Nuclear power manpower and training requirements

International Nuclear Information System (INIS)

Whan, G.A.

1984-01-01

A broad spectrum of technical personnel is required to conduct a national nuclear power program, predominantly electrical, mechanical, and nuclear engineers and health physicists. The need for nuclear education and training, even in the early planning states, is the topic of this paper. Experience gained in the United States can provide useful information to Asia-Pacific countries developing nuclear power programs. Including both on-site and off-site personnel, U.S. plants average about 570 workers for BWRs and 700 for PWRs. The need for an additional 57,000 technical employees over the next decade is projected. The technical backgrounds of the manpower required to operate and support a nuclear power plant are distinctly different from those used by non-nuclear utilities. Manpower cannot be transferred from fossil fuel plants without extensive training. Meeting the demand for nuclear education and training must be a friendly partnership among universities, government, and industry. The long-term supply of nuclear-educated personnel requires strong, government-supported universities. Most specific training, however, must be provided by industry. (author)

Electrofishing power requirements in relation to duty cycle

Science.gov (United States)

Miranda, L.E.; Dolan, C.R.

2004-01-01

Under controlled laboratory conditions we measured the electrical peak power required to immobilize (i.e., narcotize or tetanize) fish of various species and sizes with duty cycles (i.e., percentage of time a field is energized) ranging from 1.5% to 100%. Electrofishing effectiveness was closely associated with duty cycle. Duty cycles of 10-50% required the least peak power to immobilize fish; peak power requirements increased gradually above 50% duty cycle and sharply below 10%. Small duty cycles can increase field strength by making possible higher instantaneous peak voltages that allow the threshold power needed to immobilize fish to radiate farther away from the electrodes. Therefore, operating within the 10-50% range of duty cycles would allow a larger radius of immobilization action than operating with higher duty cycles. This 10-50% range of duty cycles also coincided with some of the highest margins of difference between the electrical power required to narcotize and that required to tetanize fish. This observation is worthy of note because proper use of duty cycle could help reduce the mortality associated with tetany documented by some authors. Although electrofishing with intermediate duty cycles can potentially increase effectiveness of electrofishing, our results suggest that immobilization response is not fully accounted for by duty cycle because of a potential interaction between pulse frequency and duration that requires further investigation.

Probabilistic safety analysis of DC power supply requirements for nuclear power plants. Technical report

International Nuclear Information System (INIS)

Baranowsky, P.W.; Kolaczkowski, A.M.; Fedele, M.A.

1981-04-01

A probabilistic safety assessment was performed as part of the Nuclear Regulatory Commission generic safety task A-30, Adequacy of Safety Related DC Power Supplies. Event and fault tree analysis techniques were used to determine the relative contribution of DC power related accident sequences to the total core damage probability due to shutdown cooling failures. It was found that a potentially large DC power contribution could be substantially reduced by augmenting the minimum design and operational requirements. Recommendations included (1) requiring DC power divisional independence, (2) improved test, maintenance, and surveillance, and (3) requiring core cooling capability be maintained following the loss of one DC power bus and a single failure in another system

Safety requirements for a nuclear power plant electric power system

Energy Technology Data Exchange (ETDEWEB)

Fouad, L F; Shinaishin, M A

1988-06-15

This work aims at identifying the safety requirements for the electric power system in a typical nuclear power plant, in view of the UNSRC and the IAEA. Description of a typical system is provided, followed by a presentation of the scope of the information required for safety evaluation of the system design and performance. The acceptance and design criteria that must be met as being specified by both regulatory systems, are compared. Means of implementation of such criteria as being described in the USNRC regulatory guides and branch technical positions on one hand and in the IAEA safety guides on the other hand are investigated. It is concluded that the IAEA regulations address the problems that may be faced with in countries having varying grid sizes ranging from large stable to small potentially unstable ones; and that they put emphasis on the onsite standby power supply. Also, in this respect the Americans identify the grid as the preferred power supply to the plant auxiliaries, while the IAEA leaves the possibility that the preferred power supply could be either the grid or the unit main generator depending on the reliability of each. Therefore, it is found that it is particularly necessary in this area of electric power supplies to deal with the IAEA and the American sets of regulations as if each complements and not supplements the other. (author)

Power supply requirements for a tokamak fusion reactor

International Nuclear Information System (INIS)

Brooks, J.N.; Kustom, R.L.

1979-02-01

The power supply requirements for a 7-M major radius commercial tokamak reactor have been examined, using a system approach combining models of the reactor and poloidal coil set, plasma burn cycle and MHD calculations, and power supply characteristics and cost data. A conventional system using an MGF set and solid-state rectifier/inverter power supplies was studied in addition to systems using a homopolar generator, superconducting energy storage inductor, and dump resistors. The requirements and cost of the power supplies depend on several factors but most critically on the ohmic heating ramp time used for startup. Long ramp times (approx. > 8 s) seems to be feasible, from the standpoint of resistive volt-second losses, and would appear to make conventional systems quite competitive with nonconventional ones, which require further research and development

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

46 CFR 111.10-4 - Power requirements, generating sources.

Science.gov (United States)

2010-10-01

... ELECTRIC SYSTEMS-GENERAL REQUIREMENTS Power Supply § 111.10-4 Power requirements, generating sources. (a) The aggregate capacity of the electric ship's service generating sources required in § 111.10-3 must... or sources must be sufficient to supply those services necessary to provide normal operational...

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.

Beam heating requirements for a tokamak experimental power reactor

International Nuclear Information System (INIS)

Bertoncini, P.J.; Brooks, J.N.; Fasolo, J.A.; Stacey, W.M. Jr.

1976-01-01

Typical beam heating requirements for effective tokamak experimental power reactor (TEPR) operation have been studied in connection with the Argonne preliminary conceptual TEPR design. For an ignition level plasma (approximately 100 MWt fusion power) for the nominal case envisioned, the neutral beam is only used to heat the plasma to ignition. This typically requires a beam power output of 40 MW at 180 keV for about 3 sec with a total energy of 114 MJ supplied to the plasma. The beam requirements for an ignition device are not very sensitive to changes in wall-sputtered impurity levels or plasma resistivity. For a plasma that must be driven due to poor confinement, the beam must remain on for most of the burn cycle. For representative cases, beam powers of approximately 23 MW are required for a total on-time of 20 to 50 sec. Reqirements on power level, beam energy, on-time, and beam-generation efficiency all represent considerable advances over present technology. For the Argonne TEPR design, a total of 16 to 32 beam injectors is envisioned. For a 40-MW, 180-keV, one-component beam, each injector supplies about 7 to 14 A of neutrals to the plasma. For positive ion sources, about 50 to 100 A of ions are required per injector and some form of particle and/or energy recycling appears to be essential in order to meet the power and efficiency requirements

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

18 CFR 35.37 - Market power analysis required.

Science.gov (United States)

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Market power analysis required. 35.37 Section 35.37 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY... Wholesale Sales of Electric Energy, Capacity and Ancillary Services at Market-Based Rates § 35.37 Market...

Grid Code Requirements for Wind Power Integration

DEFF Research Database (Denmark)

Wu, Qiuwei

2018-01-01

This chapter reviews the grid code requirements for integration of wind power plants (WPPs). The grid codes reviewed are from the UK, Ireland, Germany, Denmark, Spain, Sweden, the USA, and Canada. Transmission system operators (TSOs) around the world have specified requirements for WPPs under...

FLECH PowerMax Service Requirement Specification

DEFF Research Database (Denmark)

It is expected that in the future, ancillary services will be required at distribution level. This work describes how one of these ancillary services, the PowerMax service, must be spec ified within a market framework. The basis of this work is the Flexibility Clearing House (FLE CH) platform...... and the Distribution System Operator (DSO) services defined in [1]. The PowerMax service has been further discussed in [2], and this technical report seeks to clarify the implementation details first discussed in that paper. The aim of the PowerMax service it to relieve congestion issue s in the distribution system...... by establishing a maximum power that a cluster of consumer devices may draw from the syste m. The consumers will receive a payment for providing this service, and the DSO will be able to postpone grid reinfo rcement...

When Power Shapes Interpersonal Behavior: Low Relationship Power Predicts Men’s Aggressive Responses to Low Situational Power

Science.gov (United States)

Overall, Nickola C.; Hammond, Matthew D.; McNulty, James K.; Finkel, Eli J.

2016-01-01

When does power in intimate relationships shape important interpersonal behaviors, such as psychological aggression? Five studies tested whether possessing low relationship power was associated with aggressive responses, but (1) only within power-relevant relationship interactions when situational power was low, and (2) only by men because masculinity (but not femininity) involves the possession and demonstration of power. In Studies 1 and 2, men lower in relationship power exhibited greater aggressive communication during couples’ observed conflict discussions, but only when they experienced low situational power because they were unable to influence their partner. In Study 3, men lower in relationship power reported greater daily aggressive responses toward their partner, but only on days when they experienced low situational power because they were either (a) unable to influence their partner or (b) dependent on their partner for support. In Study 4, men who possessed lower relationship power exhibited greater aggressive responses during couples’ support-relevant discussions, but only when they had low situational power because they needed high levels of support. Study 5 provided evidence for the theoretical mechanism underlying men’s aggressive responses to low relationship power. Men who possessed lower relationship power felt less manly on days they faced low situational power because their partner was unwilling to change to resolve relationship problems, which in turn predicted greater aggressive responses to their partner. These results demonstrate that fully understanding when and why power is associated with interpersonal behavior requires differentiating between relationship and situational power. PMID:27442766

International power projections and capital requirements

International Nuclear Information System (INIS)

Ann, H.

1989-01-01

This work is related to the international power projections and capital requirements of all kinds of energy and the share of electricity. It is also related to the so-called greenhouse effect carbon dioxide concentration in atmosphere. (A.C.A.S.)

Implications of fusion power plant studies for materials requirements

International Nuclear Information System (INIS)

Cook, Ian; Ward, David; Dudarev, Sergei

2002-01-01

This paper addresses the key requirements for fusion materials, as these have emerged from studies of commercial fusion power plants. The objective of the international fusion programme is the creation of power stations that will have very attractive safety and environmental features and viable economics. Fusion power plant studies have shown that these objectives may be achieved without requiring extreme advances in materials. But it is required that existing candidate materials perform at least as well as envisaged in the environment of fusion neutrons, heat fluxes and particle fluxes. The development of advanced materials would bring further benefits. The work required entails the investigation of many intellectually exciting physics issues of great scientific interest, and of wider application than fusion. In addition to giving an overview, selected aspects of the science, of particular physics interest, are illustrated

Manpower requirements for nuclear power in developing countries

International Nuclear Information System (INIS)

Csik, B.J.

1980-01-01

It is recognized that each country has its individual unique characteristics and that there is no typical or average developing country. Common conditions represent exceptions, rather than the rule. Manpower requirements, however, are created by the tasks to be performed and activities to be carried out at each definite stage of a nuclear power project or programme. These tasks and activities, as well as the manpower requirements they create, are of a similar nature for any country, subject to the influence of prevailing local conditions. First, successive stages of the evolution of a nuclear power programme are defined. These are: pre-planning, planning, study and procurement, construction, operation of the first plant, confirmed and self-sufficient in implementing nuclear power projects. The developing countries are then classified according to the present stage of their evolution. Finally, the present and future manpower requirements of each country or group of countries are estimated. No attempt has been made to try to establish any precise data for any country in particular. The results obtained are global estimates, intended as indications of trends and of orders of magnitude. It is found that the developing world's present manpower requirements for nuclear power are of the order of 100,000 people, of which about 20,000 need specialized nuclear training. By the year 2000, for an installed nuclear capacity of 150 to 200 GW, overall manpower requirements should increase to more than 500,000 which would include 130,000 with specialized nuclear training. (author)

National Maglev initiative: California line electric utility power system requirements

Science.gov (United States)

Save, Phil

1994-01-01

The electrical utility power system requirements were determined for a Maglev line from San Diego to San Francisco and Sacramento with a maximum capacity of 12,000 passengers an hour in each direction at a speed of 300 miles per hour, or one train every 30 seconds in each direction. Basically the Maglev line requires one 50-MVA substation every 12.5 miles. The need for new power lines to serve these substations and their voltage levels are based not only on equipment loading criteria but also on limitations due to voltage flicker and harmonics created by the Maglev system. The resulting power system requirements and their costs depend mostly on the geographical area, urban or suburban with 'strong' power systems, or mountains and rural areas with 'weak' power systems. A reliability evaluation indicated that emergency power sources, such as a 10-MW battery at each substation, were not justified if sufficient redundancy is provided in the design of the substations and the power lines serving them. With a cost of $5.6 M per mile, the power system requirements, including the 12-kV DC cables and the inverters along the Maglev line, were found to be the second largest cost component of the Maglev system, after the cost of the guideway system ($9.1 M per mile), out of a total cost of $23 M per mile.

Space nuclear power requirements for ozone layer modification

International Nuclear Information System (INIS)

Dolan, T.J.

1991-01-01

This work estimates the power requirements for using photochemical processes driven by space nuclear power to counteract the Earth's ozone layer depletion. The total quantity of ozone (O 3 ) in the Earth's atmosphere is estimated to be about 4.7 x 10 37 molecules. The ozone production and destruction rates in the stratosphere are both on the order of 4.9 x 10 31 molecules/s, differing by a small fraction so that the net depletion rate is about 0.16 to 0.26% per year. The delivered optical power requirement for offsetting this depletion is estimated to be on the order of 3 GW. If the power were produced by satellite reactors at 800 km altitude (orbit decay time ∼ 300 years), some means of efficient power beaming would be needed to deliver the power to stratospheric levels (10--50 km). Ultraviolet radiation at 140--150 nm could have higher absorption rates in O 2 (leading to production of atomic oxygen, which can combine with O 2 to form O 3 ) than in ozone (leading to photodissociation of O 3 ). Potential radiation sources include H 2 lasers and direct nuclear pumping of ultraviolet fluorescers. 5 refs

Nuclear space power and propulsion requirements and issues

International Nuclear Information System (INIS)

Swerdling, M.; Isenberg, L.

1995-01-01

The use of nuclear power in space is going through a low point. The kinds of missions that would use nuclear power are expensive and there are few new expensive missions. Both NASA and DoD are in a mode of cheaper, faster, better, which means using what is available as much as possible and only incorporating new technology to reduce mission cost. NASA is performing Mission to Planet Earth and detailed exploration missions of Mars. These NASA missions can be done with solar-battery power subsystems and there is no need for nuclear power. The NASA mission to Pluto does require nuclear radioisotope power. Ways to reduce the power subsystem cost and the power level are being investigated. NASA is studying ways to explore beyond Mars with solar-battery power because of the cost and uncertainty in the availability and launchability of nuclear space power systems. The DoD missions are all in earth orbit and can be done with solar-battery systems. The major DoD requirement at present is to reduce costs of all their space missions. One way to do this is to develop highly efficient upper stage boosters that can be integrated with lower cost Earth to low orbit stages and still place their payloads in to higher orbits. One attractive upper stage is a nuclear bimodal (propulsion and power) engine to accomplished lower booster cost to place space assets in GEO. However this is not being pursued because of DOE's new policy not to fund nuclear space power research and development as well as the difficulty in obtaining launch approval for nuclear propulsion and power systems

Reduced power processor requirements for the 30-cm diameter HG ion thruster

Science.gov (United States)

Rawlin, V. K.

1979-01-01

The characteristics of power processors strongly impact the overall performance and cost of electric propulsion systems. A program was initiated to evaluate simplifications of the thruster-power processor interface requirements. The power processor requirements are mission dependent with major differences arising for those missions which require a nearly constant thruster operating point (typical of geocentric and some inbound planetary missions) and those requiring operation over a large range of input power (such as outbound planetary missions). This paper describes the results of tests which have indicated that as many as seven of the twelve power supplies may be eliminated from the present Functional Model Power Processor used with 30-cm diameter Hg ion thrusters.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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 (Russian Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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.

Nuclear power technology requirements for NASA exploration missions

International Nuclear Information System (INIS)

Bloomfield, H.S.

1990-01-01

This paper discusses how future exploration of the Moon and Mars will mandate developments in many areas of technology. In particular, major advances will be required in planet surface power systems and space transportation systems. Critical nuclear technology challenges that can enable strategic self-sufficiency, acceptable operational costs and cost-effective space transportation goals for NASA exploration missions have been identified. Critical technologies for surface power systems include stationary and mobile nuclear reactor and radio-isotope heat sources coupled to static and dynamic power conversion devices. These technologies can provide dramatic reductions in mass leading to operational and transportation cost savings. Critical technologies for space transportation systems include nuclear thermal rocket and nuclear electric propulsion options which present compelling concepts for significantly reducing mass, cost or travel time required for Earth-Mars transport

Greater-than-Class C low-level radioactive waste transportation regulations and requirements study

International Nuclear Information System (INIS)

Tyacke, M.; Schmitt, R.

1993-07-01

The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively

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

International Nuclear Information System (INIS)

2017-01-01

This publication establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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.

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

International Nuclear Information System (INIS)

2017-01-01

This publication establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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.

Grid code requirements for wind power generation

International Nuclear Information System (INIS)

Djagarov, N.; Filchev, S.; Grozdev, Z.; Bonev, M.

