is required. The organization and management of plant operations ensures that a high level of safety is achieved through the effective management and control of operational activities. This publication is a revision of the Safety Requirements publication Safety of Nuclear Power Plants: Operation, which was issued in 2000 as IAEA Safety Standards Series No. NS-R-2. The purpose of this revision was to restructure Safety Standards Series No. NS-R-2 in the light of new operating experience and new trends in the nuclear industry; to introduce new requirements that were not included in Safety Standards Series No. NS-R-2 on the operation of nuclear power plants; and to reflect current practices, new concepts and technical developments. This update also reflects feedback on the use of the standards, both from Member States and from the IAEA's safety related activities. The publication is presented in the new format for Safety Requirements publications. The present publication reflects the safety principles of the Fundamental Safety Principles. It has been harmonized with IAEA Safety Standards Series No. GS-R-3 on The Management System for Facilities and Activities. Guidance on the fulfilment of the safety requirements is provided in supporting Safety Guides. The terminology used in this publication is defined and explained in the IAEA Safety Glossary. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This

India's power programs and its concern over environmental safety

International Nuclear Information System (INIS)

Prasad, G.E.; Mittra, J.; Sarma, M.S.R.

2000-01-01

India's need for electrical power is enormous and per capita consumption of power is to be increased at least by 10 times to reach the level of the world average. Thermal power generation faces two-fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India 's self reliant, . three stage, 'closed-fuel-cycle' nuclear power program is promising a better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, the Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating' necessary safety features in the design, operational safety through a structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from the nuclear power program. Based on the latest technology, as available in case of the nuclear power option, it is quite possible to meet high energy requirements with least impact on the environment. (authors)

The next generation of power reactors - safety characteristics

International Nuclear Information System (INIS)

Modro, S.M.

1995-01-01

The next generation of commercial nuclear power reactors is characterized by a new approach to achieving reliability of their safety systems. In contrast to current generation reactors, these designs apply passive safety features that rely on gravity-driven transfer processes or stored energy, such as gas-pressurized accumulators or electric batteries. This paper discusses the passive safety system of the AP600 and Simplified Boiling Water Reactor (SBWR) designs

Nuclear power in competitive electricity markets

International Nuclear Information System (INIS)

2000-01-01

Economic deregulation in the power sector raises new challenges for the prospects of nuclear power. A key issue is to assess whether nuclear power can be competitive in a de-regulated electricity market. Other important considerations include safety, nuclear liability and insurance, the nuclear power infrastructure, and health and environmental protection. This study, conducted by a group of experts from twelve OECD Member countries and three international organisations, provides a review and analysis of these issues, as related to both existing and future nuclear power plants. It will be of particular interest to energy analysts, as well as to policy makers in the nuclear and government sectors. (author)

DS424: A Roadmap for the Implementation of the IAEA Safety Standards

International Nuclear Information System (INIS)

Yllera, Javier

2010-01-01

Many countries interested in developing nuclear power programmes for the first time need to have experience in using and regulating radioactive source materials. They need to have experience in building and operating large non-nuclear construction projects. Nuclear power has unique attributes and commitments associated with it that other industries do not. Although undertaken as a national endeavour with many national implications, building and operating a nuclear facility also has global implications (financial, political, safety, etc.). DG’s 2008 General Conference speech: “Every country has the right to introduce nuclear power, as well as the responsibility to do it right.”. The development of IAEA Safety Standards is an statutory function of the IAEA (article III of the IAEA Statute): “The Agency is authorized to establish or adopt… standards of safety for protection of health and minimization of danger to life and property…”. New guide (DS 424) constitutes a “Road-map” to apply the entire suite of IAEA Safety Standards progressively during the early phases of the implementation of a nuclear power programme. IAEA safety review missions based on internationally agreed safety standards are well established and are the best tools to build up confidence on the capacity of a country to develop nuclear energy in a safe way

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Report of the Task Group on Electrical Safety of Department of Energy facilities

Energy Technology Data Exchange (ETDEWEB)

None

1993-01-01

The Task Group on Electrical Safety at DOE Facilities (Task Group), which was formally established on October 27, 1992. The Task Group reviewed the electrical safety-related occurrence history of, and conducted field visits to, seven DOE sites chosen to represent a cross section of the Department`s electrical safety activities. The purpose of the field visits was to review, firsthand, electrical safety programs and practices and to gain greater insight to the root causes and corrective actions taken for recently reported incidents. The electrical safety environment of the DOE complex is extremely varied, ranging from common office and industrial electrical systems to large high-voltage power distribution systems (commercial transmission line systems). It includes high-voltage/high-power systems associated with research programs such as linear accelerators and experimental fusion confinement systems. Age, condition, and magnitude of the facilities also varies, with facilities dating from the Manhattan Project, during World War II, to the most modem complexes. The complex is populated by Federal (DOE and other agencies) and contractor employees engaged in a wide variety of occupations and activities in office, research and development, and industrial settings. The sites visited included all of these variations and are considered by the Task Group to offer a valid representation of the Department`s electrical safety issues. The sites visited were Oak Ridge National Laboratory (ORNL), Stanford Linear Accelerator Center (SLAC), Idaho National Engineering Laboratory (INEL), Nevada Test Site (NTS), Savannah River Site (SRS), Hanford Reservation (Hanford), and the Uranium Mill Tailings Remedial Action Project (UMTRA) located at Grand Junction, Colorado.

IEEE standard requirements for reliability analysis in the design and operation of safety systems for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1976-01-01

The purpose of this standard is to provide uniform, minimum acceptable requirements for the performance of reliability analyses for safety-related systems found in nuclear-power generating stations, but not to define the need for an analysis. The need for reliability analysis has been identified in other standards which expand the requirements of regulations (e.g., IEEE Std 379-1972 (ANSI N41.2-1972), ''Guide for the Application of the Single-Failure Criterion to Nuclear Power Generating Station Protection System,'' which describes the application of the single-failure criterion). IEEE Std 352-1975, ''Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems,'' provides guidance in the application and use of reliability techniques referred to in this standard

Improving the electromagnetic compatibility of track circuits with electric rolling stock of double power supply with induction traction motors and electrictraction network

Directory of Open Access Journals (Sweden)

N.G. Visin

2012-04-01

Full Text Available In this article the research results of many authors on the effect of current interference from the existing electric rolling stock with induction traction motors (ITM on the track circuits and the possibility of exceeding the train traffic safety standards are used. The new promising scheme of power circuit for electric locomotive of double power supply with an ITM applying the intermediary high-frequency transformer for reducing significantly the interference effects to SCB and communication devices is developed.

78 FR 4873 - Electrical Protective Equipment Standard and the Electric Power Generation, Transmission, and...

Science.gov (United States)

2013-01-23

... performing job duties. The training requirements of the Standard inform workers of the safety hazards of... this method, you must submit a copy of your comments and attachments to the OSHA Docket Office, Docket... Distribution Standard (Sec. 1910.269) Training Certification (Sec. 1910.269(a)(2)(vii)) This provision requires...

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Safety improvement of Paks nuclear power plant

International Nuclear Information System (INIS)

Vamos, G.

1999-01-01

Safety upgrading completed in the early nineties at the Paks NPP include: replacement of steam generator safety valves and control valves; reliability improvement of the electrical supply system; modification of protection logic; enhancement of the fire protection; construction of full scope Training Simulator. Design safety upgrading measures achieved in recent years were concerned with: relocation of steam generator emergency feed-water supply; emergency gas removal from the primary coolant system; hydrogen management in the containment; protection against sumps; preventing of emergency core cooling system tanks from refilling. Increasing seismic resistance, containment assessment, refurbishment of reactor protection system, improving reliability of emergency electrical supply, analysis of internal hazards are now being implemented. Safety upgrading measures which are being prepared include: bleed and feed procedures; reactor over-pressurisation protection in cold state; treatment of steam generator primary to secondary leak accidents. Operational safety improvements are dealing with safety culture, training measures and facilities; symptom based emergency operating procedures; in-service inspection; fire protection. The significance of international cooperation is emphasised in view of achieving nuclear safety standards recognised in EU

Instantaneous input electrical power measurements of HITU transducer

International Nuclear Information System (INIS)

Karaboece, B; Guelmez, Y; Rajagapol, S; Shaw, A

2011-01-01

HITU (High Intensity Theraupetic Ultrasound) transducers are widely used in therapeutic ultrasound in medicine. The output ultrasonic power of HITU transducer can be measured in number of methods described in IEC 61161 standard [1]. New IEC standards specifically for measurement of HITU equipment are under development. The ultrasound power radiated from a transducer is dependent on applied input electrical voltage and current and consequently power. But, up to now, no standardised method has been developed and adopted for the input electrical power measurements. Hence, a workpackage was carried out for the establishment of such method in the frequency range of 1 to 3 MHz as a part of EURAMET EMRP Era-net plus 'External Beam Cancer Therapy' project. Several current shunts were developed and evaluated. Current measurements were also realized with Philips current probe and preamplifier at NPL and Agilent current probe at UME. In this paper, a method for the measurement of instantaneous electrical power delivered to a reactive ultrasound transducer in the required frequency range is explored.

Instantaneous input electrical power measurements of HITU transducer

Energy Technology Data Exchange (ETDEWEB)

Karaboece, B; Guelmez, Y [Tuebitak Ulusal Metroloji Enstituesue (UME), P.K. 54 41470 Gebze-Kocaeli (Turkey); Rajagapol, S; Shaw, A, E-mail: baki.karaboce@ume.tubitak.gov.t [National Physical Laboratory (NPL), Hampton Road, Teddington TW11 0LW (United Kingdom)

2011-02-01

HITU (High Intensity Theraupetic Ultrasound) transducers are widely used in therapeutic ultrasound in medicine. The output ultrasonic power of HITU transducer can be measured in number of methods described in IEC 61161 standard [1]. New IEC standards specifically for measurement of HITU equipment are under development. The ultrasound power radiated from a transducer is dependent on applied input electrical voltage and current and consequently power. But, up to now, no standardised method has been developed and adopted for the input electrical power measurements. Hence, a workpackage was carried out for the establishment of such method in the frequency range of 1 to 3 MHz as a part of EURAMET EMRP Era-net plus 'External Beam Cancer Therapy' project. Several current shunts were developed and evaluated. Current measurements were also realized with Philips current probe and preamplifier at NPL and Agilent current probe at UME. In this paper, a method for the measurement of instantaneous electrical power delivered to a reactive ultrasound transducer in the required frequency range is explored.

The impact of safety standards updating for design purposes in nuclear power plants licensing

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2009-01-01

The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

Requirements for the support power systems of CANDU nuclear power plants

International Nuclear Information System (INIS)

1990-08-01

This Standard covers principal criteria and requirements for design, fabrication, installation, qualification, inspection, and documentation for assurance that support power will be available as required. The minimum requirements for support power are determined by the special safety systems and other safety-related systems that must function to ensure that the public health risk is acceptably low. Support power systems of a CANDU nuclear power plant include those parts of the electrical systems and instrument air systems that are necessary for the operation of safety-related systems

IAEA Sees Safety Commitment at Spain’s Almaraz Nuclear Power Plant, Areas for Enhancement

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts said the operator of Spain’s Almaraz Nuclear Power Plant demonstrated a commitment to the long-term safety of the plant and noted several good practices to share with the nuclear industry globally. The team also identified areas for further enhancement. The Operational Safety Review Team (OSART) today concluded an 18-day mission to Almaraz, whose two 1,050-MWe pressurized-water reactors started commercial operation in 1983 and 1984, respectively. Centrales Nucleares Almaraz-Trillo (CNAT) operates the plant, located about 200 km southwest of Madrid. OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing recommendations for improvement where appropriate. Nuclear power generates more than 21 per cent of electricity in Spain, whose seven operating power reactors all began operation in the 1980s.The mission made a number of recommendations to improve operational safety, including: • The plant should implement further actions related to management, staff and contractors to enforce standards and expectations related to industrial safety. • The plant should take measures to reinforce and implement standards to enhance the performance of reactivity manipulations in a deliberate and carefully-controlled manner. • The plant should improve the support, training and documented guidance for Severe Accident Management Guideline users in order to mitigate complex severe accident scenarios. The team provided a draft report of the mission to the plant’s management. The plant management and the Nuclear Safety Council (CSN), which is responsible for nuclear safety oversight in Spain, will have the opportunity to make factual comments on the draft. These will be reviewed by the IAEA and the final report will be submitted to the Government of Spain within three months. The plant management said it would address the areas

Progress of innovation of electrical power technology in FY2013

International Nuclear Information System (INIS)

Mayumi, Akihiko; Tanaka, Masanori; Yamaguchi, Hiroshi

2014-01-01

The following is the description of technical innovations at 12 companies including Tokyo Electric Power Company, Chubu Electric Power Company, and Japan Atomic Power Company. Tokyo Electric Power Company presented (1) the developments of a wet-type air decontaminating apparatus for inside/outside of power plant, (2) a robot to be used for field investigation at the Fukushima Daiichi nuclear power plant, (3) a visualization technology using laser for detection, and (4) removal of debris at the power plant. Chubu Electric Power Company presented application of a flap gate to the opening on exterior wall of building as a countermeasure against tsunami at the Hamaoka nuclear power plant. Hokuriku Electric Power Company presented a nuclear reactor operation training simulator for full-scope operation training for the Shika nuclear power station. Chugoku Electric Power Company presented their efforts in implementing a predictive monitoring system at the Shimane Nuclear Power Station. Shikoku Electric Power Company presented the installation of a weir with a flap gate to the interior of seawater pit as a countermeasure against tsunami. Japan Atomic Power Company presented an impact assessment method of fallout during transportation of materials caused by nuclear reactor accident, design and development of a square-type shielding container for radioactive wastes, a strength test on concrete materials for the safety design of Tsuruga Power Station Units 3 and 4, decommissioning of nuclear power plant, and research and development of the fast breeder reactor. (S.Y.)