2011-01-01

In this paper production data of wind power in Europe and Bulgaria and plans for their development within 2030 are reviewed. The main characteristics of wind generators used in Bulgaria are listed. A review of the grid code in different European countries, which regulate the requirements for renewable sources, is made. European recommendations for requirements harmonization are analyzed. Suggestions for the Bulgarian gird code are made

Safety and regulatory requirements of nuclear power plants

International Nuclear Information System (INIS)

Kumar, S.V.; Bhardwaj, S.A.

2000-01-01

A pre-requisite for a nuclear power program in any country is well established national safety and regulatory requirements. These have evolved for nuclear power plants in India with participation of the regulatory body, utility, research and development (R and D) organizations and educational institutions. Prevailing international practices provided a useful base to develop those applicable to specific system designs for nuclear power plants in India. Their effectiveness has been demonstrated in planned activities of building up the nuclear power program as well as with unplanned activities, like those due to safety related incidents etc. (author)

18 CFR 284.504 - Standard requirements for market-power authorizations.

Science.gov (United States)

2010-04-01

... Commission within 10 days of acquiring knowledge of significant changes occurring in its market power status... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Standard requirements for market-power authorizations. 284.504 Section 284.504 Conservation of Power and Water Resources...

Variable Resistance Training Promotes Greater Strength and Power Adaptations Than Traditional Resistance Training in Elite Youth Rugby League Players.

Science.gov (United States)

Rivière, Maxence; Louit, Loic; Strokosch, Alasdair; Seitz, Laurent B

2017-04-01

Rivière, M, Louit, L, Strokosch, A, and Seitz, LB. Variable resistance training promotes greater strength and power adaptations than traditional resistance training in elite youth rugby league players. J Strength Cond Res 31(4): 947-955, 2017-The purpose of this study was to examine the strength, velocity, and power adaptations in youth rugby league players in response to a variable resistance training (VRT) or traditional free-weight resistance training (TRAD) intervention. Sixteen elite youth players were assigned to a VRT or TRAD group and completed 2 weekly upper- and lower-body strength and power sessions for 6 weeks. Training programs were identical except that the VRT group trained the bench press exercise with 20% of the prescribed load coming from elastic bands. Bench press 1 repetition maximum (1RM) and bench press mean velocity and power at 35, 45, 65, 75, and 85% of 1RM were measured before and after the training intervention, and the magnitude of the changes was determined using effect sizes (ESs). The VRT group experienced larger increases in both absolute (ES = 0.46 vs. 0.20) and relative (ES = 0.41 vs. 0.19) bench press 1RM. Similar results were observed for mean velocity as well as both absolute and relative mean power at 35, 45, 65, 75, and 85% of 1RM. Furthermore, both groups experienced large gains in both velocity and power in the heavier loads but small improvements in the lighter loads. The improvements in both velocity and power against the heavier loads were larger for the VRT group, whereas smaller differences existed between the 2 groups in the lighter loads. Variable resistance training using elastic bands may offer a greater training stimulus than traditional free-weight resistance training to improve upper-body strength, velocity, and power in elite youth rugby league players.

Power system requirements and selection for the space exploration initiative

International Nuclear Information System (INIS)

Biringer, K.L.; Bartine, D.E.; Buden, D.; Foreman, J.; Harrison, S.

1991-01-01

The Space Exploration Initiative (SEI) seeks to reestablish a US program of manned and unmanned space exploration. The President has called for a program which includes a space station element, a manned habitation of the moon, and a human exploration of Mars. The NASA Synthesis Group has developed four significantly different architectures for the SEI program. One key element of a space exploration effort is the power required to support the missions. The Power Speciality Team of the Synthesis Group was tasked with assessing and evaluating the power requirements and candidate power technologies for such missions. Inputs to the effort came from existing NASA studies as well as other governments agency inputs such as those from DOD and DOE. In addition, there were industry and university briefings and results of solicitations from the AIAA and the general public as part of the NASA outreach effort. Because of the variety of power needs in the SEI program, there will be a need for multiple power system technologies including solar, nuclear and electrochemical. Due to the high rocket masses required to propel payloads to the moon and beyond to Mars, there is great emphasis placed on the need for high power density and high energy density systems. Power system technology development work is needed results will determine the ultimate technology selections. 23 refs., 10 figs

VGB-requirements regarding technical data for power plants

International Nuclear Information System (INIS)

Richnow, Joerg

2009-01-01

Much of the technical plant data resulting from the planning, construction and start-up of power plants is needed for subsequent management and maintenance. Because of this, VGB has taken the initiative and has defined standard minimum requirements from power plant operators for technical plant data. They relate to the details and structure of this data, the definition of material classes and characteristics for the main power plant components and IT implementation for delivery of the technical plant data. (orig.)

Requirements Specication for Ampliers and Power Supplies in Active Loudspeakers

DEFF Research Database (Denmark)

Schneider, Henrik; Jensen, Lasse Crone; Petersen, Lars Press

2014-01-01

This work aims to provide designers with a method to develop a requirements specication for power supplies and ampliers in active loudspeakers. The motivation is to avoid over-sizing and unnecessary cost. A realistic estimation of the power supplied during playback of audio in a given loudspeaker...... is obtained by considering a wide range of audio source material, loudness normalization of the source material, crossover ltering, driver characteristics as well as a perceived maximum loudness/volume level. The results from analysing a sub-woofer and a woofer reveals the peak power, peak voltage, peak...... current and apparent power - thus providing a solid foundation for a requirement specication....

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.

Neutronics requirements for a DEMO fusion power plant

Energy Technology Data Exchange (ETDEWEB)

Fischer, U., E-mail: ulrich.fischer@kit.edu [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Bachmann, C. [EUROfusion Consortium , Boltzmannstraße 2, 85748 Garching (Germany); Palermo, I. [Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Madrid (Spain); Pereslavtsev, P. [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Villari, R. [ENEA UT-FUS C.R. Frascati, Via E. Fermi 45, 00044 Frascati (Italy)

2015-10-15

Highlights: • Discussion and specification of neutronic requirements for a DEMO power plant. • TBR uncertainties are reviewed/discussed and design margins are elaborated. • Limits are given for radiation loads to super-conducting magnets and steel structural components. • Available DEMO results are compared to recommended limits and TBR design target. - Abstract: This paper addresses the neutronic requirements a DEMO fusion power plant needs to fulfil for a reliable and safe operation. The major requirement is to ensure Tritium self-sufficiency taking into account the various uncertainties and plant-internal losses that occur during DEMO operation. A further major requirement is to ensure sufficient protection of the superconducting magnets against the radiation penetrating in-vessel components and vessel. Reliable criteria for the radiation loads need to be defined and verified to ensure the reliable operation of the magnets over the lifetime of DEMO. Other issues include radiation induced effects on structural materials such as the accumulated displacement damage, the generation of gases such as helium which may deteriorate the material performance. The paper discusses these issues and their impact on design options for DEMO taking into account results obtained in the frame of European Power Plant Physics and Technology (PPPT) 2013 programme activities with DEMO models employing the helium cooled pebble bed (HCPB), the helium cooled lithium lead (HCLL), and the water-cooled (WCLL) blanket concepts.

Use of fuel cells to meet military requirements for mobile power

International Nuclear Information System (INIS)

Andrukaitis, E.

2004-01-01

'Full text:' The use of fuel cell technology in military applications will depend on safe, high energy density systems being developed. An important part of using this technology is also the development of alternative hydrogen producing fuels with high energy densities and are easy to transport. Fuel cells are now a very large R and D effort for several military applications around the world. The major reason is because of the high power demands needed requires electrical energy sources that far exceed the capabilities of batteries currently being fielded for portable applications. Fuel cells are regarded as highly efficient, tactical energy converters that can be adapted for wide range of power requirements. They are potentially the lowest weight power source when coupled with batteries or capacitors to form hybrid systems. Generally electrical power is needed to support a number of applications from ultra-high power for electrical pulses (radios, sensors) to reliable, conditioned power for command and control systems. In the future, sustained power for electric drive systems, will also be required. Some of the promising applications in the military and the R and D challenges that remain to reach performance and reliability targets suitable for military requirements will be discussed. (author)

Power requirements assessment for lunar and Mars scientific and experimental payloads

International Nuclear Information System (INIS)

Kotas, J.F.

1992-01-01

This paper reports on an evaluation of prospective scientific payloads and surface experiments for future manned missions to the moon and Mars which determined that overall mission objectives and requirements influence the selection of candidate power systems. A generic classification of these science missions was developed to examine these relationships. Scientific missions were defined for the four Synthesis Report architectures and cumulative power load and payload mix computed. Approximately half of all deployed science payloads were sited within the main surface outpost and powered by the central power generation facility. The remaining remote science payloads require either autonomous or smaller central power facilities

10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

Science.gov (United States)

2010-01-01

... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license... 10 Energy 2 2010-01-01 2010-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF...

International comparison of requirements for connection of wind turbines to power systems

Energy Technology Data Exchange (ETDEWEB)

Jauch, C. [Risoe National Lab., Roskilde (Denmark). Dept. of Wind Energy; Matevosyan, J.; Ackermann, T. [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Electrical Engineering; Bolik, S. [Vestas Wind Systems A/S, Ringkoebing (Denmark)

2005-07-01

Power production from wind turbines has increased considerably during the last decade. Therefore today's wind turbines, which are typically set up in wind farms, have a significant influence on the operation of power systems. The efficient and secure operation of power systems is supported by grid codes, which are sets of requirements for all network users (suppliers, customers, etc.). In Europe, several transmission network operators have introduced special grid connection requirements for wind farms. These requirements are mainly based on existing grid codes, initially written for conventional power plants usually equipped with synchronous generators. This article presents a comparison of grid connection requirements for wind farms issued, or proposed as a draft, by transmission network operators in Denmark, Sweden, Germany, Scotland and Ireland. (author)

Energy Storage Requirements for PV Power Ramp Rate Control in Northern Europe

Directory of Open Access Journals (Sweden)

Julius Schnabel

2016-01-01

Full Text Available Photovoltaic (PV generators suffer from fluctuating output power due to the highly fluctuating primary energy source. With significant PV penetration, these fluctuations can lead to power system instability and power quality problems. The use of energy storage systems as fluctuation compensators has been proposed as means to mitigate these problems. In this paper, the behavior of PV power fluctuations in Northern European climatic conditions and requirements for sizing the energy storage systems to compensate them have been investigated and compared to similar studies done in Southern European climate. These investigations have been performed through simulations that utilize measurements from the Tampere University of Technology solar PV power station research plant in Finland. An enhanced energy storage charging control strategy has been developed and tested. Energy storage capacity, power, and cycling requirements have been derived for different PV generator sizes and power ramp rate requirements. The developed control strategy leads to lesser performance requirements for the energy storage systems compared to the methods presented earlier. Further, some differences on the operation of PV generators in Northern and Southern European climates have been detected.

Greater autonomy at work

NARCIS (Netherlands)

Houtman, I.L.D.

2004-01-01

In the past 10 years, workers in the Netherlands increasingly report more decision-making power in their work. This is important for an economy in recession and where workers face greater work demands. It makes work more interesting, creates a healthier work environment, and provides opportunities

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

Current trends in codal requirements for safety in operation of nuclear power plants

International Nuclear Information System (INIS)

Srivasista, K.; Shah, Y.K.; Gupta, S.K.

2006-01-01

The Code of practice on safety in nuclear power plant operation states the requirements to be met during operation of a nuclear power plant for assuring safety. Among various stages of authorization, regulatory body issues authorization for operation of a nuclear power plant, monitors and enforces regulatory requirements. The responsible organization shall have overall responsibility and the plant management shall have the primary responsibility for ensuring safe and efficient operation of its nuclear power plants. A set of codal requirements covering technical and administrative aspects are mandatory for the plant management to implement to ensure that the nuclear power plant is operated in accordance with the design intent. Requirements on operating procedures and instructions establish operation and maintenance, inspection and testing of the plant in a planned and systematic way. The requirements on emergency preparedness programme establish with a reasonable assurance that, in the event of an emergency situation, appropriate measures can be taken to mitigate the consequences. Commissioning requirements verify performance criteria during commissioning to ensure that the design intent and QA requirements are met. Several modifications in systems important to safety required during operation of a nuclear power plant are regulated. However new operational codal requirements arising out of periodic safety review, operational experience feedback, life management, probabilistic safety assessment, physical security, safety convention and obligations and decommissioning are not covered in the present code of practice for safety in nuclear power plant operation. Codal provisions on 'Review by operating organization on aspects of design having implications on operability' are also required to be addressed. The merits in developing such a methodology include acceptance of the design by operating organization, ensuring maintainability, proper layout etc. in the new designs

Estimates of power requirements for a Manned Mars Rover powered by a nuclear reactor

Science.gov (United States)

Morley, Nicholas J.; El-Genk, Mohamed S.; Cataldo, Robert; Bloomfield, Harvey

1991-01-01

This paper assesses the power requirement for a Manned Mars Rover vehicle. Auxiliary power needs are fulfilled using a hybrid solar photovoltaic/regenerative fuel cell system, while the primary power needs are meet using an SP-100 type reactor. The primary electric power needs, which include 30-kW(e) net user power, depend on the reactor thermal power and the efficiency of the power conversion system. Results show that an SP-100 type reactor coupled to a Free Piston Stirling Engine yields the lowest total vehicle mass and lowest specific mass for the power system. The second lowest mass was for a SP-100 reactor coupled to a Closed Brayton Cycle using He/Xe as the working fluid. The specific mass of the nuclear reactor power system, including a man-rated radiation shield, ranged from 150-kg/kW(e) to 190-kg/KW(e) and the total mass of the Rover vehicle varied depend upon the cruising speed.

RF Power Requirements for PEFP SRF Cavity Test

International Nuclear Information System (INIS)

Kim, Han Sung; Seol, Kyung Tae; Kwon, Hyeok Jung; Cho, Yong Sub

2011-01-01

For the future extension of the PEFP (Proton Engineering Frontier Project) Proton linac, preliminary study on the SRF (superconducting radio-frequency) cavity is going on including a five-cell prototype cavity development to confirm the design and fabrication procedures and to check the RF and mechanical properties of a low-beta elliptical cavity. The main parameters of the cavity are like followings. - Frequency: 700 MHz - Operating mode: TM010 pi mode - Cavity type: Elliptical - Geometrical beta: 0.42 - Number of cells: 5 - Accelerating gradient: 8 MV/m - Epeak/Eacc: 3.71 - Bpeak/Eacc: 7.47 mT/(MV/m) - R/Q: 102.3 ohm - Epeak: 29.68 MV/m (1.21 Kilp.) - Geometrical factor: 121.68 ohm - Cavity wall thickness: 4.3 mm - Stiffening structure: Double ring - Effective length: 0.45 m For the test of the cavity at low temperature of 4.2 K, many subsystems are required such as a cryogenic system, RF system, vacuum system and radiation shielding. RF power required to generate accelerating field inside cavity depends on the RF coupling parameters of the power coupler and quality factor of the SRF cavity and the quality factor itself is affected by several factors such as operating temperature, external magnetic field level and surface condition. Therefore, these factors should be considered to estimate the required RF power for the SRF cavity test

Compiling Utility Requirements For New Nuclear Power Plant Project

International Nuclear Information System (INIS)

Patrakka, Eero

2002-01-01

Teollisuuden Voima Oy (TVO) submitted in November 2000 to the Finnish Government an application for a Decision-in-Principle concerning the construction of a new nuclear power plant in Finland. The actual investment decision can be made first after a positive decision has been made by the Government and the Parliament. Parallel to the licensing process, technical preparedness has been upheld so that the procurement process can be commenced without delay, when needed. This includes the definition of requirements for the plant and preliminary preparation of bid inquiry specifications. The core of the technical requirements corresponds to the specifications presented in the European Utility Requirement (EUR) document, compiled by major European electricity producers. Quite naturally, an amount of modifications to the EUR document are needed that take into account the country- and site-specific conditions as well as the experiences gained in the operation of the existing NPP units. Along with the EUR-related requirements concerning the nuclear island and power generation plant, requirements are specified for scope of supply as well as for a variety of issues related to project implementation. (author)

Power Consumption and Calculation Requirement Analysis of AES for WSN IoT.

Science.gov (United States)

Hung, Chung-Wen; Hsu, Wen-Ting

2018-05-23

Because of the ubiquity of Internet of Things (IoT) devices, the power consumption and security of IoT systems have become very important issues. Advanced Encryption Standard (AES) is a block cipher algorithm is commonly used in IoT devices. In this paper, the power consumption and cryptographic calculation requirement for different payload lengths and AES encryption types are analyzed. These types include software-based AES-CB, hardware-based AES-ECB (Electronic Codebook Mode), and hardware-based AES-CCM (Counter with CBC-MAC Mode). The calculation requirement and power consumption for these AES encryption types are measured on the Texas Instruments LAUNCHXL-CC1310 platform. The experimental results show that the hardware-based AES performs better than the software-based AES in terms of power consumption and calculation cycle requirements. In addition, in terms of AES mode selection, the AES-CCM-MIC64 mode may be a better choice if the IoT device is considering security, encryption calculation requirement, and low power consumption at the same time. However, if the IoT device is pursuing lower power and the payload length is generally less than 16 bytes, then AES-ECB could be considered.

Lift and Power Required for Flapping Wing Hovering Flight on Mars

Science.gov (United States)

Pohly, Jeremy; Sridhar, Madhu; Bluman, James; Kang, Chang-Kwon; Landrum, D. Brian; Fahimi, Farbod; Aono, Hikaru; Liu, Hao

2017-11-01

Achieving flight on Mars is challenging due to the ultra-low density atmosphere. Bio-inspired flapping motion can generate sufficient lift if bumblebee-inspired wings are scaled up between 2 and 4 times their nominal size. However, due to this scaling, the inertial power required to sustain hover increases and dominates over the aerodynamic power. Our results show that a torsional spring placed at the wing root can reduce the flapping power required for hover by efficiently storing and releasing energy while operating at its resonance frequency. The spring assisted reduction in flapping power is demonstrated with a well-validated, coupled Navier-Stokes and flight dynamics solver. The total power is reduced by 79%, whereas the flapping power is reduced by 98%. Such a reduction in power paves the way for an efficient, realizable micro air vehicle capable of vertical takeoff and landing as well as sustained flight on Mars. Alabama Space Grant Consortium Fellowship.

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.

Supplying the power requirements to a sensor network using radio frequency power transfer.

Science.gov (United States)

Percy, Steven; Knight, Chris; Cooray, Francis; Smart, Ken

2012-01-01

Wireless power transmission is a method of supplying power to small electronic devices when there is no wired connection. One way to increase the range of these systems is to use a directional transmitting antenna, the problem with this approach is that power can only be transmitted through a narrow beam and directly forward, requiring the transmitter to always be aligned with the sensor node position. The work outlined in this article describes the design and testing of an autonomous radio frequency power transfer system that is capable of rotating the base transmitter to track the position of sensor nodes and transferring power to that sensor node. The system's base station monitors the node's energy levels and forms a charge queue to plan charging order and maintain energy levels of the nodes. Results show a radio frequency harvesting circuit with a measured S11 value of -31.5 dB and a conversion efficiency of 39.1%. Simulation and experimentation verified the level of power transfer and efficiency. The results of this work show a small network of three nodes with different storage types powered by a central base node.

Supplying the Power Requirements to a Sensor Network Using Radio Frequency Power Transfer

Directory of Open Access Journals (Sweden)

Steven Percy

2012-06-01

Full Text Available Wireless power transmission is a method of supplying power to small electronic devices when there is no wired connection. One way to increase the range of these systems is to use a directional transmitting antenna, the problem with this approach is that power can only be transmitted through a narrow beam and directly forward, requiring the transmitter to always be aligned with the sensor node position. The work outlined in this article describes the design and testing of an autonomous radio frequency power transfer system that is capable of rotating the base transmitter to track the position of sensor nodes and transferring power to that sensor node. The system’s base station monitors the node’s energy levels and forms a charge queue to plan charging order and maintain energy levels of the nodes. Results show a radio frequency harvesting circuit with a measured S11 value of −31.5 dB and a conversion efficiency of 39.1%. Simulation and experimentation verified the level of power transfer and efficiency. The results of this work show a small network of three nodes with different storage types powered by a central base node.

Forecast of wind energy production and ensuring required balancing power

International Nuclear Information System (INIS)

Merkulov, M.

2010-01-01

The wind energy is gaining larger part of the energy mix around the world as well as in Bulgaria. Having in mind the irregularity of the wind, we are in front of a challenge for management of the power grid in new unknown conditions. The world's experience has proven that there could be no effective management of the grid without forecasting tools, even with small scale of wind power penetration. Application of such tools promotes simple management of large wind energy production and reduction of the quantities of required balancing powers. The share of the expenses and efforts for forecasting of the wind energy is incomparably small in comparison with expenses for keeping additional powers in readiness. The recent computers potential allow simple and rapid processing of large quantities of data from different sources, which provides required conditions for modeling the world's climate and producing sophisticated forecast. (author)

International environmental issues and requirements for new power projects

Energy Technology Data Exchange (ETDEWEB)

Newman, J.R. [Golder Associates Inc., Gainesville, FL (United States); Maltby, J.H. [Golder Associates Inc., Washington, DC (United States)

1997-12-31

The purpose of this presentation was to discuss the emerging role of financial entities in determining environmental requirements for international power projects. The paper outlines the following: emerging conditions; examples of announced privatization energy projects by country; types of government and international financial entity sources; problems for IPPs; similarity and differences between the World Bank and the USEPA; comparison of the international standards and regulations for power plants; recent trends/issues involving international power project approval; and recommendations for understanding/expediting the financial entities` environmental approval process and how to expedite this process.

Bruce Power's nuclear pressure boundary quality assurance program requirements, implementation and transition

International Nuclear Information System (INIS)

Krane, J.C.

2009-01-01

The development of a full scope nuclear pressure boundary quality assurance program in Canada requires extensive knowledge of the structure and detailed requirements of codes and standards published by the Canadian Standards Association (CSA) and American Society of Mechanical Engineers (ASME). Incorporation into company governance documents and implementation of these requirements while managing the transition to more recent revisions of these codes and standards represents a significant challenge for Bruce Power, Canada's largest independent nuclear operator. This paper explores the key developments and innovative changes that are used to ensure successful regulatory compliance and effective implementation of the Bruce Power Pressure Boundary Quality Assurance Program. Challenges and mitigating strategies to sustain this large compliance based program at Bruce Power's 8 unit nuclear power plant site will also be detailed. (author)

Requirements under decree 430 UJD for unit outlet and standby power supply

International Nuclear Information System (INIS)

Vanco, K.

2012-01-01

At present, the nuclear power plants are only sufficient resources, which can cover a huge demand for electricity. Concentration so huge power in one place require adequate security from the perspective lead power outlet and standby power supply of reactor unit. (Author)

Regulatory requirement of the Juragua nuclear Power Plant PSA

International Nuclear Information System (INIS)

Valhuerdi Debesa, C.

1996-01-01

Probabilistic Safety Assessment has proved to be a powerful tool for improving the knowledge of the safety insides of Nuclear Power Plants and increasing the efficiency of the safety measures adopted by both operators and regulators. In this paper the regulatory approach adopted in Cuba with regard to the PSA , the scope of the requirement and the basis and proposal of this decision are presented

Power requirements for superior H-mode confinement on Alcator C-Mod: experiments in support of ITER

International Nuclear Information System (INIS)

Hughes, J.W.; Reinke, M.L.; Terry, J.L.; Brunner, D.; Greenwald, M.; Hubbard, A.E.; LaBombard, B.; Lipschultz, B.; Ma, Y.; Wolfe, S.; Wukitch, S.J.; Loarte, A.

2011-01-01

Power requirements for maintaining sufficiently high confinement (i.e. normalized energy confinement time H 98 ≥ 1) in H-mode and its relation to H-mode threshold power scaling, P th , are of critical importance to ITER. In order to better characterize these power requirements, recent experiments on the Alcator C-Mod tokamak have investigated H-mode properties, including the edge pedestal and global confinement, over a range of input powers near and above P th . In addition, we have examined the compatibility of impurity seeding with high performance operation, and the influence of plasma radiation and its spatial distribution on performance. Experiments were performed at 5.4 T at ITER relevant densities, utilizing bulk metal plasma facing surfaces and an ion cyclotron range of frequency waves for auxiliary heating. Input power was scanned both in stationary enhanced D α (EDA) H-modes with no large edge localized modes (ELMs) and in ELMy H-modes in order to relate the resulting pedestal and confinement to the amount of power flowing into the scrape-off layer, P net , and also to the divertor targets. In both EDA and ELMy H-mode, energy confinement is generally good, with H 98 near unity. As P net is reduced to levels approaching that in L-mode, pedestal temperature diminishes significantly and normalized confinement time drops. By seeding with low-Z impurities, such as Ne and N 2 , high total radiated power fractions are possible, along with substantial reductions in divertor heat flux (>4x), all while maintaining H 98 ∼ 1. When the power radiated from the confined versus unconfined plasma is examined, pedestal and confinement properties are clearly seen to be an increasing function of P net , helping to unify the results with those from unseeded H-modes. This provides increased confidence that the power flow across the separatrix is the correct physics basis for ITER extrapolation. The experiments show that P net /P th of one or greater is likely to lead to H

Solid-state fast voltage compensator for pulsed power applications requiring constant AC power consumption

CERN Document Server

Magallanes, Francisco Cabaleiro; Viarouge, Philippe; Cros, Jérôme

2015-01-01

This paper proposes a novel topological solution for pulsed power converters based on capacitor-discharge topologies, integrating a Fast Voltage Compensator which allows an operation at constant power consumption from the utility grid. This solution has been retained as a possible candidate for the CLIC project under study at CERN, which requires more than a thousand synchronously-operated klystron modulators producing a total pulsed power of almost 40 GW. The proposed Fast Voltage Compensator is integrated in the modulator such that it only has to treat the capacitor charger current and a fraction of the charging voltage, meaning that its dimensioning power and cost are minimized. This topology can be used to improve the AC power quality of any pulsed converters based on capacitor-discharge concept. A prototype has been built and exploited to validate the operating principle and demonstrate the benefits of the proposed solution.

Empirical Models for Power and Energy Requirements II : A Powered Implement Operation in Serdang Sandy Clay Loam, Malaysia

Directory of Open Access Journals (Sweden)

A. F. Kheiralla

2017-12-01

Full Text Available Power and energy requirements were measured with an instrumented tractor for rotary tilling in Serdang sandy clay loam soil.  The effects of travel speed and rotor speed upon the measured data were investigated.  Power model from orthogonal regression analysis was formulated based on linear and quadratic functions of travel speed and bite length.  Fuel consumption model from regression analysis was formulated based on linear tractor PTO power as well as linear equivalent tractor PTO power.  Fuel consumption rates predicted by ASAE D497.3 were found to be 25% to 28% overestimates of the values predicted by the model developed.  However, fuel consumption rates reported by OECD Tractor Test were found to be 1% to 9% lower than the fuel consumption rates predicted by the model developed.  A comparison of power and energy requirements for both powered and draught implements showed that the disk harrow was the most energy efficient implement in terms of fuel consumption and specific energy followed by the rotary tiller, disk plough and mouldboard.  Finally, average PTO power, fuel consumption, wheel slip, wheel power and specific energy for a powered implement are presented.

Validation of Power Requirement Model for Active Loudspeakers

DEFF Research Database (Denmark)

Schneider, Henrik; Madsen, Anders Normann; Bjerregaard, Ruben

2015-01-01

. There are however many advantages that could be harvested from such knowledge like size, cost and efficiency improvements. In this paper a recently proposed power requirement model for active loudspeakers is experimentally validated and the model is expanded to include the closed and vented type enclosures...

Requirement profile for nuclear power station personnel

International Nuclear Information System (INIS)

Roeglin, H.C.

1984-01-01

The starting point in deriving the requirement profile for the shift personnel in the control rooms of nuclear power stations is information of a technical, organisational and ergonomic kind. The technique used, the distribution of work to different work areas and the configuration of the workplace is determined by the tasks and the environmental conditions in which they have to be done. (orig./DG) [de

Rest Interval Required for Power Training With Power Load in the Bench Press Throw Exercise.

Science.gov (United States)

Hernández Davó, Jose L; Solana, Rafael Sabido; Sarabia Marín, Jose M; Fernández Fernández, Jaime; Moya Ramón, Manuel

2016-05-01

This study aimed to test the influence of various rest interval (RI) durations used between sets on power output performance and physiological and perceptual variables during a strength training session using 40% of the 1 repetition maximum (1RM) in the bench press throw exercise. Thirty-one college students (18 males and 13 females) took part in the study. The experimental protocol consists of 5 sets of 8 repetitions of the bench press throw exercise with a load representing 40% of 1RM. Subjects performed the experimental protocol on 3 different occasions, differing by the RI between sets (1, 2, or 3 minutes). During the sessions, power data (mean power and peak power), physiological (lactate concentration [La]) and perceptual (rating of perceived exertion) variables were measured. In addition, delayed onset muscular soreness was reported 24 and 48 hours after the training session. One-way repeated-measures analysis of variance showed that 1-minute RI entailed higher power decreases and greater increases in values of physiological and perceptual variables compared with both 2- and 3-minute RIs. Nevertheless, no differences were found between 2- and 3-minute RIs. Therefore, this study showed that, when training with 40% of 1RM in the bench press throw exercise, a 2-minute RI between sets can be enough to avoid significant decreases in power output. Consequently, training sessions' duration could be reduced without causing excessive fatigue, allowing additional time to focus on other conditioning priorities.

Overall quality assurance program requirements for nuclear power plants

International Nuclear Information System (INIS)

1992-09-01

This standard contains the requirements for the owner's overall quality assurance program for a nuclear power plant. This program encompasses all phases of a nuclear power plant life cycle, including site evaluation, design, procurement, manufacturing, construction and installation, commissioning, operation, and decommissioning. It covers the activities associated with specifying, directing, and administering the work to be done during these phases, and the evaluation and integrated of the activities and programs of participants

Environmental Impacts of Wind Power Development on the Population Biology of Greater Prairie-Chickens

Energy Technology Data Exchange (ETDEWEB)

Sandercock, Brett K. [Kansas State University

2013-05-22

Executive Summary 1. We investigated the impacts of wind power development on the demography, movements, and population genetics of Greater Prairie-Chickens (Tympanuchus cupido) at three sites in northcentral and eastern Kansas for a 7-year period. Only 1 of 3 sites was developed for wind power, the 201MW Meridan Way Wind Power Facility at the Smoky Hills site in northcentral Kansas. Our project report is based on population data for prairie chickens collected during a 2-year preconstruction period (2007-2008), a 3-year postconstruction period (2009-2011) and one final year of lek surveys (2012). Where relevant, we present preconstruction data from our field studies at reference sites in the northern Flint Hills (2007-2009) and southern Flint Hills (2006-2008). 2. We addressed seven potential impacts of wind power development on prairie chickens: lek attendance, mating behavior, use of breeding habitat, fecundity rates, natal dispersal, survival rates, and population numbers. Our analyses of pre- and postconstruction impacts are based on an analysis of covariance design where we modeled population performance as a function of treatment period, distance to eventual or actual site of the nearest wind turbine, and the interaction of these factors. Our demographic and movement data from the 6-year study period at the Smoky Hills site included 23 lek sites, 251 radio-marked females monitored for 287 bird-years, and 264 nesting attempts. Our genetic data were based on genotypes of 1,760 females, males and chicks that were screened with a set of 27 microsatellite markers that were optimized in the lab. 3. In our analyses of lek attendance, the annual probability of lek persistence during the preconstruction period was ~0.9. During the postconstruction period, distance to nearest turbine did not have a significant effect on the probability of lek persistence. However, the probability of lek persistence increased from 0.69 at 0 m to 0.89 at 30 km from turbines, and most

Research on spacecraft electrical power conversion

Science.gov (United States)

Wilson, T. G.

1983-01-01

The history of spacecraft electrical power conversion in literature, research and practice is reviewed. It is noted that the design techniques, analyses and understanding which were developed make today's contribution to power computers and communication installations. New applications which require more power, improved dynamic response, greater reliability, and lower cost are outlined. The switching mode approach in electronic power conditioning is discussed. Technical aspects of the research are summarized.

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

Recommended general safety requirements for nuclear power plants

International Nuclear Information System (INIS)

1983-06-01

This report presents recommendations for a set of general safety requirements that could form the basis for the licensing of nuclear power plants by the Atomic Energy Control Board. In addition to a number of recommended deterministic requirements the report includes criteria for the acceptability of the design of such plants based upon the calculated probability and consequence (in terms of predicted radiation dose to members of the public) of potential fault sequences. The report also contains a historical review of nuclear safety principles and practices in Canada

International requirements for life extension of nuclear power plants

International Nuclear Information System (INIS)

Wernicke, Robert

2009-01-01

Lifetime extension or long-term operation of nuclear facilities are topics of great international significance against the backdrop of a fleet of nuclear power plants of which many have reached 2/3 of their planned life. The article deals with the conditions for, and the specific requirements of, seeking long-term operation of nuclear power plants as established internationally and on the basis of IAEA collections. Technically, long-term operation is possible for many of the nuclear power plants in the world because, normally, they were built on the basis of conservative rules and regulations and, as a consequence, incorporate significant additional safety. Application of requirements to specific plants implies assessments of technical safety which show that conservative design philosophies created reserves and, as a consequence, there is an adequate level of safety also in long-term plant operation. For this purpose, the technical specifications must be revised, necessary additions made, and (international) operating experience taken into account and management of aging established. Two examples are presented to show how the approach to long-term plant operation is put into practice on a national level. (orig.)

Evaluation of the energy required for constructing and operating a fusion power plant

International Nuclear Information System (INIS)

Buende, R.

1982-09-01

The energy required for constructing and operating a tokamak fusion power plant is appraised with respect to the energy output during the lifetime of the plant. A harvesting factor is deduced as a relevant figure of energetic merit and is used for a comparison between fusion, fission, and coal-fired power plants. Because fusion power plants involve considerable uncertainties the comparison is supplemented by a sensitivity analysis. In comparison with Light Water Reactor plants fusion power plants appear to be rather favourable in this respect. The energy required for providing the fuel is relatively low for fusion plants, thus overcompensating the considerable higher amount of energy necessary for constructing the fusion power plant. (orig.)