Test to prove the resistance to incidents of components of electric and control systems in the safety containment of nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

The marginal program for proving the suitability of safety-relevant components of electric and control systems in the safety containment during a loss-of-coolant incident is described. Variant test conditions are established in the component-specific test program. Special attention has been paid to the representation of the course of pressure and temperature for the performance test of the valve room of the Nuclear Power Plant Philippsburg 2. (DG) [de

TOPEX electrical power system

Science.gov (United States)

Chetty, P. R. K.; Roufberg, Lew; Costogue, Ernest

1991-01-01

The TOPEX mission requirements which impact the power requirements and analyses are presented. A description of the electrical power system (EPS), including energy management and battery charging methods that were conceived and developed to meet the identified satellite requirements, is included. Analysis of the TOPEX EPS confirms that all of its electrical performance and reliability requirements have been met. The TOPEX EPS employs the flight-proven modular power system (MPS) which is part of the Multimission Modular Spacecraft and provides high reliability, abbreviated development effort and schedule, and low cost. An energy balance equation, unique to TOPEX, has been derived to confirm that the batteries will be completely recharged following each eclipse, under worst-case conditions. TOPEX uses three NASA Standard 50AH Ni-Cd batteries, each with 22 cells in series. The MPS contains battery charge control and protection based on measurements of battery currents, voltages, temperatures, and computed depth-of-discharge. In case of impending battery depletion, the MPS automatically implements load shedding.

76 FR 58101 - Electric Reliability Organization Interpretation of Transmission Operations Reliability Standard

Science.gov (United States)

2011-09-20

....C. Cir. 2009). \\4\\ Mandatory Reliability Standards for the Bulk-Power System, Order No. 693, FERC... for maintaining real and reactive power balance. \\14\\ Electric Reliability Organization Interpretation...; Order No. 753] Electric Reliability Organization Interpretation of Transmission Operations Reliability...

NB Power's public safety perspective

Energy Technology Data Exchange (ETDEWEB)

Sisk, P [New Brunswick Power, Fredericton, NB (Canada)

2009-07-01

New Brunswick Power Generation (NB Power) - Genco operates and maintains one of North America's most diverse generating systems. It consists of 15 hydro, coal, oil and diesel-powered generating stations and supplies approximately 75 per cent of the in-province load. It also exports energy to neighbouring New England, Quebec, Prince Edward Island, and Nova Scotia. This presentation provided some history regarding public safety issues at NB Power. The Mactaquac generating system was discussed with particular reference to its activities, challenges and control measures such as signage, audible alarms, visuals, security fencing, and coast guard navigation buoys. Several recommendations were presented, such as developing a tool to conduct risk assessment at all hydro stations; developing a public safety campaign; installing booms where required; standardizing signs; evaluating security risks; and conducting pre-spill inspections to remove the public from dangerous areas. figs.

Probabilist methods applied to electric source problems in nuclear safety

International Nuclear Information System (INIS)

Carnino, A.; Llory, M.

1979-01-01

Nuclear Safety has frequently been asked to quantify safety margins and evaluate the hazard. In order to do so, the probabilist methods have proved to be the most promising. Without completely replacing determinist safety, they are now commonly used at the reliability or availability stages of systems as well as for determining the likely accidental sequences. In this paper an application linked to the problem of electric sources is described, whilst at the same time indicating the methods used. This is the calculation of the probable loss of all the electric sources of a pressurized water nuclear power station, the evaluation of the reliability of diesels by event trees of failures and the determination of accidental sequences which could be brought about by the 'total electric source loss' initiator and affect the installation or the environment [fr

Quality and Safety Assurance - Priority Task at Nuclear Power Projects Implementation

International Nuclear Information System (INIS)

Nenkova, B.; Manchev, B.; Tomov, E.

2010-01-01

Quality and safety assurance at implementation of nuclear power engineering projects is important and difficult task for realization. Many problems arise during this process, when many companies from different countries participate, with various kinds of activities and services provided. The scope of activities necessary for quality and safety assurance is therefore quite expanded and diverse. In order to increase the safety and reliability of Kozloduy NPP Plc (KNPP) Units 5 and 6, as well as to bring the units in conformity with the newest international requirements for quality and safety in the field of nuclear energy, a program for their modernization on the basis of different technical studies and assessments was implemented. The Units 5 and 6 Modernization Program of Kozloduy Nuclear Power Plant was composed of 212 modifications aimed to improve the safety, operability, and reliability of the Units. The Program was realized by stages during yearly planned outages since year 2002 to 2007, without additional outages. A major Program Objective was to extend the Units Life Time in at least 15 Years, under a continuous, safe, and reliable operation. The Modernization Program of Units 5 and 6 of the Bulgarian Nuclear Power Plant in Kozloduy was the first and for the time being the only one in the world, program in the field of nuclear power engineering, by which the full scope of recommendations for improvement of the Kozloduy NPP units was applied. The main goal of the National Electric Company, which is the Employer for the construction of new nuclear facility in Bulgaria, is after completion of all activities regarding construction of Belene NPP the plant to meet or exceed the requirements of the respective national and international quality and safety codes and standards, as well as the IAEA guidelines, as they are established. The objective of this report is to describe different aspects of the quality assurance according to the requirements of quality and

Advanced design nuclear power plants: Competitive, economical electricity. An analysis of the cost of electricity from coal, gas and nuclear power plants

International Nuclear Information System (INIS)

1992-06-01

This report presents an updated analysis of the projected cost of electricity from new baseload power plants beginning operation around the year 2000. Included in the study are: (1) advanced-design, standardized nuclear power plants; (2) low emissions coal-fired power plants; (3) gasified coal-fired power plants; and (4) natural gas-fired power plants. This analysis shows that electricity from advanced-design, standardized nuclear power plants will be economically competitive with all other baseload electric generating system alternatives. This does not mean that any one source of electric power is always preferable to another. Rather, what this analysis indicates is that, as utilities and others begin planning for future baseload power plants, advanced-design nuclear plants should be considered an economically viable option to be included in their detailed studies of alternatives. Even with aggressive and successful conservation, efficiency and demand-side management programs, some new baseload electric supply will be needed during the 1990s and into the future. The baseload generating plants required in the 1990s are currently being designed and constructed. For those required shortly after 2000, the planning and alternatives assessment process must start now. It takes up to ten years to plan, design, license and construct a new coal-fired or nuclear fueled baseload electric generating plant and about six years for a natural gas-fired plant. This study indicates that for 600-megawatt blocks of capacity, advanced-design nuclear plants could supply electricity at an average of 4.5 cents per kilowatt-hour versus 4.8 cents per kilowatt-hour for an advanced pulverized-coal plant, 5.0 cents per kilowatt-hour for a gasified-coal combined cycle plant, and 4.3 cents per kilowatt-hour for a gas-fired combined cycle combustion turbine plant

Small nuclear power reactor emergency electric power supply system reliability comparative analysis

International Nuclear Information System (INIS)

Bonfietti, Gerson

2003-01-01

This work presents an analysis of the reliability of the emergency power supply system, of a small size nuclear power reactor. Three different configurations are investigated and their reliability analyzed. The fault tree method is used as the main tool of analysis. The work includes a bibliographic review of emergency diesel generator reliability and a discussion of the design requirements applicable to emergency electrical systems. The influence of common cause failure influences is considered using the beta factor model. The operator action is considered using human failure probabilities. A parametric analysis shows the strong dependence between the reactor safety and the loss of offsite electric power supply. It is also shown that common cause failures can be a major contributor to the system reliability. (author)

Safety-evaluation report related to the license renewal and power increase for the National Bureau of Standards Reactor (Docket No. 50-184)

International Nuclear Information System (INIS)

1983-09-01

This Safety Evaluation Report for the application filed by the National Bureau of Standards (NBS) for an increase in power from 10 MWt to 20 MWt and for a renewal of the Operating License TR-5 to continue to operate the test reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Gaithersburg, Maryland, on the site of the National Bureau of Standards, which is a bureau of the Department of Commerce. The staff concludes that the NBS reactor can operate at the 20 MWt power level without endangering the health and safety of the public

Instrumentation and control systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It supplements Safety Standards Series No. NS-R-1: Safety of Nuclear Power Plants: Design (the Requirements for Design), which establishes the design requirements for ensuring the safety of nuclear power plants. This Safety Guide describes how the requirements should be met for instrumentation and control (I and C) systems important to safety. This publication is a revision and combination of two previous Safety Guides: Safety Series Nos 50-SG-D3 and 50-SG-D8, which are superseded by this new Safety Guide. The revision takes account of developments in I and C systems important to safety since the earlier Safety Guides were published in 1980 and 1984, respectively. The objective of this Safety Guide is to provide guidance on the design of I and C systems important to safety in nuclear power plants, including all I and C components, from the sensors allocated to the mechanical systems to the actuated equipment, operator interfaces and auxiliary equipment. This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety. It expands on paragraphs of Ref in the area of I and C systems important to safety. This publication is intended for use primarily by designers of nuclear power plants and also by owners and/or operators and regulators of nuclear power plants. This Safety Guide provides general guidance on I and C systems important to safety which is broadly applicable to many nuclear power plants. More detailed requirements and limitations for safe operation specific to a particular plant type should be established as part of the design process. The present guidance is focused on the design principles for systems important to safety that warrant particular attention, and should be applied to both the design of new I and C systems and the modernization of existing systems. Guidance is provided on how design

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Safety goals for commercial nuclear power plants

International Nuclear Information System (INIS)

Roe, J.W.

1988-01-01

In its official policy statement on safety goals for the operation of nuclear power plants, the Nuclear Regulatory Commission (NRC) set two qualitative goals, supported by two quantitative objectives. These goals are that (1) individual members of the public should be provided a level of protection from the consequences of nuclear power plant operation such that individuals bear no significant additional risk to life and health; and (2) societal risks to life and health from nuclear power plant operation should be comparable to or less than the risks of generating electricity by viable competing technologies and should not be a significant addition to other societal risks. As an alternative, this study proposes four quantitative safety goals for nuclear power plants. It begins with an analysis of the NRC's safety-goal development process, a key portion of which was devoted to delineating criteria for evaluating goal-development methods. Based on this analysis, recommendations for revision of the NRC's basic benchmarks for goal development are proposed. Using the revised criteria, NRC safety goals are evaluated, and the alternative safety goals are proposed. To further support these recommendations, both the NRC's goals and the proposed goals are compared with the results of three major probabilistic risk assessment studies. Finally, the potential impact of these recommendations on nuclear safety is described

IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

Review on signal-by-wire and power-by-wire actuation for more electric aircraft

Directory of Open Access Journals (Sweden)

Jean-Charles MARÉ

2017-06-01

Full Text Available The huge and rapid progress in electric drives offers new opportunities to improve the performances of aircraft at all levels: fuel burn, environmental footprint, safety, integration and production, serviceability, and maintainability. Actuation for safety-critical applications like flight-controls, landing gears, and even engines is one of the major consumers of non-propulsive power. Conventional actuation with centralized hydraulic power generation and distribution and control of power by throttling has been well established for decades, but offers a limited potential of evolution. In this context, electric drives become more and more attractive to remove the natural drawbacks of conventional actuation and to offer new opportunities for improving performance. This paper takes the stock, at both the signal and power levels, of the evolution of actuation for safety-critical applications in aerospace. It focuses on the recent advances and the remaining challenges to be taken toward full electrical actuation for commercial and military aircraft, helicopters, and launchers. It logically starts by emphasizing the specificity of safety-critical actuation for aerospace. The following section addresses in details the evolution of aerospace actuation from mechanically-signaled and hydraulically-supplied to all electric, with special emphasis on research and development programs and on solutions entered into service. Finally, the last section reviews the challenges to be taken to generalize the use of all-electric actuators for future aircraft programs.

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

Dictionary of electrical engineering. Power engineering, automation technology, measurement and control technology, mechatronics. English - German; Fachwoerterbuch Elektrotechnik. Energietechnik, Automatisierungstechnik, Mess-, Steuer- und Regelungstechnik, Mechatronik. Englisch - Deutsch

Energy Technology Data Exchange (ETDEWEB)

Heckler, H.

2007-07-01

The foreign-language vocabulary taught at school usually does not cover terms needed during professional life in electrical engineering. This comprehensive dictionary contains more than 60,000 electrotechnical and engineering terms - used in textbooks, manuals, data sheets, whitepapers and international standards. British English and American English spelling differences are identified. Terms used in IEC standards of the International Electrotechnical Commission are marked, allowing the reader to have easy access to the multilingual glossary of the IEC. This book contains the in-house dictionaries of the internationally operating companies Festo, KEB, Phoenix Contact, and Rittal. Topics: - Basic of electrical engineering, - Electrical power engineering, - Mechatronics, - Electrical drive engineering, - Electrical connection technology, - Automation technology, - Safety-related technology, - Information technology, - Measurement and control technology, - Explosion protection - Power plant technology, - Lightning and overvoltage protection. (orig.)

Safety issues relating to the design of fusion power facilities

International Nuclear Information System (INIS)

Stasko, R.R.; Wong, K.Y.; Russell, S.B.

1986-06-01

In order to make fusion power a viable future source of energy, it will be necessary to ensure that the cost of power for fusion electric generation is competitive with advanced fission concepts. In addition, fusion power will have to live up to its original promise of being a more radiologically benign technology than fission, and be able to demonstrate excellent operational safety performance. These two requirements are interrelated, since the selection of an appropriate safety philosophy early in the design phase could greatly reduce or eliminate the capital costs of elaborate safety related and protective sytems. This paper will briefly overview a few of the key safety issues presently recognized as critical to the ultimate achievement of licensable, environmentally safe and socially acceptable fusion power facilities. 12 refs

New quantitative safety standards: different techniques, different results?

International Nuclear Information System (INIS)

Rouvroye, J.L.; Brombacher, A.C.