Generating units performances: power system requirements

Energy Technology Data Exchange (ETDEWEB)

Fourment, C; Girard, N; Lefebvre, H

1994-08-01

The part of generating units within the power system is more than providing power and energy. Their performance are not only measured by their energy efficiency and availability. Namely, there is a strong interaction between the generating units and the power system. The units are essential components of the system: for a given load profile the frequency variation follows directly from the behaviour of the units and their ability to adapt their power output. In the same way, the voltage at the units terminals are the key points to which the voltage profile at each node of the network is linked through the active and especially the reactive power flows. Therefore, the customer will experience the frequency and voltage variations induced by the units behaviour. Moreover, in case of adverse conditions, if the units do not operate as well as expected or trip, a portion of the system, may be the whole system, may collapse. The limitation of the performance of a unit has two kinds of consequences. Firstly, it may result in an increased amount of not supplied energy or loss of load probability: for example if the primary reserve is not sufficient, a generator tripping may lead to an abnormal frequency deviation, and load may have to be shed to restore the balance. Secondly, the limitation of a unit performance results in an economic over-cost for the system: for instance, if not enough `cheap` units are able to load-following, other units with higher operating costs have to be started up. We would like to stress the interest for the operators and design teams of the units on the one hand, and the operators and design teams of the system on the other hand, of dialog and information exchange, in operation but also at the conception stage, in order to find a satisfactory compromise between the system requirements and the consequences for the generating units. (authors). 11 refs., 4 figs.

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.

Effect of power system technology and mission requirements on high altitude long endurance aircraft

Science.gov (United States)

Colozza, Anthony J.

1994-01-01

An analysis was performed to determine how various power system components and mission requirements affect the sizing of a solar powered long endurance aircraft. The aircraft power system consists of photovoltaic cells and a regenerative fuel cell. Various characteristics of these components, such as PV cell type, PV cell mass, PV cell efficiency, fuel cell efficiency, and fuel cell specific mass, were varied to determine what effect they had on the aircraft sizing for a given mission. Mission parameters, such as time of year, flight altitude, flight latitude, and payload mass and power, were also altered to determine how mission constraints affect the aircraft sizing. An aircraft analysis method which determines the aircraft configuration, aspect ratio, wing area, and total mass, for maximum endurance or minimum required power based on the stated power system and mission parameters is presented. The results indicate that, for the power system, the greatest benefit can be gained by increasing the fuel cell specific energy. Mission requirements also substantially affect the aircraft size. By limiting the time of year the aircraft is required to fly at high northern or southern latitudes, a significant reduction in aircraft size or increase in payload capacity can be achieved.

Parameterized Flight Mission for Secondary Power Requirement Estimations of Commercial Transport Aircraft

OpenAIRE

Lampl, Thomas; Muschkorgel, Sandra; Hornung, Mirko;

2018-01-01

The trend towards More-Electric Aircraft (MEA) and the introduction of new system technologies lead to considerable changes at the system level of commercial transport aircraft. Because the number of systems and power requirements are increasing, the consideration and integration of aircraft systems in early aircraft design phases is important. The objective of this contribution is to develop a characteristic flight mission with modelled aircraft systems to estimate the secondary power requir...

Reduction of wind power induced reserve requirements by advanced shortest-term forecasts and prediction intervals

Energy Technology Data Exchange (ETDEWEB)

Dobschinski, Jan; Wessel, Arne; Lange, Bernhard; Bremen, Lueder von [Fraunhofer Institut fuer Windenergie und Energiesystemtechnik (IWES), Kassel (Germany)

2009-07-01

In electricity systems with large penetration of wind power, the limited predictability of the wind power generation leads to an increase in reserve and balancing requirements. At first the present study concentrates on the capability of dynamic day-ahead prediction intervals to reduce the wind power induced reserve and balancing requirements. Alternatively the reduction of large forecast errors of the German wind power generation by using advanced shortest-term predictions has been evaluated in a second approach. With focus on the allocation of minute reserve power the aim is to estimate the maximal remaining uncertainty after trading activities on the intraday market. Finally both approaches were used in a case study concerning the reserve requirements induced by the total German wind power expansion in 2007. (orig.)

Human Resources Requirements for New Nuclear Power Programs

International Nuclear Information System (INIS)

Goodnight, Charles T.

2014-01-01

Summary: Planning to Meet HR Requirements for New Nuclear Power Programs Must Begin Early. Many years of preparation are required before the “Right Number of the Right People” … will be … “In the Right Place at the Right Time”. • Seven key steps which must be taken include: 1) Identify detailed Human Resources requirements, based on the selected site and reactor design; 2) Conduct an assessment of national capacity to develop and/or provide those resources; 3) Conduct a Gap Analysis to determine what additional steps will be needed to fill any capacity shortfalls; 4) Develop initial and recurring recruiting and training plans; 5) Begin recruiting and training; 6) Review and adjust as personnel move and/or leave; 7) Ensure adequate relationships are in place for sources of future recruiting

Energy Data Visualization Requires Additional Approaches to Continue to be Relevant in a World with Greater Low-Carbon Generation

International Nuclear Information System (INIS)

Grant Wilson, I. A.

2016-01-01

The hypothesis described in this article proposes that energy visualization diagrams commonly used need additional changes to continue to be relevant in a world with greater low-carbon generation. The diagrams that display national energy data are influenced by the properties of the type of energy being displayed, which in most cases has historically meant fossil fuels, nuclear fuels, or hydro. As many energy systems throughout the world increase their use of electricity from wind- or solar-based renewables, a more granular display of energy data in the time domain is required. This article also introduces the shared axes energy diagram that provides a simple and powerful way to compare the scale and seasonality of the demands and supplies of an energy system. This aims to complement, rather than replace existing diagrams, and has an additional benefit of promoting a whole systems approach to energy systems, as differing energy vectors, such as natural gas, transport fuels, and electricity, can all be displayed together. This, in particular, is useful to both policy makers and to industry, to build a visual foundation for a whole systems narrative, which provides a basis for discussion of the synergies and opportunities across and between different energy vectors and demands. The diagram’s ability to wrap a sense of scale around a whole energy system in a simple way is thought to explain its growing popularity.

Energy Data Visualization Requires Additional Approaches to Continue to be Relevant in a World with Greater Low-Carbon Generation

Energy Technology Data Exchange (ETDEWEB)

Grant Wilson, I. A., E-mail: grant.wilson@sheffield.ac.uk [Environmental and Energy Engineering Group, Department of Chemical and Biological Engineering, The University of Sheffield, Sheffield (United Kingdom)

2016-08-31

The hypothesis described in this article proposes that energy visualization diagrams commonly used need additional changes to continue to be relevant in a world with greater low-carbon generation. The diagrams that display national energy data are influenced by the properties of the type of energy being displayed, which in most cases has historically meant fossil fuels, nuclear fuels, or hydro. As many energy systems throughout the world increase their use of electricity from wind- or solar-based renewables, a more granular display of energy data in the time domain is required. This article also introduces the shared axes energy diagram that provides a simple and powerful way to compare the scale and seasonality of the demands and supplies of an energy system. This aims to complement, rather than replace existing diagrams, and has an additional benefit of promoting a whole systems approach to energy systems, as differing energy vectors, such as natural gas, transport fuels, and electricity, can all be displayed together. This, in particular, is useful to both policy makers and to industry, to build a visual foundation for a whole systems narrative, which provides a basis for discussion of the synergies and opportunities across and between different energy vectors and demands. The diagram’s ability to wrap a sense of scale around a whole energy system in a simple way is thought to explain its growing popularity.

The requirements and specific features related to power supply in telecommunications of Ukraine

Energy Technology Data Exchange (ETDEWEB)

Lubashenko, T. [Inst. Giprosvijaz, Kiev (Ukraine); Gordon, A. [ProElectro Ltd., Kiev (Ukraine)

2000-07-01

The article deals with the description of trends of power supplies in the telecommunication sector. The basic normative documents regarding the design of the power supplies are pointed out. The requirements concerning the design of the power supplies are outlined. The peculiarities of the power supplies in Ukrainian telecommunications are given. (orig.)

Byproduct metal requirements for U.S. wind and solar photovoltaic electricity generation up to the year 2040 under various Clean Power Plan scenarios

Science.gov (United States)

Nassar, Nedal T.; Wilburn, David R.; Goonan, Thomas G.

2016-01-01

The United States has and will likely continue to obtain an increasing share of its electricity from solar photovoltaics (PV) and wind power, especially under the Clean Power Plan (CPP). The need for additional solar PV modules and wind turbines will, among other things, result in greater demand for a number of minor metals that are produced mainly or only as byproducts. In this analysis, the quantities of 11 byproduct metals (Ag, Cd, Te, In, Ga, Se, Ge, Nd, Pr, Dy, and Tb) required for wind turbines with rare-earth permanent magnets and four solar PV technologies are assessed through the year 2040. Three key uncertainties (electricity generation capacities, technology market shares, and material intensities) are varied to develop 42 scenarios for each byproduct metal. The results indicate that byproduct metal requirements vary significantly across technologies, scenarios, and over time. In certain scenarios, the requirements are projected to become a significant portion of current primary production. This is especially the case for Te, Ge, Dy, In, and Tb under the more aggressive scenarios of increasing market share and conservative material intensities. Te and Dy are, perhaps, of most concern given their substitution limitations. In certain years, the differences in byproduct metal requirements between the technology market share and material intensity scenarios are greater than those between the various CPP and No CPP scenarios. Cumulatively across years 2016–2040, the various CPP scenarios are estimated to require 15–43% more byproduct metals than the No CPP scenario depending on the specific byproduct metal and scenario. Increasing primary production via enhanced recovery rates of the byproduct metals during the beneficiation and enrichment operations, improving end-of-life recycling rates, and developing substitutes are important strategies that may help meet the increased demand for these byproduct metals.

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.

Assessment of tritium breeding requirements for fusion power reactors

International Nuclear Information System (INIS)

Jung, J.

1983-12-01

This report presents an assessment of tritium-breeding requirements for fusion power reactors. The analysis is based on an evaluation of time-dependent tritium inventories in the reactor system. The method presented can be applied to any fusion systems in operation on a steady-state mode as well as on a pulsed mode. As an example, the UWMAK-I design was analyzed and it has been found that the startup inventory requirement calculated by the present method significantly differs from those previously calculated. The effect of reactor-parameter changes on the required tritium breeding ratio is also analyzed for a variety of reactor operation scenarios

A modular Space Station/Base electrical power system - Requirements and design study.

Science.gov (United States)

Eliason, J. T.; Adkisson, W. B.

1972-01-01

The requirements and procedures necessary for definition and specification of an electrical power system (EPS) for the future space station are discussed herein. The considered space station EPS consists of a replaceable main power module with self-contained auxiliary power, guidance, control, and communication subsystems. This independent power source may 'plug into' a space station module which has its own electrical distribution, control, power conditioning, and auxiliary power subsystems. Integration problems are discussed, and a transmission system selected with local floor-by-floor power conditioning and distribution in the station module. This technique eliminates the need for an immediate long range decision on the ultimate space base power sources by providing capability for almost any currently considered option.

10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... systems. (8) Emergency ac electrical power systems, including: Emergency diesel generators (EDGs...

Mathematically modelling the power requirement for a vertical shaft mowing machine

Directory of Open Access Journals (Sweden)

Jorge Simón Pérez de Corcho Fuentes

2008-09-01

Full Text Available This work describes a mathematical model for determining the power demand for a vertical shaft mowing machine, particularly taking into account the influence of speed on cutting power, which is different from that of other models of mowers. The influence of the apparatus’ rotation and translation speeds was simulated in determining power demand. The results showed that no chan-ges in cutting power were produced by varying the knives’ angular speed (if translation speed was constant, while cutting power became increased if translation speed was increased. Variations in angular speed, however, influenced other parameters deter-mining total power demand. Determining this vertical shaft mower’s cutting pattern led to obtaining good crop stubble quality at the mower’s lower rotation speed, hence reducing total energy requirements.

Ideal MHD Stability Prediction and Required Power for EAST Advanced Scenario

International Nuclear Information System (INIS)

Chen Junjie; Li Guoqiang; Qian Jinping; Liu Zixi

2012-01-01

The Experimental Advanced Superconducting Tokamak (EAST) is the first fully superconducting tokamak with a D-shaped cross-sectional plasma presently in operation. The ideal magnetohydrodynamic (MHD) stability and required power for the EAST advanced tokamak (AT) scenario with negative central shear and double transport barrier (DTB) are investigated. With the equilibrium code TOQ and stability code GATO, the ideal MHD stability is analyzed. It is shown that a moderate ratio of edge transport barriers' (ETB) height to internal transport barriers' (ITBs) height is beneficial to ideal MHD stability. The normalized beta β N limit is about 2.20 (without wall) and 3.70 (with ideal wall). With the scaling law of energy confinement time, the required heating power for EAST AT scenario is calculated. The total heating power P t increases as the toroidal magnetic field B T or the normalized beta β N is increased. (magnetically confined plasma)

Ideal MHD Stability Prediction and Required Power for EAST Advanced Scenario

Science.gov (United States)

Chen, Junjie; Li, Guoqiang; Qian, Jinping; Liu, Zixi

2012-11-01

The Experimental Advanced Superconducting Tokamak (EAST) is the first fully superconducting tokamak with a D-shaped cross-sectional plasma presently in operation. The ideal magnetohydrodynamic (MHD) stability and required power for the EAST advanced tokamak (AT) scenario with negative central shear and double transport barrier (DTB) are investigated. With the equilibrium code TOQ and stability code GATO, the ideal MHD stability is analyzed. It is shown that a moderate ratio of edge transport barriers' (ETB) height to internal transport barriers' (ITBs) height is beneficial to ideal MHD stability. The normalized beta βN limit is about 2.20 (without wall) and 3.70 (with ideal wall). With the scaling law of energy confinement time, the required heating power for EAST AT scenario is calculated. The total heating power Pt increases as the toroidal magnetic field BT or the normalized beta βN is increased.

High gain requirements and high field Tokamak experiments

International Nuclear Information System (INIS)

Cohn, D.R.

1994-01-01

Operation at sufficiently high gain (ratio of fusion power to external heating power) is a fundamental requirement for tokamak power reactors. For typical reactor concepts, the gain is greater than 25. Self-heating from alpha particles in deuterium-tritium plasmas can greatly reduce ητ/temperature requirements for high gain. A range of high gain operating conditions is possible with different values of alpha-particle efficiency (fraction of alpha-particle power that actually heats the plasma) and with different ratios of self heating to external heating. At one extreme, there is ignited operation, where all of the required plasma heating is provided by alpha particles and the alpha-particle efficiency is 100%. At the other extreme, there is the case of no heating contribution from alpha particles. ητ/temperature requirements for high gain are determined as a function of alpha-particle heating efficiency. Possibilities for high gain experiments in deuterium-tritium, deuterium, and hydrogen plasmas are discussed

Design requirements, criteria and methods for seismic qualification of CANDU power plants

International Nuclear Information System (INIS)

Singh, N.; Duff, C.G.

1979-10-01

This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)

Energy data visualisation requires additional approaches to continue to be relevant in a world with greater low-carbon generation.

Directory of Open Access Journals (Sweden)

I.A. Grant Wilson

2016-08-01

Full Text Available The hypothesis described in this article proposes that energy visualisation diagrams commonly used need additional changes to continue to be relevant in a world with greater low-carbon generation. The diagrams that display national energy data are influenced by the properties of the type of energy being displayed, which in most cases has historically meant fossil fuels, nuclear fuels or hydro. As many energy systems throughout the world increase their use of electricity from wind or solar based renewables, a more granular display of energy data in the time domain is required. This article also introduces the shared axes energy diagram that provides a simple and powerful way in which to compare the scale and seasonality of the demands and supplies of an energy system. This aims to complement rather than replace existing diagrams, and has an additional benefit of promoting a whole systems approach to energy systems, as differing energy vectors such as natural gas, transport fuels, and electricity can all be displayed together. This in particular, is useful to both policy makers and to industry, to build a visual foundation for a whole systems narrative, which provides a basis for discussion of the synergies and opportunities across and between different energy vectors and demands. The diagram’s ability to wrap a sense of scale around a whole energy system in a simple way is thought to explain its growing popularity.

Power feature required for PEFC powered electric propulsion ship

Energy Technology Data Exchange (ETDEWEB)

Yoshida, Isao [NKK Corp., Yokohama (Japan); Oka, Masaru [Mitsubishi Heavy Industries, Ltd., Nagasaki (Japan)

1996-12-31

This report covers part of a joint study on a PEFC system for ship propulsion, summarized in a presentation to this Seminar, entitled {open_quote}Study on a Polymer Electrolyte Fuel Cell (PEFC) Propulsion System for Surface Ships{close_quotes}, and which envisages application to a 1,500 DWT cargo vessel. The aspect treated here concerns an analysis of the load-following performance required and estimated of a PEFC system to power the envisaged ship. The analysis proved that difficulty should be expected of the fuel supply circuit in following with adequate rapidity the sharp changes of load on fuel cell under certain conditions. Further integrated experiments and simulation exercises are currently in progress to further analyze the response characteristics of the fuel supply circuit-particularly of the methanol reformer and gas reservoir-to determine the best measure to be adopted for overcoming the expected difficulty.

Manpower requirements of quality assurance personnel for the nuclear power plants

International Nuclear Information System (INIS)

Aly, A.E.; El-sayed, A.A.; Shabaan, I.H.

1987-01-01

Basic principles for structuring and staffing of the quality assurance (Q.A.)organisation in the nuclear power plant (NPP) are presented. the manpower requirements of the Q.A.organisation in the NPP during both construction and operational stages are determined. the manpower requirements for Q.A./Q.C. functions in a NPP are found to be proportional to the number of craft workers needed to perform the required level of the construction. The Q.A./Q.C. personnel are about 15% of the total number of the craft workers required during construction

Laser requirements for a laser fusion energy power plant

Institute of Scientific and Technical Information of China (English)

Stephen; E.Bodner; Andrew; J.Schmitt; John; D.Sethian

2013-01-01

We will review some of the requirements for a laser that would be used with a laser fusion energy power plant, including frequency, spatial beam smoothing, bandwidth, temporal pulse shaping, efficiency, repetition rate, and reliability. The lowest risk and optimum approach uses a krypton fluoride gas laser. A diode-pumped solid-state laser is a possible contender.

Conditions and requirements for a potential application of solar power satellites /SPS/ for Europe

Energy Technology Data Exchange (ETDEWEB)

Westphal, W. (Berlin, Technische Universitaet, Berlin, West Germany); Ruth, J. (ESA, European Space Research and Technology Centre, Noordwijk, Netherlands)

1980-12-01

The potential problems of a future introduction of Solar Power Satellites (SPS) as baseload power plants for Western European countries are considered, emphasizing the differences of SPS utilization in Europe compared with that in the USA as a result of geographical, orbital organizational, and industrial conditions. If estimated SPS safety zone areas are required, then the SPS system incorporating the 2.45 GHz microwave power transmission appears crucial for utilization in Western Europe in order to eliminate the large rectenna area requirements of an SPS 5 GW power system. A frequency variation of up to 5 or 10 GHz, and the application of either laser power transmission or solid state devices which could alleviate rectenna siting problems and restrictions on the use of the geosynchronous orbit are discussed.

Requirements on future energy supply. Analysis on the demand of future power plant capacity and strategy for a sustainable power utilization in Germany

International Nuclear Information System (INIS)

2003-08-01

This strategy paper was drawn up with a view to maximum ecological compatibility of pwer plant modernization and sustainable power generation and use. The first part of the paper analyzes the power plants to be decommissioned on a medium-term basis and - against the background of several different scenarios for future power demand - an estimate of power plant capacities required by 2020. The second part describes the goals and concrete requirements of sustainable energy use. In the final part, the available instruments are presented, and those instruments are recommended that will be best suited for making power demand and supply efficient, sustainable and environment-friend.y [de

Report of the Committee to review safeguards requirements at power reactors

International Nuclear Information System (INIS)

1983-05-01

In October 1982, NRC's Executive Director for Operations appointed a five-member Committee to review NRC security requirements at nuclear power plants with a view toward evaluating the impact of these requirements on operational safety. During visits to five power reactor sites and more than a dozen days of meetings over a period of four months, the Committee observed plant operating conditions and obtained views from abut 100 persons representing 16 nuclear utilities and industry organizations. They also interviewed about 40 NRC employees, including Resident Inspectors, and members of the Regional and Headquarters staffs. Overall, the Committee did not identify any clear operational safety problems associated with implementation of the NRC's security requirements. However, they did find that the potential existed, to varying degrees, at licensed facilities. The Committee's report, dated February 28, 1983, contains five basic findings and a number of associated recommendations intended to minimize the potential impact of security on safety

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

Power system reliability impacts of wind generation and operational reserve requirements

Directory of Open Access Journals (Sweden)

Esteban Gil

2015-06-01

Full Text Available Due to its variability, wind generation integration presents a significant challenge to power system operators in order to maintain adequate reliability levels while ensuring least cost operation. This paper explores the trade-off between the benefits associated to a higher wind penetration and the additional operational reserve requirements that they impose. Such exploration is valued in terms of its effect on power system reliability, measured as an amount of unserved energy. The paper also focuses on how changing the Value of Lost Load (VoLL can be used to attain different reliability targets, and how wind power penetration and the diversity of the wind energy resource will impact quality of supply (in terms of instances of unserved energy. The evaluation of different penetrations of wind power generation, different wind speed profiles, wind resource diversity, and different operational reserve requirements, is conducted on the Chilean Northern Interconnected System (SING using statistical modeling of wind speed time series and computer simulation through a 24-hour ahead unit commitment algorithm and a Monte Carlo simulation scheme. Results for the SING suggest that while wind generation can significantly reduce generation costs, it can also imply higher security costs to reach acceptable reliability levels.

Manpower requirements for nuclear power programmes in nations of intermediate capacity

International Nuclear Information System (INIS)

Cantarell, I.; Cerrolaza, J.A.; Llado, J.M.

1980-01-01

A study is made of the manpower required for initiating and carrying out a nuclear power programme in countries which have not developed their own nuclear technology but where the technical and economic level is such to permit a substantial input from local industry. The discussion is based on Spanish experience. The three basic elements in a nuclear programme are taken to be the operating company, the regulating authority and the engineering firm involved. The role of each of these is briefly considered and the manpower requirements during the design, construction and operational phases of a power station are evaluated. A short account is also given of the manpower requirements of other enterprises such as those involved in the civil engineering, the assembly and construction control. The variations in the labour force are described with the aim of deriving estimates of the number of people involved in the development of a nuclear power programme as a function of time: actual numbers are given for the case of the Spanish national energy plan. A brief description is given of the various courses on nuclear science and engineering provided in Spain and the requirements laid down by the regulations. A short account is given of Spanish nuclear development, with emphasis on the work carried out by the Nuclear Energy Board, not only as a research organization but also in its promotional and training capacities and as a source of personnel for industry. Finally, some comments are made on the possibilities opened up by international co-operation. (author)

EUR, an European utility requirements documents for future LWR power stations

International Nuclear Information System (INIS)

Berbey, Pierre; Lienard, Michel; Redon, Ramon; Essmann, Juergen; Taylor, David T.

2004-01-01

A group of the major European utilities are developing a common requirement document which will be used for the LWR nuclear power plants to be built in Europe from the beginning of the next century. This document provides harmonised policies and technical requirements that will allow the implementation of a design developed in one country into another one. The objectives and contents of the document, the organisation set up for its production and the main requirements are summarised in the paper. (author)

Structural materials requirements for in-vessel components of fusion power plants

International Nuclear Information System (INIS)

Schaaf, B. van der

2000-01-01

The economic production of fusion energy is determined by principal choices such as using magnetic plasma confinement or generating inertial fusion energy. The first generation power plants will use deuterium and tritium mixtures as fuel, producing large amounts of highly energetic neutrons resulting in radiation damage in materials. In the far future the advanced fuels, 3 He or 11 B, determine power plant designs with less radiation damage than in the first generation. The first generation power plants design must anticipate radiation damage. Solid sacrificing armour or liquid layers could limit component replacements costs to economic levels. There is more than radiation damage resistance to determine the successful application of structural materials. High endurance against cyclic loading is a prominent requirement, both for magnetic and inertial fusion energy power plants. For high efficiency and compactness of the plant, elevated temperature behaviour should be attractive. Safety and environmental requirements demand that materials have low activation potential and little toxic effects under both normal and accident conditions. The long-term contenders for fusion power plant components near the plasma are materials in the range from innovative steels, such as reduced activation ferritic martensitic steels, to highly advanced ceramic composites based on silicon carbide, and chromium alloys. The steels follow an evolutionary path to basic plant efficiencies. The competition on the energy market in the middle of the next century might necessitate the riskier but more rewarding development of SiCSiC composites or chromium alloys

Future CANDU nuclear power plant design requirements document executive summary

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; S. A. Usmani

1996-03-01

The future CANDU Requirements Document (FCRED) describes a clear and complete statement of utility requirements for the next generation of CANDU nuclear power plants including those in Korea. The requirements are based on proven technology of PHWR experience and are intended to be consistent with those specified in the current international requirement documents. Furthermore, these integrated set of design requirements, incorporate utility input to the extent currently available and assure a simple, robust and more forgiving design that enhances the performance and safety. The FCRED addresses the entire plant, including the nuclear steam supply system and the balance of the plant, up to the interface with the utility grid at the distribution side of the circuit breakers which connect the switchyard to the transmission lines. Requirements for processing of low level radioactive waste at the plant site and spent fuel storage requirements are included in the FCRED. Off-site waste disposal is beyond the scope of the FCRED. 2 tabs., 1 fig. (Author) .new

Fukushima, two years later, modification requirements in nuclear power plants

International Nuclear Information System (INIS)

Sanchez J, J.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Salmeron V, J. A.

2013-10-01

The occurred events in the nuclear power plant of Fukushima Daiichi as consequence of the strong earthquake of 9 grades in the Richter scale and the later tsunami with waves estimated in more than 14 meters high began a series of important questions about the safety of the nuclear power plants in operation and of the new designs. Firstly, have allowed to be questioned on the magnitudes and consequences of the extreme external natural events; that can put in risk the integrity of the safety barriers of a nuclear power plant when being presented in a multiple way. As consequence of the events of the Fukushima Daiichi NPP, the countries with NPPs in operation and /or construction carried out evaluations about their safety operation. They have also realized evaluations about accidents and their impact in the safety, analysis and studies too that have forced to the regulatory bodies to continue a systematic and methodical revision of their procedures and regulations, to identify the possible improvements to the safety in response to the events happened in Japan; everything has taken it to determine the necessity to incorporate additional requirements to the nuclear power plants to mitigate events Beyond the Design Base. Due to Mexico has the nuclear power plant of Laguna Verde, with two units of BWR-5 type with contention Mark III, some the modifications can be applicable to these units to administrate and/or to mitigate the consequences of the possible occurrence of an accident Beyond the Design Base and that could generate a severe accident. In this work an exposition is presented on the modification requirements to confront external natural events Beyond the Design Base, and its application in our country. (Author)

42 CFR 84.146 - Method of measuring the power and torque required to operate blowers.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Method of measuring the power and torque required... RESPIRATORY PROTECTIVE DEVICES Supplied-Air Respirators § 84.146 Method of measuring the power and torque.... These are used to facilitate timing. To determine the torque or horsepower required to operate the...

Current USAEC seismic requirements for nuclear power plants

International Nuclear Information System (INIS)

Mehta, D.S.

1975-01-01

The principal seismic and geologic considerations which guide the USAEC in its evaluation of the suitability of proposed sites for nuclear power plants and plant design bases are set forth as design criteria in the AEC regulatory guides. The basic requirements of seismic design and analysis for seismic Category I structures, components, and systems important to public safety have been established in the USAEC regulatory guides and Code of Federal Regulations. It is pointed out that the current state-of-art techniques, best available technology, and additional studies in the field of earthquake engineering can be utilized to resolve seismic concerns. The seismic design requirements for nuclear plants to withstand postulated earthquakes can be standardized and this will be a significant milestone in the continuation of the Nuclear Standardization Program. (author)

12 CFR 714.6 - Are you required to retain salvage powers over the leased property?

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Are you required to retain salvage powers over the leased property? 714.6 Section 714.6 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING CREDIT UNIONS LEASING § 714.6 Are you required to retain salvage powers over the leased...

18 CFR 292.209 - Exceptions from requirements for hydroelectric small power production facilities located at a new...

Science.gov (United States)

2010-04-01

... requirements for hydroelectric small power production facilities located at a new dam or diversion. 292.209... Exceptions from requirements for hydroelectric small power production facilities located at a new dam or... the Federal Power Act, at which non-Federal hydroelectric development is permissible; or (2) An...

Greater-confinement disposal

International Nuclear Information System (INIS)

Trevorrow, L.E.; Schubert, J.P.

1989-01-01

Greater-confinement disposal (GCD) is a general term for low-level waste (LLW) disposal technologies that employ natural and/or engineered barriers and provide a degree of confinement greater than that of shallow-land burial (SLB) but possibly less than that of a geologic repository. Thus GCD is associated with lower risk/hazard ratios than SLB. Although any number of disposal technologies might satisfy the definition of GCD, eight have been selected for consideration in this discussion. These technologies include: (1) earth-covered tumuli, (2) concrete structures, both above and below grade, (3) deep trenches, (4) augered shafts, (5) rock cavities, (6) abandoned mines, (7) high-integrity containers, and (8) hydrofracture. Each of these technologies employ several operations that are mature,however, some are at more advanced stages of development and demonstration than others. Each is defined and further described by information on design, advantages and disadvantages, special equipment requirements, and characteristic operations such as construction, waste emplacement, and closure

How wing kinematics affect power requirements and aerodynamic force production in a robotic bat wing

International Nuclear Information System (INIS)

Bahlman, Joseph W; Swartz, Sharon M; Breuer, Kenneth S

2014-01-01

Bats display a wide variety of behaviors that require different amounts of aerodynamic force. To control and modulate aerodynamic force, bats change wing kinematics, which, in turn, may change the power required for wing motion. There are many kinematic mechanisms that bats, and other flapping animals, can use to increase aerodynamic force, e.g. increasing wingbeat frequency or amplitude. However, we do not know if there is a difference in energetic cost between these different kinematic mechanisms. To assess the relationship between mechanical power input and aerodynamic force output across different isolated kinematic parameters, we programmed a robotic bat wing to flap over a range of kinematic parameters and measured aerodynamic force and mechanical power. We systematically varied five kinematic parameters: wingbeat frequency, wingbeat amplitude, stroke plane angle, downstroke ratio, and wing folding. Kinematic values were based on observed values from free flying Cynopterus brachyotis, the species on which the robot was based. We describe how lift, thrust, and power change with increases in each kinematic variable. We compare the power costs associated with generating additional force through the four kinematic mechanisms controlled at the shoulder, and show that all four mechanisms require approximately the same power to generate a given force. This result suggests that no single parameter offers an energetic advantage over the others. Finally, we show that retracting the wing during upstroke reduces power requirements for flapping and increases net lift production, but decreases net thrust production. These results compare well with studies performed on C. brachyotis, offering insight into natural flight kinematics. (paper)

Reactive power interconnection requirements for PV and wind plants : recommendations to NERC.

Energy Technology Data Exchange (ETDEWEB)

McDowell, Jason (General Electric, Schenectady, NY); Walling, Reigh (General Electric, Schenectady, NY); Peter, William (SunPower, Richmond, CA); Von Engeln, Edi (NV Energy, Reno, NV); Seymour, Eric (AEI, Fort Collins, CO); Nelson, Robert (Siemens Wind Turbines, Orlando, FL); Casey, Leo (Satcon, Boston, MA); Ellis, Abraham; Barker, Chris. (SunPower, Richmond, CA)

2012-02-01

Voltage on the North American bulk system is normally regulated by synchronous generators, which typically are provided with voltage schedules by transmission system operators. In the past, variable generation plants were considered very small relative to conventional generating units, and were characteristically either induction generator (wind) or line-commutated inverters (photovoltaic) that have no inherent voltage regulation capability. However, the growing level of penetration of non-traditional renewable generation - especially wind and solar - has led to the need for renewable generation to contribute more significantly to power system voltage control and reactive power capacity. Modern wind-turbine generators, and increasingly PV inverters as well, have considerable dynamic reactive power capability, which can be further enhanced with other reactive support equipment at the plant level to meet interconnection requirements. This report contains a set of recommendations to the North-America Electricity Reliability Corporation (NERC) as part of Task 1-3 (interconnection requirements) of the Integration of Variable Generation Task Force (IVGTF) work plan. The report discusses reactive capability of different generator technologies, reviews existing reactive power standards, and provides specific recommendations to improve existing interconnection standards.

Day-ahead optimal dispatch for wind integrated power system considering zonal reserve requirements

International Nuclear Information System (INIS)

Liu, Fan; Bie, Zhaohong; Liu, Shiyu; Ding, Tao

2017-01-01

Highlights: • Analyzing zonal reserve requirements for wind integrated power system. • Modeling day-ahead optimal dispatch solved by chance constrained programming theory. • Determining optimal zonal reserve demand with minimum confidence interval. • Analyzing numerical results on test and large-scale real-life power systems. - Abstract: Large-scale integration of renewable power presents a great challenge for day-ahead dispatch to manage renewable resources while provide available reserve for system security. Considering zonal reserve is an effective way to ensure reserve deliverability when network congested, a random day-ahead dispatch optimization of wind integrated power system for a least operational cost is modeled including zonal reserve requirements and N − 1 security constraints. The random model is transformed into a deterministic one based on the theory of chance constrained programming and a determination method of optimal zonal reserve demand is proposed using the minimum confidence interval. After solving the deterministic model, the stochastic simulation is conducted to verify the validity of solution. Numerical tests and results on the IEEE 39 bus system and a large-scale real-life power system demonstrate the optimal day-ahead dispatch scheme is available and the proposed method is effective for improving reserve deliverability and reducing load shedding after large-capacity power outage.

Development of safety-related regulatory requirements for nuclear power in developing countries. Key issue paper no. 4

International Nuclear Information System (INIS)

Han, K.I.