1999-01-01

Safety Instrumented Systems (SIS) are used in the process industry to perform safety functions. Many factors can influence the safety of a SIS like system layout, diagnostics, testing and repair. In standards like the German DIN no quantitative analysis is demanded (DIN V 19250 Grundlegende Sicherheitsbetrachtungen fuer MSR-Schutzeinrichtungen, Berlin, 1994; DIN/VDE 0801 Grundsaetze fuer Rechner in Systemen mit Sicherheitsaufgaben, Berlin, 1990). The analysis according to these standards is based on expert opinion and qualitative analysis techniques. New standards like the IEC 61508 (IEC 61508 Functional safety of electrical/electronic/programmable electronic safety-related systems, IEC, Geneve, 1997) and the ISA-S84.01 (ISA-S84.01.1996 Application of Safety Instrumented Systems for the Process Industries, Instrument Society of America, Research Triangle Park, 1996) require quantitative risk analysis but do not prescribe how to perform the analysis. Earlier publications of the authors (Rouvroye et al., Uncertainty in safety, new techniques for the assessment and optimisation of safety in process industry, D W. Pyatt (ed), SERA-Vol. 4, Safety engineering and risk analysis, ASME, New York 1995; Rouvroye et al., A comparison study of qualitative and quantitative analysis techniques for the assessment of safety in industry, P.C. Cacciabue, I.A. Papazoglou (eds), Proceedings PSAM III conference, Crete, Greece, June 1996) have shown that different analysis techniques cover different aspects of system behaviour. This paper shows by means of a case study, that different (quantitative) analysis techniques may lead to different results. The consequence is that the application of the standards to practical systems will not always lead to unambiguous results. The authors therefore propose a technique to overcome this major disadvantage

Inductively coupled power systems for electric vehicles: a fourth dimension

Energy Technology Data Exchange (ETDEWEB)

Bolger, J G

1980-09-01

There are three traditional methods of supplying energy to electric vehicles. The inductively coupled roadway power system is a fourth method that adds important new dimensions to electric-vehicle capabilities. It efficiently transfers power to moving vehicles without physical contact, freeing the electric vehicle from most of the applicational constraints imposed by the other three methods. The single power conductor in the roadway carries several hundred amperes of alternating current. The current causes a weak magnetic flux to circulate through the air above it when a vehicle's power pickup is not present. When a vehicle's pickup is suported over the inductor, a more intense flux circulates through the steel cores in the road and in the pickup. Applications, electrical safety, and present status of the technology are discussed in the paper presented at the St. Louis EXPO '80.

International standard for the charging of electric vehicles; Internationaler Standard fuer das Laden von Elektrofahrzeugen - Schlussbericht

Energy Technology Data Exchange (ETDEWEB)

Mathoy, A.

2001-12-15

This final report for the Swiss Federal Office of Energy (SFOE) reports on the situation regarding the standardisation of battery charging systems for electric vehicles. The advantages of an international standard both for users and manufacturers of electrically-powered vehicles are discussed. The work done in the IEC and CENELEC technical committees is reviewed. Developments achieved since 1999 are reviewed and further developments and work to be done are examined. The most important points in the IEC standard 61851 are looked at and various connector interfaces are described. Direct and inductive charging systems according to IEC 61980 are examined and the special situation in Italy, where power available in homes for the charging of electrical vehicles is more limited, is reviewed.

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

International Nuclear Information System (INIS)

Wittmann, R.

1998-01-01

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

Progress of technological innovation on electric power in FY2014

International Nuclear Information System (INIS)

Nishikawa, Yoshikazu; Fujii, Yutaka; Sasagawa, Toshiro

2015-01-01

This paper overviews the technological development in FY2014 at Tokyo Electric Power Company, Chubu Electric Power Company, Hokuriku Electric Power Company, Shikoku Electric Power Company, and Electric Power Development Company. In this overview, further breakdown was made for the following departments of each company: nuclear power generation, thermal power generation, hydraulic power generation, power transmission, power distribution, transformation, research and development and technological development, and information and communication. In addition, this paper outlines the achievement of technological development at Japan Atomic Power Company, such as the technological development related to the existing power station, development of new technology, and the development of future reactor. Fukushima Daiichi Nuclear Power Station has developed an investigative system using a high altitude survey robot and a movable monitoring system. Hamaoka Nuclear Power Station examined the feasibility of state diagnostic technique based on multi-point analysis, and studied stress corrosion cracking at the newly established Nuclear Safety Research Laboratory. Shika Nuclear Power Station (Unit 1) applied a pipe stress improvement process by means of high frequency induction heating as a stress corrosion cracking countermeasure. Ikata Nuclear Power Station newly adopted high degree cross-linking cation resin, and high cracking strength anion resin as the primary resins. Oma Nuclear Power Station worked on the all reactor core utilization technology of MOX fuel. (A.O.)

Overview of electric power industry of main countries in the world

International Nuclear Information System (INIS)

2013-01-01

The electric power supply system, power producer, regulation system, electricity liberalization, power demand and supply, electricity rate, development of electric power sources, nuclear power generation and renewable energy of six countries such as USA, England, German, France, Russia and China are reported. On USA, 3,754 x 10 9 kWh of total electric energy, 104 of nuclear reactors are running and giving careful consideration to safety of the plant. Shale gas production is increasing, and new technology of electric car, smart grid and demand response is developing. On England, 368 x 10 9 kWh of total electric energy, which consisted of 70.4% thermal power, 18.8% nuclear power and 10.8% renewable energy, 18 nuclear reactors are running, but almost nuclear power plants will be closed until 2023. Biomass and wind power have been developed. On German, 609 x 10 9 kWh of total electric energy, 9 nuclear reactors are running but closed till 2022, the renewable energy such as wind power and photovoltaic is introduced. On France, 542 x 10 9 kWh total electric energy, which consisted of 9% hydroelectricity, 9% thermal power, 78% nuclear power and 4% renewable energy. The renewable energy plan is formulated. On Russia, 1,052 x 10 9 kWh total electric energy consisted of 67.8% thermal power, 15.7% hydroelectricity and 16.4% nuclear power, 32 nuclear power plants are running and 9 nuclear reactors building. On China, 4,693 x 10 9 kWh power consumption, 6 nuclear power plants are running to generate 1.85% electric energy, the objects of nuclear power generation and renewable energy were announced. (S.Y.)

The electric power engineering handbook electric power transformer engineering

CERN Document Server

Harlow, James H

2012-01-01

Electric Power Transformer Engineering, Third Edition expounds the latest information and developments to engineers who are familiar with basic principles and applications, perhaps including a hands-on working knowledge of power transformers. Targeting all from the merely curious to seasoned professionals and acknowledged experts, its content is structured to enable readers to easily access essential material in order to appreciate the many facets of an electric power transformer.Topically structured in three parts, the book: * Illustrates for electrical engineers the relevant theories and pri

The Canadian approach to nuclear power safety

International Nuclear Information System (INIS)

Atchison, R.J.; Boyd, F.C.; Domaratski, Z.

1983-07-01

The development of the Canadian nuclear power safety philosophy and practice is traced from its early roots at the Chalk River Nuclear Laboratory to the licensing of the current generation of power reactors. Basic to the philosophy is a recognition that the primary responsibility for achieving a high standard of safety resides with the licensee. As a consequence, regulatory requirements have emphasized numerical safety goals and objectives and minimized specific design or operating rules. The Canadian licensing process is described along with a discussion of some of the difficulties encountered. Examples of specific licensing considerations for each phase of a project are included

Nuclear power plants - Instrumentation and control systems important for safety - Classification (International Electrotechnical Commission Standard Publication 1226:1993)

International Nuclear Information System (INIS)

Stefanik, J.

1996-01-01

This international standard established a method of classification of the information and command functions for nuclear power plants, and the I and C and equipment that provide those functions, into categories that designate the importance for safety of the functions, and the associated systems and equipment. The resulting classification then determines relevant design criteria. The design criteria are the measures of quality by which the adequacy of each functions, and the associated systems and equipment in relation to its importance to plant safety is ensured. In this standard, the criteria are those of functionality, reliability, performance, environmental durability and quality assurance. This standard is applicable to all the information and command functions, and the instrumentation and control systems and equipment that provide those functions. The functions, systems and equipment under consideration provide automated protection, closed or open loop control, and information to the operating staff. They keep the NPP conditions inside the safe operating envelope and provide automatic actions, or enable manual actions, that mitigate accidents or prevent or minimize radioactive releases to the site or wider environment. The functions, and the associated systems and equipment that fulfill these roles safeguard the health and safety of the NPP operators and the public. This standard complements, and does not replace or supersede, the Safety Guides and Codes of Practice published by the International Atomic Energy Agency

IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

International Nuclear Information System (INIS)

2012-01-01

Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

Innovations in techniques of electric power in 2008

International Nuclear Information System (INIS)

Ohfusa, Takahiro; Endo, Yukio; Ino, Hiroyuki

2009-01-01

Tokyo Electric Power Company (TEPCO), Kansai Electric Power Co., Inc., Tohoku Electric Power and other nine companies reported the results of innovations in techniques of electric power in 2008, Japan. J-Power started construction of the Ohma Nuclear Power Plant (power generating capacity: 1,383 MW, ABWR) in Ohma Town, Aomori prefecture, Japan, in May 2008. TEPCO developed the low vibration control valve and carried out the model experiments using air as fluid and the simulation by computational fluid dynamics. Mach number distribution (ε L =0.068) at the valve showed change of the supersonic jet flow as time advanced and a periodic pressure change on the valve and valve seat. Japan Atomic Power Company reported development of techniques for the established nuclear power station such as control of pipe thinning of the secondary system of PWR by insertion of oxygen at Tsuruga Power Station Unit 2, risk evaluation, the effects of increase of generating power on aging deterioration, and development of heat protective clothing. Researched are a power generation plant of small-and-medium-size reactors which took in reforming technology using the location to a narrow site, funds by stakeholders and the idea of future 'fast breeder reactor system', sodium-cooled loop type reactor, which uses TRU as fuel. The accumulator tank of new type safety system for Tsuruga Power Station Unit 3 and 4 is designed and tested. Decommissioning process of Tokai Power Plant and recycling of shielding materials, blocks and concrete powder are stated. (S.Y.)

NUSS safety standards: A critical assessment

International Nuclear Information System (INIS)

Minogue, R.B.

1985-01-01

The NUSS safety standards are based on systematic review of safety criteria of many countries in a process carefully defined to assure completeness of coverage. They represent an international consensus of accepted safety principles and practices for regulation and for the design, construction, and operation of nuclear power plants. They are a codification of principles and practices already in use by some Member States. Thus, they are not standards which describe methodologies at their present state of evolution as a result of more recent experience and improvements in technological understanding. The NUSS standards assume an underlying body of national standards and a defined technological base. Detailed design and industrial practices vary between countries and the implementation of basic safety standards within countries has taken approaches that conform with national industrial practices. Thus, application of the NUSS standards requires reconciliation with the standards of the country where the reactor will be built as well as with the country from which procurement takes place. Experience in making that reconciliation will undoubtedly suggest areas of needed improvement. After the TMI accident a reassessment of the NUSS programme was made and it was concluded that, given the information at that time and the then level of technology, the basic approach was sound; the NUSS programme should be continued to completion, and the standards should be brought into use. It was also recognized, however, that in areas such as probabilistic risk assessment, human factors methodology, and consideration of detailed accident sequences, more advanced technology was emerging. As these technologies develop, and become more amenable to practical application, it is anticipated that the NUSS standards will need revision. Ideally those future revisions will also flow from experience in their use

Defining a standard metric for electricity savings

International Nuclear Information System (INIS)

Koomey, Jonathan; Akbari, Hashem; Blumstein, Carl; Brown, Marilyn; Brown, Richard; Calwell, Chris; Carter, Sheryl; Cavanagh, Ralph; Chang, Audrey; Claridge, David; Craig, Paul; Diamond, Rick; Eto, Joseph H; Fulkerson, William; Gadgil, Ashok; Geller, Howard; Goldemberg, Jose; Goldman, Chuck; Goldstein, David B; Greenberg, Steve

2010-01-01

The growing investment by governments and electric utilities in energy efficiency programs highlights the need for simple tools to help assess and explain the size of the potential resource. One technique that is commonly used in this effort is to characterize electricity savings in terms of avoided power plants, because it is easier for people to visualize a power plant than it is to understand an abstraction such as billions of kilowatt-hours. Unfortunately, there is no standardization around the characteristics of such power plants. In this letter we define parameters for a standard avoided power plant that have physical meaning and intuitive plausibility, for use in back-of-the-envelope calculations. For the prototypical plant this article settles on a 500 MW existing coal plant operating at a 70% capacity factor with 7% T and D losses. Displacing such a plant for one year would save 3 billion kWh/year at the meter and reduce emissions by 3 million metric tons of CO 2 per year. The proposed name for this metric is the Rosenfeld, in keeping with the tradition among scientists of naming units in honor of the person most responsible for the discovery and widespread adoption of the underlying scientific principle in question-Dr Arthur H Rosenfeld.