2000-01-01

In implementing a national nuclear power program, balanced regulatory requirements are necessary to ensure nuclear safety and cost competitive nuclear power, and to help gain public acceptance. However, this is difficult due to the technology-intensive nature of the nuclear regulatory requirements, the need to reflect evolving technology and the need for cooperation among multidisciplinary technical groups. This paper suggests approaches to development of balanced nuclear regulatory requirements in developing countries related to nuclear power plant safety, radiation protection and radioactive waste management along with key technical regulatory issues. It does not deal with economic or market regulation of electric utilities using nuclear power. It suggests that national regulatory requirements be developed using IAEA safety recommendations as guidelines and safety requirements of the supplier country as a main reference after careful planning, manpower buildup and thorough study of international and supplier country's regulations. Regulation making is not recommended before experienced manpower has been accumulated. With an option that the supplier country's regulations may be used in the interim, the lack of complete national regulatory requirements should not deter introduction of nuclear power in developing countries. (author)

Policy planning for nuclear power: An overview of the main issues and requirements

International Nuclear Information System (INIS)

1993-08-01

This special report, Policy Planning for Nuclear Power: An Overview of the Main Issues and Requirements, has been prepared in response to the express request of a number of IAEA Member States for a document to assist makers in developing countries on the introduction of nuclear power. The report contains information on the political, governmental, economic, financial and technical issues and requirements associated with planning and implementing a safe, economic and reliable nuclear power programme. It highlights the main areas in which policies must be developed and decisions taken, as well as the role and responsibilities of government, the plant owner and national industry. Also presented are the main criteria to assist policy planners in defining options and strategies which can achieve a balance among such objectives as cost effective and efficient electricity production, realistic and acceptable financing arrangements, national development requirements, safety and environmental protection. Further information and details on the technical and other issues presented in this report are given in the list of related IAEA publications and documents at the end of this report

Data requirements of GREAT-ER: Modelling and validation using LAS in four UK catchments

International Nuclear Information System (INIS)

Price, Oliver R.; Munday, Dawn K.; Whelan, Mick J.; Holt, Martin S.; Fox, Katharine K.; Morris, Gerard; Young, Andrew R.

2009-01-01

Higher-tier environmental risk assessments on 'down-the-drain' chemicals in river networks can be conducted using models such as GREAT-ER (Geography-referenced Regional Exposure Assessment Tool for European Rivers). It is important these models are evaluated and their sensitivities to input variables understood. This study had two primary objectives: evaluate GREAT-ER model performance, comparing simulated modelled predictions for LAS (linear alkylbenzene sulphonate) with measured concentrations, for four rivers in the UK, and investigate model sensitivity to input variables. We demonstrate that the GREAT-ER model is very sensitive to variability in river discharges. However it is insensitive to the form of distributions used to describe chemical usage and removal rate in sewage treatment plants (STPs). It is concluded that more effort should be directed towards improving empirical estimates of effluent load and reducing uncertainty associated with usage and removal rates in STPs. Simulations could be improved by incorporating the effect of river depth on dissipation rates. - Validation of GREAT-ER.

Data requirements of GREAT-ER: Modelling and validation using LAS in four UK catchments

Energy Technology Data Exchange (ETDEWEB)

Price, Oliver R., E-mail: oliver.price@unilever.co [Safety and Environmental Assurance Centre, Unilever, Colworth Science Park, Sharnbrook, Bedfordshire MK44 1LQ (United Kingdom); Munday, Dawn K. [Safety and Environmental Assurance Centre, Unilever, Colworth Science Park, Sharnbrook, Bedfordshire MK44 1LQ (United Kingdom); Whelan, Mick J. [Department of Natural Resources, School of Applied Sciences, Cranfield University, College Road, Cranfield, Bedfordshire MK43 0AL (United Kingdom); Holt, Martin S. [ECETOC, Ave van Nieuwenhuyse 4, Box 6, B-1160 Brussels (Belgium); Fox, Katharine K. [85 Park Road West, Birkenhead, Merseyside CH43 8SQ (United Kingdom); Morris, Gerard [Environment Agency, Phoenix House, Global Avenue, Leeds LS11 8PG (United Kingdom); Young, Andrew R. [Wallingford HydroSolutions Ltd, Maclean building, Crowmarsh Gifford, Wallingford, Oxon OX10 8BB (United Kingdom)

2009-10-15

Higher-tier environmental risk assessments on 'down-the-drain' chemicals in river networks can be conducted using models such as GREAT-ER (Geography-referenced Regional Exposure Assessment Tool for European Rivers). It is important these models are evaluated and their sensitivities to input variables understood. This study had two primary objectives: evaluate GREAT-ER model performance, comparing simulated modelled predictions for LAS (linear alkylbenzene sulphonate) with measured concentrations, for four rivers in the UK, and investigate model sensitivity to input variables. We demonstrate that the GREAT-ER model is very sensitive to variability in river discharges. However it is insensitive to the form of distributions used to describe chemical usage and removal rate in sewage treatment plants (STPs). It is concluded that more effort should be directed towards improving empirical estimates of effluent load and reducing uncertainty associated with usage and removal rates in STPs. Simulations could be improved by incorporating the effect of river depth on dissipation rates. - Validation of GREAT-ER.

Power requirements of biogas upgrading by water scrubbing and biomethane compression: Comparative analysis of various plant configurations

International Nuclear Information System (INIS)

Budzianowski, Wojciech M.; Wylock, Christophe E.; Marciniak, Przemysław A.

2017-01-01

Highlights: • Insights into power requirements of biomethane production from biogas are provided. • Process model is constructed, validated and simulated. • High-pressure and low-pressure plant operation in different configurations is compared. - Abstract: Biogas upgrading by water scrubbing followed by biomethane compression is an environmentally benign process. It may be achieved using various plant configurations characterised by various power requirements with associated effects on biomethane sustainability. Therefore, the current study has been undertaken to systematically investigate the power requirements of a range of water scrubbing options. Two groups of water scrubbing are analysed: (1) high pressure water scrubbing (HPWS) and (2) near-atmospheric pressure water scrubbing (NAPWS). A water scrubbing plant model is constructed, experimentally validated and simulated for seven upgrading plant configurations. Simulation results show that the power requirement of biogas upgrading in HPWS plants is mainly associated with biogas compression. In contrast, in NAPWS plants the main power is required for water pumping. In both plants the compression of the biomethane from atmosphereic pressure to 20 MPa also contributes remarkably. It is observed that the lowest specific power requirement can be obtained for a NAPWS plant without water regeneration (0.24 kW h/Nm"3 raw biogas) but this plant requires cheap water supply, e.g. outlet water from a sewage treatment plant or river. The second is HPWS without flash (0.29 kW h/Nm"3 raw biogas). All other HPWS with flash and NAPWS with water regeneration plants have specific power requirements between 0.30 and 0.33 kW h/Nm"3 raw biogas. Biogas compression without upgrading requires about 0.29 kW h/Nm"3 raw biogas. The thermodynamic efficiency of biogas upgrading is between 2.2% and 9.8% depending on the plant configuration while biomethane compression efficiency is higher, about 55%. This result implies that the

10 CFR 503.8 - No alternate power supply-general requirement for certain exemptions for new powerplants.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false No alternate power supply-general requirement for certain exemptions for new powerplants. 503.8 Section 503.8 Energy DEPARTMENT OF ENERGY (CONTINUED) ALTERNATE FUELS NEW FACILITIES General Requirements for Exemptions § 503.8 No alternate power supply—general...

Analysis of the Possibility of Required Resources Estimation for Nuclear Power Plant Decommissioning Applying BIM

Energy Technology Data Exchange (ETDEWEB)

Jung, Insu [Korea Institute of construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

2014-05-15

Estimation of decommissioning cost, decommissioning strategy, and decommissioning quantity at the time when entering into any decommissioning plans are some elements whose inputs are mandatory for nuclear power plant decommissioning. Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. This study aims at analyzing whether required resources for decommissioning nuclear power plants can be estimated, applying BIM. To achieve this goal, this study analyzed the status quo of BIM such as definition, characteristics, and areas applied, and made use of them when drawing out study results by examining types and features of the tools realizing BIM. In order to review how BIM could be used for decommissioning nuclear power plants, the definition, characteristics and applied areas of BIM were discussed. BIM designs objects of the structures (walls, slabs, pillars, stairs, windows and doors, etc.) by 3D technology and endows attribute (function, structure and usage) information for each object, thereby providing visualized information of structures for participants in construction projects. Major characteristics of BIM attribute information are as follows: - Geometry: The information of objects is represented by measurable geometric information - Extensible object attributes: Objects include pre-defined attributes, and allow extension of other attributes. Any model that includes these attributes forms relationships with other various attributes in order to perform analysis and simulation. - All information including the attributes are integrated to ensure continuity, accuracy and accessibility, and all information used during the life cycle of structures are supported. This means that when information of required resources is added as another attributes other than geometric

Integrated approach for power quality requirements at the point of connection

NARCIS (Netherlands)

Cobben, J.F.G.; Bhattacharyya, S.; Myrzik, J.M.A.; Kling, W.L.

2007-01-01

Given the nature of electricity, every party connected to the power system influences voltage quality, which means that every party also should meet requirements. In this field, a sound coordination among technical standards (system-related, installation-related and product-related) is of paramount

Quality assurance requirements for the operation of Swedish nuclear power plants

International Nuclear Information System (INIS)

1983-09-01

An adaption of NRC's 10 CFR 50, Appendis B (Quality Assurance Criteria for Nuclear Power and Fuel Reprocessing Plants) to Swedish conditions is presented. No references are given to regulations standards etc that influence the requirements and their adaption to local conditions. (Aa)

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition); Bezopasnost' atomnykh ehlektrostantsij: proektirovanie. Konkretnye trebovaniya bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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.

General requirements for concrete containment structures for CANDU nuclear power plants

International Nuclear Information System (INIS)

1993-07-01

This standard provides the general requirements used in the design, construction, testing, and commissioning of concrete containment structures for CANDU nuclear power plants designated as class containment and is directed to the owners, designers, manufacturers, fabricators, and constructors of the concrete components and parts

Space power subsystem automation technology

Science.gov (United States)

Graves, J. R. (Compiler)

1982-01-01

The technology issues involved in power subsystem automation and the reasonable objectives to be sought in such a program were discussed. The complexities, uncertainties, and alternatives of power subsystem automation, along with the advantages from both an economic and a technological perspective were considered. Whereas most spacecraft power subsystems now use certain automated functions, the idea of complete autonomy for long periods of time is almost inconceivable. Thus, it seems prudent that the technology program for power subsystem automation be based upon a growth scenario which should provide a structured framework of deliberate steps to enable the evolution of space power subsystems from the current practice of limited autonomy to a greater use of automation with each step being justified on a cost/benefit basis. Each accomplishment should move toward the objectives of decreased requirement for ground control, increased system reliability through onboard management, and ultimately lower energy cost through longer life systems that require fewer resources to operate and maintain. This approach seems well-suited to the evolution of more sophisticated algorithms and eventually perhaps even the use of some sort of artificial intelligence. Multi-hundred kilowatt systems of the future will probably require an advanced level of autonomy if they are to be affordable and manageable.

Analysis of power and frequency control requirements in view of increased decentralized production and market liberalization

International Nuclear Information System (INIS)

Roffel, B.; Boer, W.W. de

2003-01-01

This paper presents a systematic approach of the analysis of the minimum control requirements that are imposed on power producing units in the Netherlands, especially in the case when decentralized production increases. Also some effects of the liberalization on the control behavior are analyzed. First an overview is given of the amount and type of power production in the Netherlands, followed by a review of the control requirements. Next models are described, including a simplified model for the UCTE power system. The model was tested against frequency and power measurements after failure of a 558 MW production unit in the Netherlands. Agreement between measurements and model predictions proved to be good. The model was subsequently used to analyze the primary and secondary control requirements and the impact of an increase in decentralized power production on the fault restoration capabilities of the power system. Since the latter production units are not actively participating in primary and secondary control, fault restoration takes longer and becomes unacceptable when only 35% of the power producing units participate in secondary control. Finally, the model was used to study the impact of deregulation, especially the effect of 'block scheduling', on additional control actions of the secondary control. (Author)

78 FR 69543 - Record Requirements in the Mechanical Power Presses Standard

Science.gov (United States)

2013-11-20

... program). In such cases, OSHA would treat the weekly inspection as part of the periodic inspection.... OSHA-2013-0010] RIN 1218-AC80 Record Requirements in the Mechanical Power Presses Standard AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Direct final rule; request for comments...

78 FR 69606 - Record Requirements in the Mechanical Power Presses Standard

Science.gov (United States)

2013-11-20

... the inspection program). In such cases, OSHA would treat the weekly inspection as part of the periodic.... OSHA-2013-0010] RIN 1218-AC80 Record Requirements in the Mechanical Power Presses Standard AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Proposed rule; request for comments...

Flood control design requirements and flood evaluation methods of inland nuclear power plant

International Nuclear Information System (INIS)

Zhang Ailing; Wang Ping; Zhu Jingxing

2011-01-01

Effect of flooding is one of the key safety factors and environmental factors in inland nuclear power plant sitting. Up to now, the rule of law and standard systems are established for the selection of nuclear power plant location and flood control requirements in China. In this paper flood control standards of China and other countries are introduced. Several inland nuclear power plants are taken as examples to thoroughly discuss the related flood evaluation methods. The suggestions are also put forward in the paper. (authors)

EPPRD: An Efficient Privacy-Preserving Power Requirement and Distribution Aggregation Scheme for a Smart Grid.

Science.gov (United States)

Zhang, Lei; Zhang, Jing

2017-08-07

A Smart Grid (SG) facilitates bidirectional demand-response communication between individual users and power providers with high computation and communication performance but also brings about the risk of leaking users' private information. Therefore, improving the individual power requirement and distribution efficiency to ensure communication reliability while preserving user privacy is a new challenge for SG. Based on this issue, we propose an efficient and privacy-preserving power requirement and distribution aggregation scheme (EPPRD) based on a hierarchical communication architecture. In the proposed scheme, an efficient encryption and authentication mechanism is proposed for better fit to each individual demand-response situation. Through extensive analysis and experiment, we demonstrate how the EPPRD resists various security threats and preserves user privacy while satisfying the individual requirement in a semi-honest model; it involves less communication overhead and computation time than the existing competing schemes.

New requirements on safety of nuclear power plants according to the IAEA safety standards

International Nuclear Information System (INIS)

Misak, J.

2005-01-01

In this presentation author presents new requirements on safety of nuclear power plants according to the IAEA safety standards. It is concluded that: - New set of IAEA Safety Standards is close to completion: around 40 standards for NPPs; - Different interpretation of IAEA Safety Standards at present: best world practices instead of previous 'minimum common denominator'; - A number of safety improvements required for NPPs; - Requirements related to BDBAs and severe accidents are the most demanding due to degradation of barriers: hardware modifications and accident management; - Large variety between countries in implementation of accident management programmes: from minimum to major hardware modifications; -Distinction between existing and new NPPs is essential from the point of view of the requirements; WWER 440 reactors have potential to reflect IAEA Safety Standards for existing NPPs; relatively low reactor power offers broader possibilities

Prediction of requirements on labor force in the fuel and power generation sector

International Nuclear Information System (INIS)

Kaveckova, R.

1990-01-01

One of the aspects of socio-economic assessment of development is quantification of the expected requirements on the number of personnel. Predictions are discussed for the period before the year 2005 for solid fuel mining and treatment, gas production and bitumen mining, power and heat generation and also for the production of electricity and heat by nuclear power plants. They are based on an analysis of past development and the present state, on presumed implementation of various concept variants, on the type structure of nuclear power plants, on the rules of the electric power supply system, and also on foreign materials. It is expected that in 2005, nuclear power will employ 15,654 personnel. (M.D.). 4 tabs., 16 refs

12 CFR 714.5 - What is required if you rely on an estimated residual value greater than 25% of the original cost...

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 6 2010-01-01 2010-01-01 false What is required if you rely on an estimated residual value greater than 25% of the original cost of the leased property? 714.5 Section 714.5 Banks and Banking NATIONAL CREDIT UNION ADMINISTRATION REGULATIONS AFFECTING CREDIT UNIONS LEASING § 714.5 What is...

Research on Simulation Requirements and Business Architecture of Automated Demand Response in Power Sales Side Market Liberalization

Science.gov (United States)

Liu, Yiqun; Zhou, Pengcheng; Zeng, Ming; Chen, Songsong

2018-01-01

With the gradual reform of the electricity market, the power sale side liberalization has become the focus of attention as the key task of reform. The open power market provides a good environment for DR (Demand Response). It is of great significance to research the simulation requirements and business architecture of ADR (Automatic Demand Response) in power sale side market liberalization. Firstly, this paper analyzes the simulation requirements of ADR. Secondly, it analyzes the influence factors that the business development of ADR from five aspects after power sale side market liberalization. Finally, Based on ADR technology support system, the business architecture of ADR after power sale side market liberalization is constructed.

Analysis of Valve Requirements for High-Efficiency Digital Displacement Fluid Power Motors

DEFF Research Database (Denmark)

Rømer, Daniel; Johansen, Per; Pedersen, Henrik C.

2013-01-01

Digital displacement fluid power motors have been shown to enable high-efficiency operation in a wide operation range, including the part load range where conventional fluid power motors suffers from poor efficiencies. The use of these digital displacement motors set new requirements for the valve...... transition time and flow-pressure coefficient are normalized, leading to a presentation of the general efficiency map of the digital displacement motor. Finally the performance of existing commercial valves with respect to digital motors is commented....

Analysis of Balancing Requirements in Future Sustainable and Reliable Power Systems

International Nuclear Information System (INIS)

Frunt, J.

2011-01-01

This thesis elaborates on the rules for power balancing, provides a method for quantifying balancing requirements and examines the effect of future changes on balancing. Chapter 2 elaborates on system balancing and the different actors and entities in the electricity delivery system. The necessity and implementation of power balancing are explained. Also different subsequent markets (i.e., day-ahead markets, intraday markets and imbalance settlement systems) and options to trade electricity are discussed. As the research focusses mainly on the Netherlands, properties of the Dutch imbalance settlement system are analyzed. Based on this framework an in-depth analysis of imbalances and calls for balancing capacity with the corresponding prices is given. This shows the incentives to minimize the amount of imbalance in the system and to participate in the imbalance settlement system. Chapter 3 elaborates on the level of aggregation that the entities, involved in the imbalance settlement system, in electricity markets can have. Based on current market rules, incentives to either grow or shrink and by aggregating more or less entities are discussed. The level of aggregation will directly influence the functioning of the imbalance settlement system. It is shown that larger aggregations benefit more from the canceling out of imbalances. The imbalances of the Netherlands and Belgium have been aggregated to illustrate the possible benefits of aggregating multiple national imbalance settlement systems. The increased penetration of renewable generation strongly influences the planning and operation of the power system. As many renewable energy generators have a fluctuating power output, several methods are discussed in chapter 4 that can be used to classify and quantify the balancing requirements to counteract these fluctuations. Chapter 4 discusses the multiple existing classes of balancing capacity and the corresponding methods to quantify their needs. Due to the

Analysis of Balancing Requirements in Future Sustainable and Reliable Power Systems

Energy Technology Data Exchange (ETDEWEB)

Frunt, J.

2011-06-01

This thesis elaborates on the rules for power balancing, provides a method for quantifying balancing requirements and examines the effect of future changes on balancing. Chapter 2 elaborates on system balancing and the different actors and entities in the electricity delivery system. The necessity and implementation of power balancing are explained. Also different subsequent markets (i.e., day-ahead markets, intraday markets and imbalance settlement systems) and options to trade electricity are discussed. As the research focusses mainly on the Netherlands, properties of the Dutch imbalance settlement system are analyzed. Based on this framework an in-depth analysis of imbalances and calls for balancing capacity with the corresponding prices is given. This shows the incentives to minimize the amount of imbalance in the system and to participate in the imbalance settlement system. Chapter 3 elaborates on the level of aggregation that the entities, involved in the imbalance settlement system, in electricity markets can have. Based on current market rules, incentives to either grow or shrink and by aggregating more or less entities are discussed. The level of aggregation will directly influence the functioning of the imbalance settlement system. It is shown that larger aggregations benefit more from the canceling out of imbalances. The imbalances of the Netherlands and Belgium have been aggregated to illustrate the possible benefits of aggregating multiple national imbalance settlement systems. The increased penetration of renewable generation strongly influences the planning and operation of the power system. As many renewable energy generators have a fluctuating power output, several methods are discussed in chapter 4 that can be used to classify and quantify the balancing requirements to counteract these fluctuations. Chapter 4 discusses the multiple existing classes of balancing capacity and the corresponding methods to quantify their needs. Due to the

Greater-than-Class C low-level waste characterization. Appendix G: Evaluation of potential for greater-than-Class C classification of irradiated hardware generated by utility-operated reactors

International Nuclear Information System (INIS)

Cline, J.E.

1991-08-01

This study compiles and evaluates data from many sources to expand a base of data from which to estimate the activity concentrations and volumes of greater-than-Class C low-level waste that the Department of Energy will receive from the commercial power industry. Sources of these data include measurements of irradiated hardware made by or for the utilities that was classified for disposal in commercial burial sites, measurements of neutron flux in the appropriate regions of the reactor pressure vessel, analyses of elemental constituents of the particular structural material used for the components, and the activation analysis calculations done for hardware. Evaluations include results and assumptions in the activation analyses. Sections of this report and the appendices present interpretation of data and the classification definitions and requirements

Manpower and training requirements for operation and maintenance of Nuclear Power Plants

International Nuclear Information System (INIS)

Shah, J.C.

1975-01-01

The experience in India with regard to the staffing of nuclear power station operations and maintenance is encouraging in the sense that given the effort and time, developing countries should not find it unduly difficult to meet their requirements. (orig.) [de

Power uprates in nuclear power plants: international experiences and approaches for implementation

International Nuclear Information System (INIS)

Kang, Ki Sig

2008-01-01

The greater demand for electricity and the available capacity within safety margins in some operating NPPs are prompting nuclear utilities to request license modification to enable operation at a higher power level, beyond their original license provisions. Such plant modifications require an in-depth safety analysis to evaluate the possible safety impact. The analysis must consider the thermo hydraulic, radiological and structural aspects, and the plant behavior, while taking into account the capability of the structures, systems and components, and the reactor protection and safeguard systems set points. The purpose of this paper is to introduce international experiences and approaches for implementation of power uprates related to the reactor thermal power of nuclear power plants. The paper is intended to give the reader a general overview of the major processes, work products, issues, challenges, events, and experiences in the power uprates program. The process of increasing the licensed power level of a nuclear power plants is called a power uprate. One way of increasing the thermal output from a reactor is to increase the amount of fissile material in use. It is also possible to increase the core power by increasing the performance of the high power bundles. Safety margins can be maintained by either using fuels with a higher performance, or through the use of improved methods of analysis to demonstrate that the required margins are retained even at the higher power levels. The paper will review all types of power uprates, from small to large, and across various reactor types, including light and heavy water, pressurized, and boiling water reactors. Generally, however, the content of the report focuses on power uprates of the stretch and extended type. The International Atomic Energy Agency (IAEA) is developing a technical guideline on power uprates and side effects of power uprates in nuclear power plants

Requirements for auditing of quality assurance programs for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1979-01-01

Requirements and guidance are provided for establishing and implementing a system of internal and external audits of quality assurance programs for nuclear power plants, including the preparation, performance, reporting and follow-up of audits by both the auditing and the audited organizations. This standard is to be used in conjunction with ANSI N45.2

Discussion on several important safety requirements for the new nuclear power plant

International Nuclear Information System (INIS)

Yan Tianwen; Li Jigen; Zhang Lin; Feng Youcai; Jia Xiang; Li Wenhong

2013-01-01

Post the Fukushima nuclear accident, the Chinese government raised higher safety goals and safety requirements for the new nuclear power plant to be constructed. The paper expounded the important indicators of safety requirements and the aspects of safety modification that had been developed for the new NPPs. It also discussed and analyzed the main fields required by the new NPPs safety requirements in the safety goals, safety evaluation of sites, defenses of internal and external events, severe accident prevention and mitigation, design of reactor core, containment system and I and C system, and optimization of engineering measure, which gave some references to the design, construction and safety modifications of new NPPs in China. (authors)

Minimum power requirement for environmental control of aircraft

International Nuclear Information System (INIS)

Ordonez, Juan Carlos; Bejan, Adrian

2003-01-01

This paper addresses two basic issues in the thermodynamic optimization of environmental control systems (ECS) for aircraft: realistic limits for the minimal power requirement, and design features that facilitate operation at minimal power consumption. Four models are proposed and optimized. In the first, the ECS operates reversibly, the air stream in the cabin is mixed to one temperature, and the cabin experiences heat transfer with the ambient, across its insulation. The cabin temperature is fixed. In the second model, the fixed cabin temperature is assigned to the internal solid surfaces of the cabin, and a thermal resistance separates these surfaces from the air mixed in the cabin. In the third model, the ECS operates irreversibly, based on the bootstrap air cycle. The fourth model combines the ECS features of the third model with the cabin-environment interaction features of the second model. It is shown that in all models the temperature of the air stream that the ECS delivers to the cabin can be optimized for operation at minimal power. The effect of other design parameters and flying conditions is documented. The optimized air delivery temperature is relatively insensitive to the complexity of the model; for example, it is insensitive to the size of the heat exchanger used in the bootstrap air cycle. This study adds to the view that robustness is a characteristic of optimized complex flow systems, and that thermodynamic optimization results can be used for orientation in the pursuit of more complex and realistic designs

Use of prioritization in meeting regulatory requirements

International Nuclear Information System (INIS)

Bowling, M.L.; Sommers, D.A.; Girvin, L.M.

1993-01-01

The use of prioritization in the allocation of resources is certainly not a new idea. However, the degree to which prioritization must now be used is much greater than ever before. In the past, utilities generally allocated the necessary resources to meet all regulatory requirements and commitments. Prioritization was then applied to the remaining nonregulatory but required needs. This approach to resource allocation is no longer appropriate for the current and projected economic and operating environment. Key reasons for this conclusion are discussed in this paper by staff from Virginia Power

Uranium requirements for advanced fuel cycles in expanding nuclear power systems

International Nuclear Information System (INIS)

Banerjee, S.; Tamm, H.

1978-01-01

When considering advanced fuel cycle strategies in rapidly expanding nuclear power systems, equilibrium analyses do not apply. A computer simulation that accounts for system delay times and fissile inventories has been used to study the effects of different fuel cycles and different power growth rates on uranium consumption. The results show that for a given expansion rate of installed capacity, the main factors that affect resource requirements are the fissile inventory needed to introduce the advanced fuel cycle and the conversion (or breeding) ratio. In rapidly expanding systems, the effect of fissile inventory dominates, whereas in slowly expanding systems, conversion or breeding ratio dominates. Heavy-water-moderated and -cooled reactors, with their high conversion ratios, appear to be adaptable vehicles for accommodating fuel cycles covering a wide range of initial fissile inventories. They are therefore particularly suitable for conserving uranium over a wide range of nuclear power system expansion rates

General requirements for pressure-retaining systems and components in CANDU nuclear power plants

International Nuclear Information System (INIS)

1991-11-01

This standard specifies the general requirements for the design, fabrication and installation of pressure-retaining systems, components, and their supports in CANDU nuclear power plants. (16 figs., 2 tabs., 25 refs.)

CRISP. Requirements Specifications of Intelligent ICT Simulation Tools for Power Applications

Energy Technology Data Exchange (ETDEWEB)

Warmer, C.J.; Kester, J.C.P.; Kamphuis, I.G. [ECN Energy in the Built Environment and Networks, Petten (Netherlands); Carlsson, P [EnerSearch, Malmoe (Sweden); Fontela, M. [Laboratory of Electrical Engineering LEG, Grenoble (France); Gustavsson, R. [Blekinge Institute of Technology BTH, Karlskrona (Sweden)

2003-10-15

This report, deliverable D2.1 in the CRISP project, serves as a preparation report for the development of simulation tools and prototype software which will be developed in forthcoming stages of the CRISP project. Application areas for these simulations are: fault detection and diagnosis, supply and demand matching and intelligent load shedding. The context in which these applications function is the power network with a high degree of distributed generation, including renewables. In order to control a so called distributed grid we can benefit from a high level of distributed control and intelligence. This requires, on top of the power system network, an information and communication network.. We argue that such a network should be seen as an enabler of distributed control and intelligence. The applications, through which control and intelligence is implemented, then form a third network layer, the service oriented network. Building upon this three-layered network model we derive in this report the requirements for a simulation tool and experiments which study new techniques for fault detection and diagnostics and for simulation tools and experiments implementing intelligent load shedding and supply and demand matching scenarios. We also look at future implementation of these services within the three-layered network model and the requirements that follow for the core information and communication network and for the service oriented network. These requirements, supported by the studies performed in the CRISP Workpackage 1, serve as a basis for development of the simulation tools in the tasks 2.2 to 2.4.

CRISP. Requirements Specifications of Intelligent ICT Simulation Tools for Power Applications

International Nuclear Information System (INIS)

Warmer, C.J.; Kester, J.C.P.; Kamphuis, I.G.; Carlsson, P; Fontela, M.; Gustavsson, R.

2003-10-01

This report, deliverable D2.1 in the CRISP project, serves as a preparation report for the development of simulation tools and prototype software which will be developed in forthcoming stages of the CRISP project. Application areas for these simulations are: fault detection and diagnosis, supply and demand matching and intelligent load shedding. The context in which these applications function is the power network with a high degree of distributed generation, including renewables. In order to control a so called distributed grid we can benefit from a high level of distributed control and intelligence. This requires, on top of the power system network, an information and communication network.. We argue that such a network should be seen as an enabler of distributed control and intelligence. The applications, through which control and intelligence is implemented, then form a third network layer, the service oriented network. Building upon this three-layered network model we derive in this report the requirements for a simulation tool and experiments which study new techniques for fault detection and diagnostics and for simulation tools and experiments implementing intelligent load shedding and supply and demand matching scenarios. We also look at future implementation of these services within the three-layered network model and the requirements that follow for the core information and communication network and for the service oriented network. These requirements, supported by the studies performed in the CRISP Workpackage 1, serve as a basis for development of the simulation tools in the tasks 2.2 to 2.4

A Use Case Methodology to Handle Conflicting Controller Requirements for Future Power Systems

DEFF Research Database (Denmark)

Heussen, Kai; Uslar, Mathias; Tornelli, Carlo

2015-01-01

This paper proposes a standards based requirements elicitation and analysis strategy tailored for smart grid control structure development. Control structures in electric power systems often span across several systems and stakeholders. Requirements elicitation for such control systems therefore...... requires coordination across many stakeholders and it is challenging to achieve a consistent design. To enable an iterative and distributed development we suggest a conflict management approach as a modular element of the design strategy, focusing on conflict identification and tracing. The idea...

Forecasting manpower requirements for nuclear power plant construction

International Nuclear Information System (INIS)

Seltzer, N.; Schriver, W.R.

1978-01-01

This paper presents both the methodology and results of a segment of a comprehensive construction manpower demand forecasting system aimed at forecasting virtually all construction manpower requirements in the United States of America. The part of the system dealing with the demand for construction workers needed to build nuclear powered electricity generating plants is discussed here. The object of the system is to forecast manpower construction needs for each of 29 construction crafts on a monthly basis in each of 10 geographical regions of the United States. The method used is to establish profiles of the types of workers and time phasing required in the past. Profiling was done for different types of plants, different capacity classes, and different geographical locations. An appropriate worker profile matrix cannot simply be multiplied by the capacity of the proposed plant if the number of man-hours required per kilowatt of generating capacity is not constant. The value of this latter variable has changed considerably recently - presumably because of an increased awareness of environmental and safety considerations. Econometric techniques are used to forecast values for man-hours per kilowatt which are then multiplied by projected new capacity to be put in place. The resulting total man-hour requirement is then allocated over time and by craft through use of a worker profile matrix. The summary results indicate that 20 percent increases in man-hours required per kilowatt of capacity can be expected between 1977 and 1981. Total construction labour demand will rise from 65,700 work-years in 1977 to nearly 96,600 work-years in 1981. Forecasts of the actual number of different types of workers to be demanded in each month and in each region are available from the system. (author)

Considerations on the need for electricity storage requirements: Power versus energy

International Nuclear Information System (INIS)

Belderbos, Andreas; Virag, Ana; D’haeseleer, William; Delarue, Erik

2017-01-01

Highlights: • General storage principles are analyzed. • Storage units have different limitations (power versus energy). • Storage power and energy are required, dependent on residual profile. • Relationship between residual profile and optimal storage portfolio is derived. • Broadly applicable rules regarding optimal storage investments are presented. - Abstract: Different storage technologies enable an increasing share of variable renewable generation in the electricity system by reducing the temporal mismatch between generation and demand. Two storage ratings are essential to time-shift delivery of electricity to loads: electric power, or instantaneous electricity flow [W], and electric energy, or power integrated over time [Wh]. An optimal storage portfolio is likely composed of multiple technologies, each having specific power and energy ratings. This paper derives and explains the link between the shape of the time-varying demand and generation profiles and the amount of desirably installed storage capacity, both energy and power. An analysis is performed for individual storage technologies first, showing a link between the necessary power and energy capacity and the demand and generation profile. Then combinations of storage technologies are analyzed to reveal their mutual interaction in a storage portfolio. Results show an increase in desirability for storage technologies with low cost power ratings when the mismatch between generation and demand occurs in daily to weekly cycles. Storage technologies with low cost energy ratings are preferred when this mismatch occurs in monthly to seasonal cycles. The findings of this work can help energy system planners and policy makers to explain results from generation expansion planning studies and to isolate the storage benefits accountable to temporal arbitrage in broader electricity storage studies.

High power X-ray welding of metal-matrix composites

Energy Technology Data Exchange (ETDEWEB)

Rosenberg, Richard A.; Goeppner, George A.; Noonan, John R.; Farrell, William J.; Ma, Qing

1997-12-01

A method for joining metal-matrix composites (MMCs) by using high power x-rays as a volumetric heat source is provided. The method involves directing an x-ray to the weld line between two adjacent MMCs materials to create an irradiated region or melt zone. The x-rays have a power density greater than about 10{sup 4} watts/cm{sup 2} and provide the volumetric heat required to join the MMC materials. Importantly, the reinforcing material of the metal-matrix composites remains uniformly distributed in the melt zone, and the strength of the MMCs are not diminished. In an alternate embodiment, high power x-rays are used to provide the volumetric heat required to weld metal elements, including metal elements comprised of metal alloys. In an alternate embodiment, high power x-rays are used to provide the volumetric heat required to weld metal elements, including metal elements comprised of metal alloys.