Defining a standard metric for electricity savings

Energy Technology Data Exchange (ETDEWEB)

Koomey, Jonathan [Lawrence Berkeley National Laboratory and Stanford University, PO Box 20313, Oakland, CA 94620-0313 (United States); Akbari, Hashem; Blumstein, Carl; Brown, Marilyn; Brown, Richard; Calwell, Chris; Carter, Sheryl; Cavanagh, Ralph; Chang, Audrey; Claridge, David; Craig, Paul; Diamond, Rick; Eto, Joseph H; Fulkerson, William; Gadgil, Ashok; Geller, Howard; Goldemberg, Jose; Goldman, Chuck; Goldstein, David B; Greenberg, Steve, E-mail: JGKoomey@stanford.ed

2010-01-15

The growing investment by governments and electric utilities in energy efficiency programs highlights the need for simple tools to help assess and explain the size of the potential resource. One technique that is commonly used in this effort is to characterize electricity savings in terms of avoided power plants, because it is easier for people to visualize a power plant than it is to understand an abstraction such as billions of kilowatt-hours. Unfortunately, there is no standardization around the characteristics of such power plants. In this letter we define parameters for a standard avoided power plant that have physical meaning and intuitive plausibility, for use in back-of-the-envelope calculations. For the prototypical plant this article settles on a 500 MW existing coal plant operating at a 70% capacity factor with 7% T and D losses. Displacing such a plant for one year would save 3 billion kWh/year at the meter and reduce emissions by 3 million metric tons of CO{sub 2} per year. The proposed name for this metric is the Rosenfeld, in keeping with the tradition among scientists of naming units in honor of the person most responsible for the discovery and widespread adoption of the underlying scientific principle in question-Dr Arthur H Rosenfeld.

Defining a Standard Metric for Electricity Savings

Energy Technology Data Exchange (ETDEWEB)

Brown, Marilyn; Akbari, Hashem; Blumstein, Carl; Koomey, Jonathan; Brown, Richard; Calwell, Chris; Carter, Sheryl; Cavanagh, Ralph; Chang, Audrey; Claridge, David; Craig, Paul; Diamond, Rick; Eto, Joseph H.; Fulkerson, William; Gadgil, Ashok; Geller, Howard; Goldemberg, Jose; Goldman, Chuck; Goldstein, David B.; Greenberg, Steve; Hafemeister, David; Harris, Jeff; Harvey, Hal; Heitz, Eric; Hirst, Eric; Hummel, Holmes; Kammen, Dan; Kelly, Henry; Laitner, Skip; Levine, Mark; Lovins, Amory; Masters, Gil; McMahon, James E.; Meier, Alan; Messenger, Michael; Millhone, John; Mills, Evan; Nadel, Steve; Nordman, Bruce; Price, Lynn; Romm, Joe; Ross, Marc; Rufo, Michael; Sathaye, Jayant; Schipper, Lee; Schneider, Stephen H; Sweeney, James L; Verdict, Malcolm; Vorsatz, Diana; Wang, Devra; Weinberg, Carl; Wilk, Richard; Wilson, John; Worrell, Ernst

2009-03-01

The growing investment by governments and electric utilities in energy efficiency programs highlights the need for simple tools to help assess and explain the size of the potential resource. One technique that is commonly used in this effort is to characterize electricity savings in terms of avoided power plants, because it is easier for people to visualize a power plant than it is to understand an abstraction such as billions of kilowatt-hours. Unfortunately, there is no standardization around the characteristics of such power plants. In this letter we define parameters for a standard avoided power plant that have physical meaning and intuitive plausibility, for use in back-of-the-envelope calculations. For the prototypical plant this article settles on a 500 MW existing coal plant operating at a 70percent capacity factor with 7percent T&D losses. Displacing such a plant for one year would save 3 billion kW h per year at the meter and reduce emissions by 3 million metric tons of CO2 per year. The proposed name for this metric is the Rosenfeld, in keeping with the tradition among scientists of naming units in honor of the person most responsible for the discovery and widespread adoption of the underlying scientific principle in question--Dr. Arthur H. Rosenfeld.

Ship Power System Analysis Based on Safety Aspects

Directory of Open Access Journals (Sweden)

Urbaha Margarita

2017-08-01

Full Text Available This article analyses the reasons for the reduction of insulating resistance, processes influencing them and isolation diagnostic methods. It provides a short description of electrical safety situation on ships with isolated neutral electrical power systems. It also covers the methods of protecting personnel from electric shock or preventing ignition or arching damage at the fault location with the help of fault current compensation. Principal fault current compensation circuit diagrams are analysed by using the minimum value and time of transient fault current as criteria.

Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2. Docket Nos. 50-387 and 50-388, Pennsylvania Power and Light Company, Allegheny Electric Cooperative, Inc

International Nuclear Information System (INIS)

1982-07-01

Information is presented concerning site characteristics; design criteria for systems and components; reactor thermal and hydraulic characteristics; reactor coolant pressure boundary; engineered safety features; instrumentation and control; electrical power systems; auxiliary systems; conduct of operations; quality assurance; and TMI-2 requirements

Method of electric powertrain matching for battery-powered electric cars

Science.gov (United States)

Ning, Guobao; Xiong, Lu; Zhang, Lijun; Yu, Zhuoping

2013-05-01

The current match method of electric powertrain still makes use of longitudinal dynamics, which can't realize maximum capacity for on-board energy storage unit and can't reach lowest equivalent fuel consumption as well. Another match method focuses on improving available space considering reasonable layout of vehicle to enlarge rated energy capacity for on-board energy storage unit, which can keep the longitudinal dynamics performance almost unchanged but can't reach lowest fuel consumption. Considering the characteristics of driving motor, method of electric powertrain matching utilizing conventional longitudinal dynamics for driving system and cut-and-try method for energy storage system is proposed for passenger cars converted from traditional ones. Through combining the utilization of vehicle space which contributes to the on-board energy amount, vehicle longitudinal performance requirements, vehicle equivalent fuel consumption level, passive safety requirements and maximum driving range requirement together, a comprehensive optimal match method of electric powertrain for battery-powered electric vehicle is raised. In simulation, the vehicle model and match method is built in Matlab/simulink, and the Environmental Protection Agency (EPA) Urban Dynamometer Driving Schedule (UDDS) is chosen as a test condition. The simulation results show that 2.62% of regenerative energy and 2% of energy storage efficiency are increased relative to the traditional method. The research conclusions provide theoretical and practical solutions for electric powertrain matching for modern battery-powered electric vehicles especially for those converted from traditional ones, and further enhance dynamics of electric vehicles.

SAFETY ALERT: Electrical insulation defect on safety helmets

CERN Multimedia

HSE Unit

2013-01-01

Contrarily to the information provided until 31 May 2013, some “Euro Protection” safety helmets do not respect any of the requirements for electrical insulation.   This alert concerns the safety helmets identified under the following SCEM numbers: 50.43.30.050.4 white 50.43.30.060.2 yellow 50.43.30.070.0 blue This amounts up to several hundreds of helmets on the CERN site. People who need to wear an electrically insulated safety helmet for their activities, must from now on acquire a duly insulated item to be found on the CERN store under the following SCEM numbers: 50.43.30.210.6: Petzl Vertex ST Helmet (without vent) 50.43.30.300.1: IDRA Helmet with a visor for electrical work As for the people who do not need to wear an electrically insulated helmet for their activities, they can continue working with the aforementioned helmets. For your information, please take note of the maximum use limit of each helmet: “Euro Protection” Safety Helme...

The nuclear safety standards of IAEA (NUSS)

International Nuclear Information System (INIS)

Andres, H.

1980-01-01

The lecture will give an overview of the Agency's Safety Standards for Nuclear Power Plants: its range and its current state of development. The general contents of the documents will be presented, and the procedures used for their development will be briefly described. (orig.)

HIL Simulation of Power Electronics and Electric Drives for Automotive Applications

OpenAIRE

Frank Puschmann; Axel Kiffe; Thomas Schulte

2012-01-01

Hardware-in-the-loop simulation is today a standard method for testing electronic equipment in the automotive industry. Since electric drives and power electronic devices are more and more important in automotive applications, these kinds of systems have to be integrated into the hardware-in-the-loop simulation. Power converters and electric drives are used in many different applications in vehicles today (hybrid electric or electric powertrain, electric steering systems, DC-DC converters, et...

Topics to be covered in safety analysis reports for nuclear power plants with pressurized water reactors or boiling water reactors in the F.R.G

International Nuclear Information System (INIS)

Kohler, H.A.G.

1977-01-01

This manual aims at defining the standards to be used in Safety Analysis Reports for Nuclear Power Plants with Pressurized Water Reactors or Boiling Water Reactors in the Federal Republic of Germany. The topics to be covered are: Information about the site (geographic situation, settlement, industrial and military facilities, transport and communications, meteorological conditions, geological, hydrological and seismic conditions, radiological background), description of the power plant (building structures, safety vessel, reactor core, cooling system, ventilation systems, steam power plant, electrical facilities, systems for measurement and control), indication of operation (commissioning, operation, safety measures, radiation monitoring, organization), incident analysis (reactivity incidents, loss-of-coolant incidents, external impacts). (HP) [de

ELF magnetic fields in electric and gasoline-powered vehicles.

Science.gov (United States)

Tell, R A; Sias, G; Smith, J; Sahl, J; Kavet, R

2013-02-01

We conducted a pilot study to assess magnetic field levels in electric compared to gasoline-powered vehicles, and established a methodology that would provide valid data for further assessments. The sample consisted of 14 vehicles, all manufactured between January 2000 and April 2009; 6 were gasoline-powered vehicles and 8 were electric vehicles of various types. Of the eight models available, three were represented by a gasoline-powered vehicle and at least one electric vehicle, enabling intra-model comparisons. Vehicles were driven over a 16.3 km test route. Each vehicle was equipped with six EMDEX Lite broadband meters with a 40-1,000 Hz bandwidth programmed to sample every 4 s. Standard statistical testing was based on the fact that the autocorrelation statistic damped quickly with time. For seven electric cars, the geometric mean (GM) of all measurements (N = 18,318) was 0.095 µT with a geometric standard deviation (GSD) of 2.66, compared to 0.051 µT (N = 9,301; GSD = 2.11) for four gasoline-powered cars (P electric vehicles covered the same range as personal exposure levels recorded in that study. All fields measured in all vehicles were much less than the exposure limits published by the International Commission on Non-Ionizing Radiation Protection (ICNIRP) and the Institute of Electrical and Electronics Engineers (IEEE). Future studies should include larger sample sizes representative of a greater cross-section of electric-type vehicles. Copyright © 2012 Wiley Periodicals, Inc.

Nuclear reactors for space electric power

International Nuclear Information System (INIS)

Buden, D.

1978-06-01

The Los Alamos Scientific Laboratory is studying reactor power plants for space applications in the late 1980s and 1990s. The study is concentrating on high-temperature, compact, fast reactors that can be coupled with various radiation shielding systems and thermoelectric, dynamic, or thermionic electric power conversion systems, depending on the mission. Lifetimes of 7 to 10 yr at full power, at converter operating temperatures of 1275 to 1675 0 K, are being studied. The systems are being designed such that no single-failure modes exist that will cause a complete loss of power. In fact, to meet the long lifetimes, highly redundant design features are being emphasized. Questions have been raised about safety since the COSMOS 954 incident. ''Fail-safe'' means to prevent exposure of the population to radioactive material, meeting the environmental guidelines established by the U.S. Government have been and continue to be a necessary requirement for any space reactor program. The major safety feature to prevent prelaunch and launch radioactive material hazards is not operating the reactor before achieving the prescribed orbit. Design features in the reactor ensure that accidental criticality cannot occur. High orbits (above 400 to 500 nautical miles) have sufficient lifetimes to allow radioactive elements to decay to safe levels. The major proposed applications for satellites with reactors in Earth orbit are in geosynchronous orbit (19,400 nautical miles). In missions at geosynchronous orbit, where orbital lifetimes are practically indefinite, the safety considerations are negligible. Orbits below 400 to 500 nautical miles are the ones where a safety issue is involved in case of satellite malfunction. The potential missions, the question of why reactors are being considered as a prime power candidate, reactor features, and safety considerations will be discussed

Progress of innovation of electrical power technology in 2013

International Nuclear Information System (INIS)

Nakaiwa, Masaru; Inumaru, Jun; Hamada, Takashi

2014-01-01

The following is the description of technical innovations at five companies including Central Research Institute of Electric Power Industry, Japan Atomic Energy Agency, and Japan Nuclear Fuel Ltd. Central Research Institute of Electric Power Industry presented their efforts in (1) advancement of the safety of light water reactors (2) clarification of radiological risks and improvement of radiation protection matters (3) support of backend projects and (4) countermeasures against natural disasters for electric power distribution facilities aiming at the establishment of the optimum risk management. Japan Atomic Energy Agency presented the research and development related to (1) measures taken for the Fukushima Daiichi nuclear power plant accident (2) practical use of FBR cycle (3) disposal technology of high-level radioactive wastes (4) technical system to extract fusion energy (5) particle beam technology (6) research based on the formation of the foundation and social needs of atomic study (7) nuclear hydrogen/heat application (8) atomic safety (9) backend measures; and (10) nuclear proliferation. Japan Nuclear Fuel Ltd. presented the record of 5 and half years from the start to the completion of vitrification test. In the course of the development, the active test started from March 2003 was suspended due to the Great East Japan Earthquake on March 11th, 2011 but resumed thereafter and completed. (S.Y.)

75 FR 33515 - Federal Motor Vehicle Safety Standards; Electric-Powered Vehicles; Electrolyte Spillage and...

Science.gov (United States)

2010-06-14

... instrument used for measuring electrical resistance which consists of two main elements: (1) A DC generator... physiological impacts of direct current (DC) are less than those of alternating current (AC), this rule specifies lower electrical isolation requirements for certain DC components than for AC components. The...

Electric power annual, 1991

International Nuclear Information System (INIS)

1993-01-01

The Electric Power Annual is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. The 1991 edition has been enhanced to include statistics on electric utility demand-side management and nonutility supply. ''The US Electric Power Industry at a Glance'' section presents a profile of the electric power industry ownership and performance, and a review of key statistics for the year. Subsequent sections present data on generating capability, including proposed capability additions; net generation; fossil-fuel statistics; electricity sales, revenue, and average revenue per kilowatthour sold; financial statistics; environmental statistics; electric power transactions; demand-side management; and nonutility power producers. In addition, the appendices provide supplemental data on major disturbances and unusual occurrences in US electricity power systems. Each section contains related text and tables and refers the reader to the appropriate publication that contains more detailed data on the subject matter. Monetary values in this publication are expressed in nominal terms

Electric power annual 1992

Energy Technology Data Exchange (ETDEWEB)

1994-01-06

The Electric Power Annual presents a summary of electric utility statistics at national, regional and State levels. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts and the general public with historical data that may be used in understanding US electricity markets. The Electric Power Annual is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. ``The US Electric Power Industry at a Glance`` section presents a profile of the electric power industry ownership and performance, and a review of key statistics for the year. Subsequent sections present data on generating capability, including proposed capability additions; net generation; fossil-fuel statistics; retail sales; revenue; financial statistics; environmental statistics; electric power transactions; demand-side management; and nonutility power producers. In addition, the appendices provide supplemental data on major disturbances and unusual occurrences in US electricity power systems. Each section contains related text and tables and refers the reader to the appropriate publication that contains more detailed data on the subject matter. Monetary values in this publication are expressed in nominal terms.

Electrical power distribution control methods, electrical energy demand monitoring methods, and power management devices

Science.gov (United States)

Chassin, David P [Pasco, WA; Donnelly, Matthew K [Kennewick, WA; Dagle, Jeffery E [Richland, WA

2011-12-06

Electrical power distribution control methods, electrical energy demand monitoring methods, and power management devices are described. In one aspect, an electrical power distribution control method includes providing electrical energy from an electrical power distribution system, applying the electrical energy to a load, providing a plurality of different values for a threshold at a plurality of moments in time and corresponding to an electrical characteristic of the electrical energy, and adjusting an amount of the electrical energy applied to the load responsive to an electrical characteristic of the electrical energy triggering one of the values of the threshold at the respective moment in time.

18 CFR 292.308 - Standards for operating reliability.

Science.gov (United States)

2010-04-01

... reliability. 292.308 Section 292.308 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY... SMALL POWER PRODUCTION AND COGENERATION Arrangements Between Electric Utilities and Qualifying... may establish reasonable standards to ensure system safety and reliability of interconnected...

Food Safety & Standards

Institute of Scientific and Technical Information of China (English)

无

2005-01-01

@@ An increasing number of people have realized that food safety is an important issue for public health. It not only concerns public health and safety, but also has direct influence on national economic progress and social development. The development and implementation of food safety standards play a vital role in protecting public health, as well as in standardizing and facilitating the sound development of food production and business.

Status report on nuclear reactors for space electric power

International Nuclear Information System (INIS)

Buden, D.

1978-01-01

The Los Alamos Scientific Laboratory is studying reactor power plants for space applications in the late 1980s and 1990s. The study is concentrating on high-temperature, compact, fast reactors that can be coupled with various radiation shielding systems and thermoelectric, dynamic, or thermionic electric power conversion systems, depending on the mission. Increased questions have been raised about safety since the COSMOS 954 incident. High orbits (above 400 to 500 nautical miles) have sufficient lifetimes to allow radioactive elements to decay to safe levels. The major proposed applications for satellites with reactors in Earth orbit are in geosynchronous orbit (19,400 nautical miles). In missions at geosynchronous orbit where orbital lifetimes are practically indefinite, the safety considerations are negligible. The potential missions, why reactors are being considered as a prime power candidate, reactor features, and safety considerations are discussed

Periodic Safety Review of Nuclear Power Plants: Experience of Member States

International Nuclear Information System (INIS)

2010-04-01

Routine reviews of nuclear power plant operation (including modifications to hardware and procedures, operating experience, plant management and personnel competence) and special reviews following major events of safety significance are the primary means of safety verification. In addition, many Member States of the IAEA have initiated systematic safety reassessments, termed periodic safety reviews, of nuclear power plants, to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments and siting aspects. The reviews include an assessment of plant design and operation against current safety standards and practices, and they have the objective of ensuring a high level of safety throughout the plant's operating lifetime. They are complementary to the routine and special safety reviews and do not replace them. Periodic safety reviews of nuclear power plants are considered an effective way to obtain an overall view of actual plant safety, and to determine reasonable and practical modifications that should be made in order to maintain a high level of safety. They can be used as a means of identifying time limiting features of the plant in order to determine nuclear power plant operation beyond the designed lifetime. The periodic safety review process can be used to support the decision making process for long term operation or licence renewal. Since 1994, the use of periodic safety reviews by Member States has substantially broadened and confirmed its benefits. Periodic safety review results have, for example, been used by some Member States to help provide a basis for continued operation beyond the current licence term, to communicate more effectively with stakeholders regarding nuclear power plant safety, and to help identify changes to plant operation that enhance safety. This IAEA-TECDOC is intended to assist Member States in the implementation of a periodic safety review. This publication complements the

Best Estimate plus Uncertainty (BEPU) Analyses in the IAEA Safety Standards

International Nuclear Information System (INIS)

Dusic, Milorad; )

2013-01-01

The Safety Standards Series establishes an essential basis for safety and represents the broadest international consensus. Safety Standards Series publications are categorized into: Safety Fundamental (Present the overall objectives, concepts and principles of protection and safety, they are the policy documents of the safety standards), Safety Requirements (Establish requirements that must be met to ensure the protection and safety of people and the environment, both now and in the future), and Safety Guides (Provide guidance, in the form of more detailed actions, conditions or procedures that can be used to comply with the Requirements). The incorporation of more detailed requirements, in accordance with national practice, may still be necessary. There should be only one set of international safety standards. Each safety standard will be reviewed by the relevant committee or by the commission every five years. Best Estimate plus Uncertainty (BEPU) Analyses are approached in the following IAEA Safety Standards: - Safety Requirements SSR 2/1 - Safety of NPPs, Design (Revision of NS-R-1); - General Safety Requirement GSR Part 4: Safety Assessment for Facilities and Activities; - Safety Guide SSG-2 Deterministic Safety Analysis for Nuclear Power Plants. NUSSC suggested that new safety guides should be accompanied by documents like TECDOCs or Safety Reports describing in detail their recommendations where appropriate. Special review is currently underway to identify needs for revision in the light of the Fukushima accident. Revision will concern, first, the Safety Requirements, and then, the Selected Safety Guides

Complementary assessment of the safety of French nuclear power plants

International Nuclear Information System (INIS)

Camarcat, N.; Pouget-Abadie, X.

2011-01-01

As an immediate consequence of the Fukushima accident the French nuclear safety Authority (ASN) asked EDF to perform a complementary safety assessment for each nuclear power plant dealing with 3 points: 1) the consequences of exceptional natural disasters, 2) the consequences of total loss of electrical power, and 3) the management of emergency situations. The safety margin has to be assessed considering 3 main points: first a review of the conformity to the initial safety requirements, secondly the resistance to events overdoing what the facility was designed to stand for, and the feasibility of any modification susceptible to improve the safety of the facility. This article details the specifications of such assessment, the methodology followed by EDF, the task organization and the time schedule. (A.C.)

Electric power generation

International Nuclear Information System (INIS)

Pinske, J.D.

1981-01-01

Apart from discussing some principles of power industry the present text deals with the different ways of electric power generation. Both the conventional methods of energy conversion in heating and water power stations and the facilities for utilizing regenerative energy sources (sun, wind, ground heat, tidal power) are considered. The script represents the essentials of the lecture of the same name which is offered to the students of the special subject 'electric power engineering' at the Fachhochschule Hamburg. It does not require any special preliminary knowledge except for the general principles of electrical engineering. It is addressing students of electrical engineering who have passed their preliminary examination at technical colleges and universities. Moreover, it shall also be of use for engineers who want to obtain a quick survey of the structure and the operating characteristics of the extremely different technical methods of power generation. (orig.) [de

Application of probabilistic safety assessment for Macedonian electric power system

International Nuclear Information System (INIS)

Kancev, D.; Causevski, A.; Cepin, M.; Volkanovski, A.

2007-01-01

Due to the complex and integrated nature of a power system, failures in any part of the system can cause interruptions, which range from inconveniencing a small number of local residents to a major and widespread catastrophic disruption of supply known as blackout. The objective of the paper is to show that the methods and tools of probabilistic safety assessment are applicable for assessment and improvement of real power systems. The method used in this paper is developed based on the fault tree analysis and is adapted for the power system reliability analysis. A particular power system i.e. the Macedonian power system is the object of the analysis. The results show that the method is suitable for application of real systems. The reliability of Macedonian power system assumed as the static system is assessed. The components, which can significantly impact the power system are identified and analysed in more details. (author)

Nuclear energy generation and the safety criteria for Brazilian power plants

International Nuclear Information System (INIS)

Silva, Gustavo Brandão e

2016-01-01

The purpose of this paper is to show how the use of nuclear technology can help to diversify the national electricity matrix in a sustainable and efficient way. For this, an analysis of the current situation of the Brazilian electric sector will be made, exposing its fragilities and highlighting the advantages of the nuclear source as an alternative to integrate the necessary thermoelectric base to the reliable supply of electricity in the country. In addition, the objective of the work is to detail the process of exploiting atomic energy in Brazil from raw material mining, through the stages involving the manufacture of nuclear fuel, to the current operation and situation of Brazilian power plants. By taking the Angra 2 Nuclear Power Plant as a case study, the safety criteria adopted in its design and operation will be highlighted. Particular attention will also be given to the electric supply alternatives and to the active safety systems of the plant

Working out the standards for nuclear power aging management implementation (PLM Standards)

International Nuclear Information System (INIS)

Miyano, Hiroshi

2008-01-01

Background of preparation of standards, preparation of standards for development of nuclear power aging management technologies, revision of PLM (Product Lifecycle Management) standards, and problems of PLM standards are stated. The placement of social needs, scheme, the standards system, preparation of rules and standards, and practical use of them by road map are illustrated and explained. Relation between the safety regulations and examination standards, and development and preparation of standards system are outlined. The nuclear power plant aging management and the maintenance control are provided by many rules and standards. PLM standards defines the aging phenomena and extracts the measurements and reflects them on the usual maintenance flow under the long term maintenance program. New examination system constructs the usual maintenance and the maintenance based on the aging management and long term maintenance program. Outline and construction of PLM standards are explained with notes and additional books. (S.Y.)

IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

International Nuclear Information System (INIS)

2014-01-01

The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

Standard method for economic analyses of inertial confinement fusion power plants

International Nuclear Information System (INIS)

Meier, W.R.

1986-01-01

A standard method for calculating the total capital cost and the cost of electricity for a typical inertial confinement fusion electric power plant has been developed. A standard code of accounts at the two-digit level is given for the factors making up the total capital cost of the power plant. Equations are given for calculating the indirect capital costs, the project contingency, and the time-related costs. Expressions for calculating the fixed charge rate, which is necessary to determine the cost of electricity, are also described. Default parameters are given to define a reference case for comparative economic analyses

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

Qualification of electric equipments for nuclear power plants

International Nuclear Information System (INIS)

Chauvin, G.; Raimondo, E.

1983-03-01

Description of the testing equipment, testing methods and standards of the resistance to seisms of electrical equipments (switches, pump motors, electrovalves, ...) for electronuclear power plants in France. Presentation of the French design and construction rules for electrical devices in the domestic and export nuclear market (resistance to thermodynamical and chemical stresses, to seisms, etc...) [fr

Safety first. Status reports on the IAEA's safety standards

International Nuclear Information System (INIS)

Webb, G.; Karbassioun, A.; Linsley, G.; Rawl, R.

1998-01-01

Documents in the IAEA's Safety Standards Series known as RASS (Radiation Safety Standards) are produced to develop an internally consistent set of regulatory-style publications that reflects an international consensus on the principles of radiation protection and safety and their application through regulation. In this article are briefly presented the Agency's programmes on Nuclear Safety Standards (NUSS), Radioactive Waste Safety Standards (RADWASS), and Safe Transport of Radioactive Materials

Standard Review Plan for the review of safety analysis reports for nuclear power plants, Revision No. 7 to Section 9

International Nuclear Information System (INIS)

1978-03-01

Revision No. 1 to Section 9 of the Standard Review Plan incorporates changes that have been developed since the original issuance in September 1975, many of which are editorial in nature, to reflect current staff practice in the review of safety analysis reports for nuclear power plants

Electric power supply for a mine: Principles and examples

International Nuclear Information System (INIS)

Mienville, G.; Grellety, J.

1990-01-01

The power supply of a water pumping system at the PEN or RAN mine is studied. A reliable pumping system was required because of the small volume of the available drainage reservoirs. Different power supply systems are considered. The 20 RV system configuration and adapted safety devices are described. The use of a generating set was required to ensure the mine operations. The power supply system in use allowed a reduction of the electricity cost [fr

Internal Arc: People safety in the electrical wiring

International Nuclear Information System (INIS)

Inchausti, J. M.

2009-01-01

The aim of this article is to describe the internal arc phenomenon, an extremely fast, almost explosive and unattended process of transformation form an initial electric power to the generation of a pressure and heat wave inside the medium its produced its consequences for safety, current methods of limiting them and current regulations in general for equipment used in medium-voltage electrical distribution networks. Taking into account that this type of equipment is found thought the distribution network in both public buildings and unrestricted access areas, safety (of operators and the general public) must be taken into account in the design of equipment and installations to minimize the risk of internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which the manufacturer has to takes steps to minimize the risks of an internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which an internal arc occurring, it is understood to be vitally important that users, installers and designers of Medium Voltage installations are familiar with the installation conditions stated by the manufacturer and thus avoid risks. (Author) 14 refs

Research on the impacts of large-scale electric vehicles integration into power grid

Science.gov (United States)

Su, Chuankun; Zhang, Jian

2018-06-01

Because of its special energy driving mode, electric vehicles can improve the efficiency of energy utilization and reduce the pollution to the environment, which is being paid more and more attention. But the charging behavior of electric vehicles is random and intermittent. If the electric vehicle is disordered charging in a large scale, it causes great pressure on the structure and operation of the power grid and affects the safety and economic operation of the power grid. With the development of V2G technology in electric vehicle, the study of the charging and discharging characteristics of electric vehicles is of great significance for improving the safe operation of the power grid and the efficiency of energy utilization.

Present state of electric power business in United States and Europe

International Nuclear Information System (INIS)

Onishi, Kenichi

2011-01-01

This article reported present state of nuclear power and electric power business in United States and Europe after Fukushima Daiichi Accident. As for the trend of demand and supply of electric power and policy, the accident forced Germany possibly to proceed with phase-out of nuclear power, but France and United States to sustain nuclear power with no great change of energy policy at this moment. As for the trend of electric power market, there was not state in United States with liberalized retail market of electric power after rolling blackouts occurred in California State in the early 2000s. In Germany proceeding with renewable energy introduction, renewable electricity fed into the grid was paid for by the network operators at fixed tariffs and the costs passed on to electricity consumers were increasing. Renewable Portfolio Standards (RPS) in United States forced the state to introduction of renewable energy to some ratio, and Feed-in Tariff (FIT) introduced in EU in 1990s lead to introduction of a large amount of renewable electricity targeted in 2020. Huge amount of wind power introduction brought about several problems to solve such that excess electric power above domestic demand had bad effects on grids in neighboring region. Enforcement of power transmission lines was also needed with increase of maximum electric power as well as introduction of a large amount of renewable electricity. (T. Tanaka)

ELMO model predicts the price of electric power

International Nuclear Information System (INIS)

Antila, H.

2001-01-01

Electrowatt-Ekono has developed a new model, by which it is possible to make long-term prognoses on the development of electricity prices in the Nordic Countries. The ELMO model can be used as an analysis service of the electricity markets and estimation of the profitability of long-term power distribution contracts with different scenarios. It can also be applied for calculation of technical and economical fundamentals for new power plants, and for estimation of the effects of different taxation models on the emissions of power generation. The model describes the whole power generation system, the power and heat consumption and transmission. The Finnish power generation system is based on the Electrowatt-Ekono's boiler database by combining different data elements. Calculation is based on the assumption that the Nordic power generation system is used optimally, and that the production costs are minimised. In practise the effectively operated electricity markets ensure the optimal use of the production system. The market area to be described consists of Finland and Sweden. The spot prices have long been the same. Norway has been treated as a separate market area. The most potential power generation system, the power consumption and the power transmission system are presumed for the target year during a normal rainfall situation. The basic scenario is calculated on the basis of the preconditional data. The calculation is carried out on hourly basis, which enables the estimation of the price variation of electric power between different times during the day and seasons. The system optimises the power generation on the basis of electricity and heat consumption curves and fuel prices. The result is an hourly limit price for electric power. Estimates are presented as standard form reports. Prices are presented as average annuals, in the seasonal base, and in hourly or daily basis for different seasons

IEEE standard for qualifying class IE equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1974-01-01

The Institute of Electrical and Electrical Engineers, Inc. (IEEE) standards for electrical equipment (Class IE) for nuclear power generating stations are given. The standards are to provide guidance for demonstrating and documenting the adequacy of electric equipment used in all Class IE and interface systems. Representative in containment design basis event conditions for the principal reactor types are included in the appendixes for guidance in enviromental simulation

HIL Simulation of Power Electronics and Electric Drives for Automotive Applications

Directory of Open Access Journals (Sweden)

Frank Puschmann

2012-12-01

Full Text Available Hardware-in-the-loop simulation is today a standard method for testing electronic equipment in the automotive industry. Since electric drives and power electronic devices are more and more important in automotive applications, these kinds of systems have to be integrated into the hardware-in-the-loop simulation. Power converters and electric drives are used in many different applications in vehicles today (hybrid electric or electric powertrain, electric steering systems, DC-DC converters, etc.. The wide range of applications, topologies, and power levels results in various different approaches and solutions for hardware-in-the-loop testing. This paper gives an overview of hardware-in-the-loop simulation of power electronics and electric drives in the automotive industry. The currently available technologies are described and future challenges are outlined.

A complete electrical hazard classification system and its application

Energy Technology Data Exchange (ETDEWEB)

Gordon, Lloyd B [Los Alamos National Laboratory; Cartelli, Laura [Los Alamos National Laboratory

2009-01-01

The Standard for Electrical Safety in the Workplace, NFPA 70E, and relevant OSHA electrical safety standards evolved to address the hazards of 60-Hz power that are faced primarily by electricians, linemen, and others performing facility and utility work. This leaves a substantial gap in the management of electrical hazards in Research and Development (R&D) and specialized high voltage and high power equipment. Examples include lasers, accelerators, capacitor banks, electroplating systems, induction and dielectric heating systems, etc. Although all such systems are fed by 50/60 Hz alternating current (ac) power, we find substantial use of direct current (dc) electrical energy, and the use of capacitors, inductors, batteries, and radiofrequency (RF) power. The electrical hazards of these forms of electricity and their systems are different than for 50160 Hz power. Over the past 10 years there has been an effort to develop a method of classifying all of the electrical hazards found in all types of R&D and utilization equipment. Examples of the variation of these hazards from NFPA 70E include (a) high voltage can be harmless, if the available current is sufficiently low, (b) low voltage can be harmful if the available current/power is high, (c) high voltage capacitor hazards are unique and include severe reflex action, affects on the heart, and tissue damage, and (d) arc flash hazard analysis for dc and capacitor systems are not provided in existing standards. This work has led to a comprehensive electrical hazard classification system that is based on various research conducted over the past 100 years, on analysis of such systems in R&D, and on decades of experience. Initially, national electrical safety codes required the qualified worker only to know the source voltage to determine the shock hazard. Later, as arc flash hazards were understood, the fault current and clearing time were needed. These items are still insufficient to fully characterize all types of

System 80+trademark Standard Design: CESSAR design certification

International Nuclear Information System (INIS)

1990-01-01

This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80 + trademark Standard Design. This volume 9 discusses Electric Power and Auxiliary Systems

Safety Evaluation Report related to the operation of Wm. H. Zimmer Nuclear Power Station, Unit No. 1. Docket No. 50-358. Cincinnati Gas and Electric Company

International Nuclear Information System (INIS)

1982-08-01

Information is presented concerning site characteristics; design criteria for structures, systems, and components; reactor; reactor coolant system and connected systems; engineered safety features; instrumentation and controls; electric power; auxiliary systems; conduct of operations; and TMI-2 requirements

IAEA codes and guides for safety of nuclear power plants

International Nuclear Information System (INIS)

Raisic, N.

1980-01-01

The objectives and scope of the Agency's programme of nuclear safety standards are described and the role of these documents in regulation of nuclear power im Member States is discussed. For each of the five areas of safety standards development, i.e. siting, design, operation, quality assurance and governmental organization, a set of principles underlying requirements and recommendations contained in the Code of Practice and Safety Guides will be presented. Safety Guides in each of the five areas will be reviewed in respect of the scope and content. A consideration will be given to the future development of the safety standards and to the revision and updating of the published documents. (orig./RW)

A new standard for multidisciplinary health and safety technicians

International Nuclear Information System (INIS)

Trinoskey, P.A.; Fry, L.A.; Egbert, W.F.

2000-01-01

Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

A new standard for multidisciplinary health and safety technicians

Energy Technology Data Exchange (ETDEWEB)

Trinoskey, P.A.; Fry, L.A. [Lawrence Livermore National Laboratory, Univ. of California, CA (United States); Egbert, W.F. [Lawrence Livermore National Laboratory, Allied Signal Technical Corporation (United States)

2000-05-01

Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

International Nuclear Information System (INIS)

1982-01-01

A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

Shipboard electrical power systems

CERN Document Server

Patel, Mukund R

2011-01-01

Shipboard Electrical Power Systems addresses new developments in this growing field. Focused on the trend toward electrification to power commercial shipping, naval, and passenger vessels, this book helps new or experienced engineers master cutting-edge methods for power system design, control, protection, and economic use of power. Provides Basic Transferable Skills for Managing Electrical Power on Ships or on LandThis groundbreaking book is the first volume of its kind to illustrate optimization of all aspects of shipboard electrical power systems. Applying author Mukund Patel's rare combina

Nuclear Power Plants in a Competitive Electricity Market

International Nuclear Information System (INIS)

Jankauskas, V.

2002-01-01

Electricity demand is growing in the world by an average rate of 3% and, according to the International Energy Agency, is going to keep this pace of growth for the 1st quarter of the 21st century. At the same time, the role of the nuclear in the world energy mix is diminishing, and in 2020 only 9% of the world electricity will be produced at the nuclear plants versus 17% in 2000. The main reasons for the nuclear power diminishing share in the world market are not environmental or safety problems, as one may assume, but technical and economical. Long construction time, high capital cost, huge liabilities connected with the spent nuclear fuel and radioactive waste treatment, storage and final disposal are the main factors restricting the further growth of the nuclear power. Nevertheless, in the liberalized markets (U.K., Germany, Scandinavian countries) nuclear power plants are operating rather successfully. In a short run nuclear plants may become very competitive as they have very low short-run marginal costs, but in the long run they may become very in competitive. The Ignalina NPP plays the dominant ro]e in the Lithuanian electricity market, producing more than 75% of the total domestic electricity. It produces the cheapest electricity in Lithuania, mostly due to its higher availability, than the thermal power plants. The price of electricity sold by Ignalina is also lower as it does not cover all costs connected with the future decommissioning of the plant, spent fuel storage and final disposal. If at least part of this cost were included into the selling price, Ignalina might become highly competitive in a liberalised electricity market. As the Lithuanian Electricity law requires to deregulate electricity. generation prices, these prices should be set by the market. (author)

NASA safety standard for lifting devices and equipment

Science.gov (United States)

1990-09-01

NASA's minimum safety requirements are established for the design, testing, inspection, maintenance, certification, and use of overhead and gantry cranes (including top running monorail, underhung, and jib cranes), mobile cranes, derrick hoists, and special hoist supported personnel lifting devices (these do not include elevators, ground supported personnel lifts, or powered platforms). Minimum requirements are also addressed for the testing, inspection, and use of Hydra-sets, hooks, and slings. Safety standards are thoroughly detailed.

The Role of Nuclear Power in Slovak Republic; Safety Upgrading Program for WWER Reactors

International Nuclear Information System (INIS)

Toth, A.

1998-01-01

Implementation of Slovenske elektrarne Production Base Development Program, where all these safety upgrading projects of nuclear power sources at Slovak Republic are included will ensure first of all safety of nuclear power sources on internationally acceptable level, operational reliability of nuclear power units, balanced consumption and production of electric energy in Slovakia and decrease of long term ecological impact in according with international commitments of Slovakia

The history of 10 years of electrical safety

International Nuclear Information System (INIS)

1984-12-01

This book describes the foundation course of Korea electrical power corporation, including the process of the establishment with difficulty in the early period, growth through the rough passage, maintain of stability with voluntary service for public benefit. Next it deals with the management of the organization, and personnel management, financial affairs the management of business, examination for safety. The last part is an appendix for the administration law of each deportment.

The floating nuclear power plant with high safety (''Cruise-M'')

International Nuclear Information System (INIS)

Gromov, B.F.; Stepanov, V.N.; Toshinsky, G.I.; Tchekunov, V.V.; Stepanov, V.S.; Vakhrushin, M.P.; Kiryukhin, V.I.; Maltsev, V.P.; Kozlov, B.M.; Landgraf, K.A.

1997-01-01

The results of conceptual development for a floating nuclear power plant (FNPP) of 50 MW(e) with a nuclear steam producing unit (NSPU) based on a fast reactor with lead-bismut coolant were presented. A lead-bismuth coolant has a number of important safety advantages and it was developed in Russia for nuclear-powered submarines. This FNPP could be used as a power source for seawater desalination and electricity supply. (author)

Safety of nuclear power reactors in the former Eastern European Countries

International Nuclear Information System (INIS)

Chakraborty, S.

1995-01-01

This article discusses the safety of nuclear power plants in the former Eastern European countries (including the former Soviet Union). The current international design, fabrication, construction, operation, safety, regulatory standards and practices, and ways to resolve plant problems are addressed in light of experience with the Western nuclear power development programs

Electric power industry in China

Energy Technology Data Exchange (ETDEWEB)

Zisheng Jiang [Ministry of Electric Power, Beijing (China). Bureau of Electric Power Machinery

1995-07-01

This document presents the status of the electric power in China, highlighting the following aspects: recent achievement, electricity increased sharing in the total energy consumption, technical economic indexes, nuclear power, renewable energy sources, rural electrification, transmission and power network, transmission lines and substations, present status and development trends for power network, regulation of power system dispatching, power system communication. The document also presents the future developing plan, approaching the outlook and strategy, development targets of the electric power industry and the administrative system reforming of the electric power industry.

Electric power distribution. 5th Rev. Ed. Elektrische Energieverteilung

Energy Technology Data Exchange (ETDEWEB)

Flosdorff, R; Hilgarth, G

1986-01-01

The first chapter on electric power supply networks discusses transmitting media, their characteristic values, and the dimensioning of electric lines and networks; cables are given particular attention. High-voltage d.c. transmission and reactive power compensation are discussed. The next chapter describes the calculation of short-circuits and earth leakages for various neutral circuits on the basis of symmetric components. The newly introduced mesh current method for complex calculation of electric networks makes use of the potential of pocket computers. Chapter 3 discusses protective devices, i.e. earth systems and electronic protection. The next two chapters describe switch gear and power plants, including recent technical changes. The final chapter, which discusses the electric power industry, has been rewritten and extended. Methods of calculation, e.g. annual cost and cash value, are applied to transmitting media and plants. There is an extensive appendix with characteristic values of cables and overhead lines, graphical symbols, distinguishing signs of wiring diagrams, a bibliography of books, DIN standards, VDE specifications, and formulas.

Consequences of EU enlargement for supply and demand in the electricity market with special emphasis on nuclear power

International Nuclear Information System (INIS)

Jaeger, G.

2004-01-01

After the enlargement of the European Union, Europe has acquired a new dimension which is reflected also on the electricity market. The aggregate European electricity requirement of 3 000 TWh in Europe constitutes approximately one quarter of the world electricity generation. Nuclear power contributes a major share of 966 TWh. In electricity generation from nuclear power, EU-25 is No. 1 in the world. The rising demand for electricity cannot be met by the existing power plant park in the next few decades. Insufficient possibilities of exchange among countries and, especially, the enormous requirement to replace more than 200,000 MW of electricity generating capacity in Europe by 2020, plus another 100,000 MW arising from growing demand, make a comprehensive renewal of the European power plant park indispensable. After the EU enlargement, the standards of the ''old'' European Union are the yardstick for the entire ''new'' Union. This gives rise to enormous efforts, especially in the accession countries, to curb emissions and increase safety. The need for modern power plant technology is becoming particularly apparent in these cases. The example of the ten new member countries clearly shows the options realistically available for electricity generation in the future and indispensable for a favorable infrastructure. The conventional energy resources, i. e. coal, gas, and nuclear power, will be the main sources of electricity generation in Europe over the next few decades. This finding does not meet the expectations of many members of the public who feel that renewables would make the largest contribution to power supply in twenty years' time. This makes it imperative to regain popular acceptance in order to ensure electricity generation at favorable conditions and at a high level of environmental protection in the whole of Europe, with enough leeway to further advance the expansion of renewables and support a positive economic development of Europe. (orig.)

Security attack detection algorithm for electric power gis system based on mobile application

Science.gov (United States)

Zhou, Chao; Feng, Renjun; Wang, Liming; Huang, Wei; Guo, Yajuan

2017-05-01

Electric power GIS is one of the key information technologies to satisfy the power grid construction in China, and widely used in power grid construction planning, weather, and power distribution management. The introduction of electric power GIS based on mobile applications is an effective extension of the geographic information system that has been widely used in the electric power industry. It provides reliable, cheap and sustainable power service for the country. The accurate state estimation is the important conditions to maintain the normal operation of the electric power GIS. Recent research has shown that attackers can inject the complex false data into the power system. The injection attack of this new type of false data (load integrity attack LIA) can successfully bypass the routine detection to achieve the purpose of attack, so that the control center will make a series of wrong decision. Eventually, leading to uneven distribution of power in the grid. In order to ensure the safety of the electric power GIS system based on mobile application, it is very important to analyze the attack mechanism and propose a new type of attack, and to study the corresponding detection method and prevention strategy in the environment of electric power GIS system based on mobile application.

Automating a spacecraft electrical power system using expert systems

Science.gov (United States)

Lollar, L. F.

1991-01-01

Since Skylab, Marshall Space Flight Center (MSFC) has recognized the need for large electrical power systems (EPS's) in upcoming Spacecraft. The operation of the spacecraft depends on the EPS. Therefore, it must be efficient, safe, and reliable. In 1978, as a consequence of having to supply a large number of EPS personnel to monitor and control Skylab, the Electrical power Branch of MSFC began the autonomously managed power system (AMPS) project. This project resulted in the assembly of a 25-kW high-voltage dc test facility and provided the means of getting man out of the loop as much as possible. AMPS includes several embedded controllers which allow a significant level of autonomous operation. More recently, the Electrical Division at MSFC has developed the space station module power management and distribution (SSM/PMAD) breadboard to investigate managing and distributing power in the Space Station Freedom habitation and laboratory modules. Again, the requirement for a high level of autonomy for the efficient operation over the lifetime of the station and for the benefits of enhanced safety has been demonstrated. This paper describes the two breadboards and the hierarchical approach to automation which was developed through these projects.

Power and performance. Y2K challenges for electricity grids in Eastern Europe

International Nuclear Information System (INIS)

Kossilov, A.; Gueorguiev, B.; Ianev, I.; Purvis, E.

1999-01-01

The Year 2000 problem can directly affect the safety of nuclear power plants through interfaces with electric power and telecommunication systems. Recently, probabilistic safety assessments have made it clear that a 'station blackout' at a nuclear power plant is a major contributor to the sequence of events that could cause severe accidents. Within the IAEA actions concerned with Y2K problem, particular focus was on countries in eastern Europe, where here were delays in taking Y2K corrective actions

Electric vehicle system for charging and supplying electrical power

Science.gov (United States)

Su, Gui Jia

2010-06-08

A power system that provides power between an energy storage device, an external charging-source/load, an onboard electrical power generator, and a vehicle drive shaft. The power system has at least one energy storage device electrically connected across a dc bus, at least one filter capacitor leg having at least one filter capacitor electrically connected across the dc bus, at least one power inverter/converter electrically connected across the dc bus, and at least one multiphase motor/generator having stator windings electrically connected at one end to form a neutral point and electrically connected on the other end to one of the power inverter/converters. A charging-sourcing selection socket is electrically connected to the neutral points and the external charging-source/load. At least one electronics controller is electrically connected to the charging-sourcing selection socket and at least one power inverter/converter. The switch legs in each of the inverter/converters selected by the charging-source/load socket collectively function as a single switch leg. The motor/generators function as an inductor.

Electric power annual, 1990

International Nuclear Information System (INIS)

1992-01-01

The Electric Power Annual presents a summary of electric utility statistics at the national, regional and State levels. The objective of the publication is to provide industry decisionmakers, government policy-makers, analysts and the general public with historical data that may be used in understanding US electricity markets. ''The Industry at a Glance'' section presents a profile of the electric power industry ownership and performance; a review of key statistics for the year; and projections for various aspects of the electric power industry through 2010. Subsequent sections present data on generating capability, including proposed capability additions; net generation; fossil-fuel statistics; electricity sales, revenue, and average revenue per kilowatthour sold; financial statistics; environmental statistics; and electric power transactions. In addition, appendices provide supplemental data on major disturbances and unusual occurrences. Each section contains related text and tables and refers the reader to the appropriate publication that contains more detailed data on the subject matter

Application of disturbance analysis methodology to safety related transients in the electrical systems of a nuclear power plant. Report UCLA-ENG-8056

International Nuclear Information System (INIS)

Guarro, S.; Okrent, D.

1981-08-01

The present study tries to address the question of whether or not the computerized on-line procedures known under the name of DAS (Disturbance Analysis System) can be usefully and successfully applied to provide timely diagnostics and operational suggestions during the occurrence of a major electrical transient in the auxiliary systems of a nuclear power plant. The perspective of the study is from the plant-safety point of view. A short definition of DAS methodology features and capabilities is presented. A discussion of some of the problems of a general nature that are encountered in DAS safety-oriented applications are also included. The event insufficient power on both emergency buses, with reference to a particular plant dsign (San Onofre 1), is presented. Some transients that have recently occurred in the power supply systems of operating plants are examined. Whether or not a DAS could have successfully dealt with such occurrences is considered

Application of disturbance analysis methodology to safety related transients in the electrical systems of a nuclear power plant. Report UCLA-ENG-8056

Energy Technology Data Exchange (ETDEWEB)

Guarro, S.; Okrent, D.

1981-08-01

The present study tries to address the question of whether or not the computerized on-line procedures known under the name of DAS (Disturbance Analysis System) can be usefully and successfully applied to provide timely diagnostics and operational suggestions during the occurrence of a major electrical transient in the auxiliary systems of a nuclear power plant. The perspective of the study is from the plant-safety point of view. A short definition of DAS methodology features and capabilities is presented. A discussion of some of the problems of a general nature that are encountered in DAS safety-oriented applications are also included. The event insufficient power on both emergency buses, with reference to a particular plant dsign (San Onofre 1), is presented. Some transients that have recently occurred in the power supply systems of operating plants are examined. Whether or not a DAS could have successfully dealt with such occurrences is considered.

Managing realities of the new market uncertainty : standards development in the North American electricity industry

International Nuclear Information System (INIS)

Green, B.

2003-01-01

Standards for the electricity industry are developed to ensure quality and serve as a basis to which utilities should conform. Standards specify agreed upon properties for a manufactured product. They should be used for equipment specifications as well as operational procedures. Standardization is performed by regulators, transmission owners/operators, and organizations such as the National Electric Reliability Council (NERC), the Northeast Power Coordinating Council (NPCC), the North American Energy Standards Board (NAESB), and the Committee of Chief Risk Officers (CCRO). Before markets were opened to competition, operational standards were dictated by transmission owners and reliability issues were dealt with by NERC and NPCC. This presentation explained the process of standardization in the electric power industry in Canada, the derivation of standards, moving beyond NERC, and the transmission owners. Issues for Ontario Power Generation were highlighted. In contrast to the situation in the United States, there is no federal government backstop for developing Standards in Canada. There is no federal initiative toward open access. Canadian utilities participated in NERC, but compliance was voluntary. It is still questionable if Canadian utilities will implement NERC and NAESB Standards if they are codified

Electric power substations engineering

CERN Document Server

2003-01-01

This book covers all aspects of substations, from the initial concept to design, automation, operation, and physical and cyber security. Written by members of the Institute of Electrical and Electronic Engineers (IEEE) Power Engineering Society (PES) Substations Committee, each section provides a tutorial and includes references for further reading and study. The authors use photographs and graphics to help the reader understand the material. Exploring the most recent technological developments regarding industry practice and standards, the book provides an extensive overview of substations th

Liberation of electric power and nuclear power generation

International Nuclear Information System (INIS)

Yajima, Masayuki

2000-01-01

In Japan, as the Rule on Electric Business was revised after an interval of 35 years in 1995, and a competitive bid on new electric source was adopted after 1996 fiscal year, investigation on further competition introduction to electric power market was begun by establishment of the Basic Group of the Electric Business Council in 1997. By a report proposed on January, 1999 by the Group, the Rule was revised again on March, 1999 to start a partial liberation or retail of the electric power from March, 2000. From a viewpoint of energy security and for solution of global environmental problem in Japan it has been decided to positively promote nuclear power in future. Therefore, it is necessary to investigate how the competition introduction affects to development of nuclear power generation and what is a market liberation model capable of harmonizing with the development on liberation of electric power market. Here was elucidated on effect of the introduction on previous and future nuclear power generation, after introducing new aspects of nuclear power problems and investigating characteristic points and investment risks specific to the nuclear power generation. And, by investigating some possibilities to development of nuclear power generation under liberation models of each market, an implication was shown on how to be future liberation on electric power market in Japan. (G.K.)

Comparative Analysis of Three Proposed Federal Renewable Electricity Standards

Energy Technology Data Exchange (ETDEWEB)

Sullivan, P.; Logan, J.; Bird, L.; Short, W.

2009-05-01

This paper analyzes potential impacts of proposed national renewable electricity standard (RES) legislation. An RES is a mandate requiring certain electricity retailers to provide a minimum share of their electricity sales from qualifying renewable power generation. The analysis focuses on draft bills introduced individually by Senator Jeff Bingaman and Representative Edward Markey, and jointly by Representative Henry Waxman and Markey. The analysis uses NREL's Regional Energy Deployment System (ReEDS) model to evaluate the impacts of the proposed RES requirements on the U.S. energy sector in four scenarios.

76 FR 66057 - North American Electric Reliability Corporation; Order Approving Regional Reliability Standard

Science.gov (United States)

2011-10-25

... Reliability Standard that is necessitated by a physical difference in the Bulk-Power System.\\7\\ \\7\\ Order No... Reliability Standards for the Bulk-Power System, Order No. 693, FERC Stats. & Regs. ] 31,242, order on reh'g... electric system event analyses and thereby improve system reliability by promoting improved system design...

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. 1.2. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1981), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1986), which are superseded by this new Safety Guide. 1.3. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1981 and 1986, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2000, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included

On the complex analysis of the reliability, safety, and economic efficiency of atomic electric power stations

International Nuclear Information System (INIS)

Emel'yanov, I.Ya.; Klemin, A.I.; Polyakov, E.F.

1977-01-01

The problem is posed of effectively increasing the engineering performance of nuclear electric power stations (APS). The principal components of the engineering performance of modern large APS are considered: economic efficiency, radiation safety, reliability, and their interrelationship. A nomenclature is proposed for the quantitative indices which most completely characterize the enumerated properties and are convenient for the analysis of the engineering performance. The urgent problem of developing a methodology for the complex analysis and optimization of the principal performance components is considered; this methodology is designed to increase the efficiency of the work on high-performance competitive APS. The principle of complex optimization of the reliability, safety, and economic-efficiency indices is formulated; specific recommendations are made for the practical realization of this principle. The structure of the complex quantiative analysis of the enumerated performance components is given. The urgency and promise of the complex approach to solving the problem of APS optimization is demonstrated, i.e., the solution of the problem of creating optimally reliable, fairly safe, and maximally economically efficient stations

Driving with electrical power

International Nuclear Information System (INIS)

Ursin, M.; Hoeckel, M.

2008-01-01

This article takes a look at the chances offered to the electricity supply industry by the increasing use of battery-driven vehicles - and the advantages thus offered to the environment. The use of the vehicles' batteries to form a distributed electricity storage scheme is discussed. The authors comment that, although electrically-driven vehicles consume more power, the total primary energy consumption and pollutant emissions will be reduced. The actual electricity consumption of electric vehicles and the source of this power are examined. Power saved by the reduced use of electrical heating systems and boilers could, according to the authors, be used to charge the batteries of electric vehicles. The use of these batteries as a storage system to help regulate electricity supplies is discussed and the steps to be taken for the implementation of such a system are listed

Interagency Nuclear Safety Review Panel Power System Subpanel review for the Ulysses mission

International Nuclear Information System (INIS)

McCulloch, W.H.

1991-01-01

As part of the Interagency Nuclear Safety Review Panel's assessment of the nuclear safety of NASA's Ulysses Mission to investigate properties of the sun, the Power System Subpanel has reviewed the safety analyses and risk evaluations done for the General Purpose Heat Source-Radioisotope Thermoelectric Generator which provides on-board electrical power for the spacecraft. This paper summarizes the activities and results of that review. In general, the approach taken in the primary analysis, executed by the General Electric Company under contract to the Department of Energy, and the resulting conclusions were confirmed by the review. However, the Subpanel took some exceptions and modified the calculations accordingly, producing an independent evaluation of potential releases of radioactive fuel in launch and reentry accidents. Some of the more important of these exceptions are described briefly

78 FR 47805 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Science.gov (United States)

2013-08-06

... Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Revision... Used in Safety Systems of Nuclear Power Plants.'' This RG endorses the Institute of Electrical and... nuclear power plants. ADDRESSES: Please refer to Docket ID NRC-2012-0195 when contacting the NRC about the...

Standard Review Plan for the review of safety analysis reports for nuclear power plants: LWR edition

International Nuclear Information System (INIS)

1987-06-01

The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The safety review is primarily based on the information provided by an applicant in a Safety Analysis Report (SAR). The SAR must be sufficiently detailed to permit the staff to determine whether the plant can be built and operated without undue risk to the health and safety of the public. The SAR is the principal document in which the applicant provides the information needed to understand the basis upon which this conclusion has been reached. The individual SRP sections address, in detail, who performs the review, the matters that are reviewed, the basis for review, how the review is accomplished, and the conclusions that are sought. The safety review is performed by 25 primary branches. One of the objectives of the SRP is to assign the review responsibilities to the various branches and to define the sometimes complex interfaces between them. Each SRP section identifies the branch that has the primary review responsibility for that section. In some review areas the primary branch may require support, and the branches that are assigned these secondary review responsibilities are also identified for each SRP section

2017 Standard Scenarios Report: A U.S. Electricity Sector Outlook

Energy Technology Data Exchange (ETDEWEB)

Cole, Wesley J. [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Mai, Trieu T. [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Richards, James [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Das, Paritosh [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Donohoo-Vallett, Paul [US Department of Energy, Washington, DC (United States). Office of Energy Efficiency and Renewable Energy (EERE)

2017-10-03

The 2017 Standard Scenarios includes a suite of U.S. electricity sector scenarios. The report explores four power sector storylines, including the growth in natural gas and renewable energy, the relative competitiveness of wind and solar PV, the potential impact of low-cost battery storage, and the impact of nuclear lifetimes on the capacity expansion of the power sector.

Electrical Safety and Arc Flash Protections

Energy Technology Data Exchange (ETDEWEB)

R. Camp

2008-03-04

Over the past four years, the Electrical Safety Program at PPPL has evolved in addressing changing regulatory requirements and lessons learned from accident events, particularly in regards to arc flash hazards and implementing NFPA 70E requirements. This presentation will discuss PPPL's approaches to the areas of electrical hazards evaluation, both shock and arc flash; engineered solutions for hazards mitigation such as remote racking of medium voltage breakers, operational changes for hazards avoidance, targeted personnel training and hazard appropriate personal protective equipment. Practical solutions for nominal voltage identification and zero voltage checks for lockout/tagout will also be covered. Finally, we will review the value of a comprehensive electrical drawing program, employee attitudes expressed as a personal safety work ethic, integrated safety management, and sustained management support for continuous safety improvement.

Electrical Safety and Arc Flash Protections

International Nuclear Information System (INIS)

Camp, R.

2008-01-01

Over the past four years, the Electrical Safety Program at PPPL has evolved in addressing changing regulatory requirements and lessons learned from accident events, particularly in regards to arc flash hazards and implementing NFPA 70E requirements. This presentation will discuss PPPL's approaches to the areas of electrical hazards evaluation, both shock and arc flash; engineered solutions for hazards mitigation such as remote racking of medium voltage breakers, operational changes for hazards avoidance, targeted personnel training and hazard appropriate personal protective equipment. Practical solutions for nominal voltage identification and zero voltage checks for lockout/tagout will also be covered. Finally, we will review the value of a comprehensive electrical drawing program, employee attitudes expressed as a personal safety work ethic, integrated safety management, and sustained management support for continuous safety improvement.

Wind power feed-in impact on electricity prices in Germany 2009-2013

Directory of Open Access Journals (Sweden)

François Benhmad

2016-07-01

Full Text Available Until quite recently no electricity system had faced the challenges associated with high penetrations of renewable energy sources (RES. In this paper, we carry out an empirical analysis for Germany, as a country with high penetration of wind energy, to investigate the well-known merit-order effect. Our main empirical findings suggest that the increasing share of wind power in-feed induces a decrease of electricity spot price level but an increase of spot prices volatility. Furthermore, the relationship between wind power and spot electricity prices can be strongly impacted by European electricity grids interconnection which behaves like a safety valve lowering volatility and limiting the price decrease. Therefore, the impacts of wind generated electricity on electricity spot markets are less clearly pronounced in interconnected systems.

Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

International Nuclear Information System (INIS)

Bertsche, K.; Hoermann, E.

1991-01-01

The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

18 CFR 38.2 - Incorporation by reference of North American Energy Standards Board Wholesale Electric Quadrant...

Science.gov (United States)

2010-04-01

... reference of North American Energy Standards Board Wholesale Electric Quadrant standards. 38.2 Section 38.2 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY... UTILITIES § 38.2 Incorporation by reference of North American Energy Standards Board Wholesale Electric...

The critical issue of nuclear power plant safety in developing countries

International Nuclear Information System (INIS)

Rosen, M.

1977-01-01

A little more than a decade from now, large commercial nuclear power facilities will be in operation in almost 40 countries, of which approximately one-half are presently considered industrially less developed. Ambitious nuclear programmes coupled with minimal and frequently under-staffed regulatory and utility organizations are only one aspect of the difficulties related to the safety of nuclear plants that face these developing countries. Inherent problems of meeting current safety standards and requirements for the significantly non-standard nuclear power plant exports can be compounded by financial considerations that may lead to purchases of reactors of various types, from more than one supplier country and with different safety standards and requirements. An examination of these issues points to the necessity and opportunity for effective action which could include provision for adequate funding for safety considerations in the purchase contract, and for sufficient regulatory assistance and training from the developed countries. The article will introduce the topic, discuss specific examples, and offer some suggestions. (author)

Is your electric process heater safe?

Energy Technology Data Exchange (ETDEWEB)

Tiras, C.S.

2000-04-01

Over the past 35 years, electric process heaters (EPHs) have been used to heat flowing fluids in different sectors of the energy industry: oil and gas exploration and production, refineries, petrochemical plants, pipeline compression facilities and power-generation plants. EPHs offer several advantages over fired heaters and shell-and-tube exchangers, which have been around for many years, including: smaller size, lighter weight, cleaner operation, lower capital costs, lower maintenance costs, no emissions or leakage, better control and improved safety. However, while many industrial standards have addressed safety concerns of fired heaters and shell-and-tube exchangers (API, TEMA, NFPA, OSHA and NEC), no standards address EPHs. The paper presents a list of questions that plant operators need to ask about the safety of their electric process heaters. The answers are also given.

Electric power production contra electricity savings

International Nuclear Information System (INIS)

Schleisner, L.; Grohnheit, P.E.; Soerensen, H.

1991-01-01

The expansion of electricity-producing plants has, in Denmark until now, taken place in accordance with the demand for electricity. Recently, it has been suggested that the cost of the further development of such systems is greater than the cost of instigating and carrying out energy conservation efforts. The aim of the project was to evaluate the consequences for power producing plants of a reduction of the electricity consumption of end-users. A method for the analysis of the costs involved in the system and operation of power plants contra the costs that are involved in saving electricity is presented. In developing a model of this kind, consideration is given to the interplay of the individual saving project and the existing or future electricity supply. Thus it can be evaluated to what extent it would be advisable to substitute investments in the development of the capacity of the power plants with investments in the reduction of electricity consumption by the end users. This model is described in considerable detail. It will be tested in representative situations and locations throughout the Nordic countries. (AB) 17 refs

Review of light--water reactor safety studies. Volume 3 of health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

International Nuclear Information System (INIS)

Nero, A.V.; Farnaam, M.R.K.

1977-01-01

This report summarizes and compares important studies of light-water nuclear reactor safety, emphasizing the Nuclear Regulatory Commission's Reactor Safety Study, work on risk assessment funded by the Electric Power Research Institute, and the Report of the American Physical Society study group on light-water reactor safety. These reports treat risk assessment for nuclear power plants and provide an introduction to the basic issues in reactor safety and the needs of the reactor safety research program. Earlier studies are treated more briefly. The report includes comments on the Reactor Safety Study. The manner in which these studies may be used and alterations which would increase their utility are discussed

Vehicle-to-Grid Power in Danish Electric Power Systems

DEFF Research Database (Denmark)

Pillai, Jayakrishnan Radhakrishna; Bak-Jensen, Birgitte

2009-01-01

The integration of renewable energy systems is often constrained by the variable nature of their output. This demands for the services of storing the electricity generated from most of the renewable energy sources. Vehicle-to-grid (V2G) power could use the inherent energy storage of electric...... vehicles and its quick response time to balance and stabilize a power system with fluctuating power. This paper outlines the use of battery electric vehicles in supporting large-scale integration of renewable energy in the Danish electric power systems. The reserve power requirements for a high renewable...... energy penetration could be met by an amount of V2G based electric vehicles less than 10% of the total vehicle need in Denmark. The participation of electric vehicle in ancillary services would earn significant revenues to the vehicle owner. The power balancing services of electric vehicles...

On safety 1E qualification of electrical equipment for nuclear power stations

International Nuclear Information System (INIS)

Segarceanu, D.; Geambasu, C.; Avramescu, M.

1995-01-01

Electrical equipment and systems for the emergency shutdown of a nuclear reactor are qualified according to safety class 1E. Methods of qualification meeting the requirements should be used, either individually or in combination include, type-test qualification, qualification by operating experience, qualification by analysis, combined qualification. These methods qualification principles, procedures and documents are discussed. (N.T.). 1 fig

Nuclear accidents and safety measures of domestic nuclear power plants

International Nuclear Information System (INIS)

Song Zurong; Che Shuwei; Pan Xiang

2012-01-01

Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

Energy management systems on board of electric vehicles, based on power electronics

Energy Technology Data Exchange (ETDEWEB)

Guidi, Giuseppe

2009-03-15

The core of any electric vehicle (EV) is the electric drive train, intended as the energy conversion chain from the energy tank (typically some kind of rechargeable battery) to the electric motor that converts the electrical energy into the mechanical energy needed for the vehicle motion. The need for on-board electrical energy storage is the factor that has so far prevented pure electric vehicles from conquering significant market share. In fact electrochemical batteries, which are currently the most suitable device for electrical energy storage, have serious limitations in terms of energy and/or power density, cost and safety. All those characteristics reflect in pure electric vehicles being outperformed by standard internal combustion engine (ICE) based vehicles in terms of driving range, time needed to refuel and purchase cost. Electric vehicles do have their distinctive advantages, being intrinsically much more efficient, operating at zero emissions at the pipe, and offering a higher degree of controllability that can potentially enhance driving safety. No wonder then, that electric energy storage technology has attracted considerable R&D investments, resulting in new traction battery packs that are getting closer and closer to the industrial targets. In this scenario of EV technology gaining momentum, power electronics engineers have to come up with newer solutions allowing for more efficient and more reliable utilization of the precious on-board energy that comes in a form that cannot be directly utilized by the motor. At present, most of the research in the area of power electronics for automotive is focused in volume and cost reduction techniques. The increase in power density is pursued by developing components that can be operated at higher temperature, thus relieving the requirements on cooling. In this thesis, the focus is on the development of alternative topologies for the power electronics converters that make use of some peculiarities of the energy

Nuclear energy technology innovation and restructuring electric power industry for sustainable development in Korea in 21st century - issues and strategies

International Nuclear Information System (INIS)

Lee, B.W.; Chae, K.N.

2001-01-01

After TMI and Chernobyl accidents, concerns on nuclear safety and radiation health risk from radioactive wastes become the target issues for anti-nuclear. Nevertheless, nuclear power is a substantial contributor to the world electricity production, supplying more than 16 % of global electricity. The objectives of Korean nuclear energy technology innovation are to improve safety, economic competitiveness, energy security and the effectiveness of radioactive waste management in harmony with environment. Meeting such objectives, public concerns on safety and health risks would be cleared. Innovative nuclear energy system will certainly enhance socio-political acceptance and enable wider application of nuclear energy for sustainable development in Korea in the 21st Century. In parallel to such technology innovations, the effective first phase restructuring of electric power industry is in progress to enhance management efficiency and customer services. The power generation division of the former state-run utility, Korea Electric Power Corporation (KEPCO) was separated and divided into six companies - five thermal power and one hydro and nuclear power generation companies - in last April. After the reorganization of KEPCO and the break-up of monopoly, the new electric power industry will be driven by market force. (author)

Performance standards of road safety management

Directory of Open Access Journals (Sweden)

Čabarkapa Milenko R.

2016-01-01

Full Text Available Road safety management controlling means the process of finding out the information whether the road safety is improving in a measure to achieve the objectives. The process of control consists of three basic elements: definition of performances and standards, measurement of current performances and comparison with the set standards, and improvement of current performances, if they deviate from the set standards. The performance standards of road safety management system are focused on a performances measurement, in terms of their design and characteristics, in order to support the performances improvement of road safety system and thus, ultimately, improve the road safety. Defining the performance standards of road safety management system, except that determines the design of the system for performances measurement, directly sets requirements whose fulfillment will produce a road safety improvement. The road safety management system, based on the performance standards of road safety, with a focus on results, will produce the continuous improvement of road safety, achieving the long-term 'vision zero', the philosophy of road safety, that human life and health take priority over mobility and other traffic objectives of the road traffic.