Lithuanian requirements for ageing management of systems and components important to safety of nuclear power plant

International Nuclear Information System (INIS)

Ramanauskiene, A.

2000-01-01

In this paper the Lithuanian requirements for ageing management of systems and components important to safety of Ignalina nuclear power plant (two RBMK-1500 water-cooled graphite moderated channel-type power reactors) are presented

Design requirements document for the phase 1 privatization electrical power system

Energy Technology Data Exchange (ETDEWEB)

Singh, G.

1997-10-31

The electrical system for the Phase 1 privatization facilities will support the TWRS mission by providing the electrical power to the Phase 1 privatized facilities. This system will receive power from the Department of Energy-Richland Operations (RL) A4-8 230 kV transmission system powered from Bonneville Power Administration (BPA) Ashe and Midway 230 kV Substations. The existing RL 230 kV transmission line will be modified and looped 1021 into the new 230 kV substation bus. The new substation will be located in the vicinity of the privatized facilities, approximately 3.2 km (2 mi) south of the existing RL A4-8 230 kV transmission line. The substation will be capable of providing up to 40 MW of electrical power to support the Phase 1 privatization facilities and has space for accommodating future expansions. The substation will require at least two 230-13.8 kV transformers, 13.8 kV split bus switchgear, switchgear building, grounding transformers, instrument transformers, control and monitoring equipment, associated protection and isolation devices, lightning protection, yard lighting, cable and raceways, and infrastructure needed to provide desired availability and reliability. The power from the 13.8 kV switchgear located in the switchgear building will be delivered at the privatization facilities site boundaries. The 13.8 kV distribution system inside the privatization facilities site boundaries is the responsibility of the privatization contract.

Design requirements document for the phase 1 privatization electrical power system

International Nuclear Information System (INIS)

Singh, G.

1997-01-01

The electrical system for the Phase 1 privatization facilities will support the TWRS mission by providing the electrical power to the Phase 1 privatized facilities. This system will receive power from the Department of Energy-Richland Operations (RL) A4-8 230 kV transmission system powered from Bonneville Power Administration (BPA) Ashe and Midway 230 kV Substations. The existing RL 230 kV transmission line will be modified and looped 1021 into the new 230 kV substation bus. The new substation will be located in the vicinity of the privatized facilities, approximately 3.2 km (2 mi) south of the existing RL A4-8 230 kV transmission line. The substation will be capable of providing up to 40 MW of electrical power to support the Phase 1 privatization facilities and has space for accommodating future expansions. The substation will require at least two 230-13.8 kV transformers, 13.8 kV split bus switchgear, switchgear building, grounding transformers, instrument transformers, control and monitoring equipment, associated protection and isolation devices, lightning protection, yard lighting, cable and raceways, and infrastructure needed to provide desired availability and reliability. The power from the 13.8 kV switchgear located in the switchgear building will be delivered at the privatization facilities site boundaries. The 13.8 kV distribution system inside the privatization facilities site boundaries is the responsibility of the privatization contract

Guideline on radiation protection requirements for ionizing radiation shielding in nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

The guideline which entered into force on 1 May 1988 stipulates the radiation protection requirements for shielding against ionizing radiation to be met in the design, construction, commissioning, operation, and decommissioning of nuclear power plants

Thermodynamic and economic analysis on geothermal integrated combined-cycle power plants

International Nuclear Information System (INIS)

Bettocchi, R.; Cantore, G.; Negri di Montenegro, G.; Gadda, E.

1992-01-01

This paper considers geothermal integrated power plants obtained matching a geothermal plant with, a two pressure level combined plant. The purpose of the paper is the evaluation of thermodynamic and economic aspects on geothermal integrated combined-cycle power plant and a comparison with conventional solutions. The results show that the integrated combined plant power is greater than the sum of combined cycle and geothermal plant powers considered separately and that the integrated plant can offer economic benefits reaching the 16% of the total capital required

Neural net based determination of generator-shedding requirements in electric power systems

Energy Technology Data Exchange (ETDEWEB)

Djukanovic, M [Electrical Engineering Inst. ' Nikola Tesla' , Belgrade (Yugoslavia); Sobajic, D J; Pao, Y -H [Case Western Reserve Univ., Cleveland, OH (United States). Dept. of Electrical Engineering and Applied Physics Case Western Reserve Univ., Cleveland, OH (United States). Dept. of Computer Engineering and Science AI WARE Inc., Cleveland, OH (United States)

1992-09-01

This paper presents an application of artificial neural networks (ANN) in support of a decision-making process by power system operators directed towards the fast stabilisation of multi-machine systems. The proposed approach considers generator shedding as the most effective discrete supplementary control for improving the dynamic performance of faulted power systems and preventing instabilities. The sensitivity of the transient energy function (TEF) with respect to changes in the amount of dropped generation is used during the training phase of ANNs to assess the critical amount of generator shedding required to prevent the loss of synchronism. The learning capabilities of neural nets are used to establish complex mappings between fault information and the amount of generation to be shed, suggesting it as the control signal to the power system operator. (author)

Security of Supply: A Pan-European Approach - The Opportunities and Requirements of Greater Cooperation Across European Electricity Markets

International Nuclear Information System (INIS)

Ulreich, S.

2015-01-01

In December 2014, Prognos AG (Berlin/Basel) was commissioned by the Weltenergierat - Deutschland e.V to prepare a study on the potential of greater cooperation across European electricity markets. The focus of the analysis was to address the extent to which closer cooperation on ensuring generation adequacy can lead to cost reductions. Fifteen countries were analysed: seven members of the Pentalateral Energy Forum (PLEF, DE, BE, NL, LU, FR, AT and CH) and eight additional bordering countries (PL, IT, UK, ES, DK, CZ, PT and IE). Today, ensuring generation adequacy takes place at a national level and international effects are not taken into account. However, if cross-border effects are considered adequacy considerations at a national level can be relieved, e.g.: load peaks in Europe do not occur simultaneously and the feedin from renewable energy takes place at different times. Potential savings arise, as less capacity needs to be secured by conventional power plants. An indicator for this in the present study is the so-called residual load. The study is based on analyses of all existing data relating to hourly load and feed-in from renewable energy for the period from 2009 to 2014. In addition, two scenarios (based on Visions V1 and V3 of ENTSO-E's System Outlook and Adequacy Forecast) and numerous sensitivities for 2030 were generated. As the variability of the results is highly dependent on weather conditions, 48 simulations of wind power (sensitivities) established a broad corridor of results. For this reason, ranges are used in the presentation of results. The approach makes this study the most comprehensive analysis to date of the potential of closer cooperation with respect to ensuring generation adequacy. With the assumption of no grid congestion, the study reaches the following results: 1) Reduction of residual load: In contrast to a national assessment scheme, under a collective assessment scheme the residual load will reduce by 2 to 15 gigawatts (most

Design of a Solid-State Fast Voltage Compensator for klystron modulators requiring constant AC power consumption

CERN Document Server

Aguglia, Davide; Viarouge, Philippe; Cros, Jerome

2014-01-01

This paper proposes a novel topological solution for klystron modulators integrating a Fast Voltage Compensator which allows an operation at constant power consumption from the utility grid. This kind of solution is mandatory for the CLIC project under study, which requires several hundreds of synchronously operated klystron modulators for a total pulsed power of 39 GW. The topology is optimized for the challenging CLIC specifications, which require a very precise output voltage flat-top as well as fast rise and fall times (3µs). The Fast Voltage Compensator is integrated in the modulator such that it only has to manage the capacitor charger current and a fraction of the charging voltage. Consequently, its dimensioning power and cost is minimized.

Assessment of infrastructure development requirements for embarking on nuclear power program in Macedonia

International Nuclear Information System (INIS)

Popov, N.; Ilijovski, I.; Popovski, V.

2015-01-01

Over the past decades nuclear energy has been proven as reliable and economical energy supply that is capable of meeting demanding energy market requirements. Many countries around the world consider entering into new nuclear energy programs and building new power reactors for satisfying their increasing electrical energy needs. A nuclear power program is a major undertaking requiring careful planning, preparation and investment, and human resources for building adequate nuclear infrastructure. Preparations for making a decision to enter into a new nuclear energy program requires a significant amount of financial and human resources, time, and assistance from already developed countries and international nuclear organizations. The International Atomic Energy Agency (IAEA) from Vienna provides technical help, financial assistance, and documented knowledge that are important for countries facing the challenge of entering nuclear programs for the first time. The IAEA organizes technical courses and information exchange meetings for new countries at which experiences and lessons learned are provided to new countries. This paper describes the key activities in the process for making a decision to enter a new nuclear energy program. It describes the efforts currently being conducted in the Republic of Macedonia in the direction of collecting information, performing various feasibility studies, and engaging in regional cooperation for utilizing experiences of the regional countries in performing such activities, and in developing their nuclear power programs. This paper also provides an overview of the IAEA documents and recommendations that are relevant for this topic

Impact of extreme load requirements and quality assurance on nuclear power plant costs

International Nuclear Information System (INIS)

Stevenson, J.D.

1993-01-01

Definitive costs, applicable to nuclear power plant concrete structures, as a function of National Regulatory Requirements, standardization, the effect of extreme load design associated with both design basis accidents and extreme external events and quality assurance are difficult to develop since such effects are interrelated and not only differ widely from country to country, project to project but also vary in time. Table 1 shows an estimate of the of the overall plant cost effects of external event extreme load design on nuclear power plant design for the U.S -and selected foreign countries for which experience with LWRs exist- Germany is the most expensive primarily due to a military aircraft crash resistance. However, the German requirement for 4 safeguards trains rather than 2 and the containment design requirement to consider one Steam Generator blowdown concurrent with a RCS blowdown. This presentation will concentrate on the direct current impact extreme load design and quality assurance have on concrete structures, systems and components for nuclear plants. This presentation is considered timely due to the increased interest in the c potential backfit of Eastern European nuclear power stations of the WWER 440 and WWER 1000 types which typically did not consider the extreme loads identified in Table 1 and accident loads in Table 3 and quality assurance in Table 5 in their original design. Concrete structures in particular are highlighted because they typically form the last barrier to radioactive release from the containment and other Safety Related Structures

Cooling water requirements and nuclear power plants

International Nuclear Information System (INIS)

Rao, T.S.

2010-01-01

Indian nuclear power programme is poised to scuttle the energy crisis of our time by proposing joint ventures for large power plants. Large fossil/nuclear power plants (NPPs) rely upon water for cooling and are therefore located near coastal areas. The amount of water a power station uses and consumes depends on the cooling technology used. Depending on the cooling technology utilized, per megawatt existing NPPs use and consume more water (by a factor of 1.25) than power stations using other fuel sources. In this context the distinction between 'use' and 'consume' of water is important. All power stations do consume some of the water they use; this is generally lost as evaporation. Cooling systems are basically of two types; Closed cycle and Once-through, of the two systems, the closed cycle uses about 2-3% of the water volumes used by the once-through system. Generally, water used for power plant cooling is chemically altered for purposes of extending the useful life of equipment and to ensure efficient operation. The used chemicals effluent will be added to the cooling water discharge. Thus water quality impacts on power plants vary significantly, from one electricity generating technology to another. In light of massive expansion of nuclear power programme there is a need to develop new ecofriendly cooling water technologies. Seawater cooling towers (SCT) could be a viable option for power plants. SCTs can be utilized with the proper selection of materials, coatings and can achieve long service life. Among the concerns raised about the development of a nuclear power industry, the amount of water consumed by nuclear power plants compared with other power stations is of relevance in light of the warming surface seawater temperatures. A 1000 MW power plant uses per day ∼800 ML/MW in once through cooling system; while SCT use 27 ML/MW. With the advent of new marine materials and concrete compositions SCT can be constructed for efficient operation. However, the

Land Use Requirements of Modern Wind Power Plants in the United States

Energy Technology Data Exchange (ETDEWEB)

Denholm, P.; Hand, M.; Jackson, M.; Ong, S.

2009-08-01

This report provides data and analysis of the land use associated with modern, large wind power plants (defined as greater than 20 megawatts (MW) and constructed after 2000). The analysis discusses standard land-use metrics as established in the life-cycle assessment literature, and then discusses their applicability to wind power plants. The report identifies two major 'classes' of wind plant land use: 1) direct impact (i.e., disturbed land due to physical infrastructure development), and 2) total area (i.e., land associated with the complete wind plant project). The analysis also provides data for each of these classes, derived from project applications, environmental impact statements, and other sources. It attempts to identify relationships among land use, wind plant configuration, and geography. The analysts evaluated 172 existing or proposed projects, which represents more than 26 GW of capacity. In addition to providing land-use data and summary statistics, they identify several limitations to the existing wind project area data sets, and suggest additional analysis that could aid in evaluating actual land use and impacts associated with deployment of wind energy.

Pulse power requirements for large aperture optical switches based on plasma electrode Pockels cells

International Nuclear Information System (INIS)

Rhodes, M.A.; Taylor, J.

1992-06-01

We discuss very large-aperture optical switches (greater than 30 x 30 cm) as an enabling technology for inertial confinement fusion drivers based on multipass laser amplifiers. Large-scale laser fusion drivers such as the Nova laser have been based on single-pass amplifier designs in part because of the unavailability of a suitable large-aperture switch. We are developing an optical switch based on a Pockels cell employing plasma-electrodes. A plasma-electrode Pockels cell (PEPC) is a longitudinal-mode Pockels cell in which a plasma discharge is formed on each side of an electro-optic crystal (typically KDP or deuterated KDP, often designated KD*P). The plasmas formed on either side of the crystal act as transparent electrodes for a switching-pulse and are intended to allow uniform charging of the entire crystal. The switching-pulse is a nominally rectangular high-voltage pulse equal to the half-wave voltage V x ( 8 kV for KD*P or 17 kV for KDP) and is applied across the crystal via the plasma-electrodes. When the crystal is charged to V x , the polarization of an incoming, linearly polarized, laser beam is rotated by 90 degree. When used in conjunction with an appropriate, passive polarizer, an optical switch is thus realized. A switch with a clear aperture of 37 x 37 cm is now in construction for the Beamlet laser which will serve as a test bed for this switch as well as other technologies required for an advanced NOVA laser design. In this paper, we discuss the unique power electronics requirements of PEPC optical switches

Regulatory requirements for nuclear power plant site selection in Malaysia-a review.

Science.gov (United States)

Basri, N A; Hashim, S; Ramli, A T; Bradley, D A; Hamzah, K

2016-12-01

Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

The financing of nuclear power plants

International Nuclear Information System (INIS)

2009-01-01

Many countries have recognised that greater use of nuclear power could play a valuable role in reducing carbon dioxide emissions. However, given the high capital cost and complexity of nuclear power plants, financing their construction often remains a challenge. This is especially true where such financing is left to the private sector in the context of competitive electricity markets. This study examines the financial risks involved in investing in a new nuclear power plant, how these can be mitigated, and how projects can be structured so that residual risks are taken by those best able to manage them. Given that expansion of nuclear power programmes will require strong and sustained government support, the study highlights the role of governments in facilitating and encouraging investment in new nuclear generating capacity

Facing the facts: the suspension of a design requirement applicable to nuclear power reactor effluents

International Nuclear Information System (INIS)

Amado, Valeria; Biaggio, Alfredo; Canoba, Analia; Curti, Adriana

2008-01-01

A design requirement aimed at limiting the discharge of globally dispersed long-lived radionuclides released by nuclear power reactors was in force in Argentine since 1979 till recently. The practical results of such regulatory measure was the need to retain C-14 in the PHWR under construction, as well as in furniture heavy water reactors to be built in the country. This paper explains the basis of such requirement, which was formulated as a collective dose constraint per unit of energy generated, and the main assumptions that triggered it. The differences between the assumptions made at the time and the reality of nuclear power generation at the beginning of the 21 st century, as well as their implications in relation to the requirement are described, including the Suess effect and its impact in the total dose due to C-14. Finally, the facts that made no longer reasonable to keep in force the above mentioned requirement are presented. (author)

A study for the establishment of regulatory requirement and evaluation guide for station blackout in nuclear power plants

International Nuclear Information System (INIS)

Lim, J. H.; Koo, C. S.; Joo, W. P.; Oh, S. H.; Shin, W. K.

1999-01-01

The consequence of SBO event could be a severe accident unless AC power was restored within a proper time, because many safety systems depend upon AC power. Based on the severity, the SBO has been extensively studied since it was identified as Unresolved Safety Issue at USNRC. The resolution of those studies is a rule-making such as 10 CFR 50.63 and Regulatory Guide 1.155. But there is no regulatory requirements of SBO for an operating domestic nuclear power plant up to the present time. This tudy has established SBO rule(regulatory requirements and evaluation guides) for an operating PWR type of the operating nuclear power plants in Korea

Ergonomic requirements on computer-based information- and handling engineering in nuclear power plants

International Nuclear Information System (INIS)

Fassmann, W.

2002-01-01

This project provides regulatory authorities with a set of criteria for evaluating hybrid man-machine interfaces in nuclear power plant control rooms from a human factors point of view. Such standards are necessary for two reasons: (1) More and more computerised information and control systems have been and will be introduced in nuclear power plant control rooms. One possible result of this trend will be the creation of hybrid man machine interfaces which will provide both conventional and computer-based display and control devices. (2) Available rules and regulations do not contain detailed requirements on how to integrate both types of interface in such a way that plant operation by means of hybrid interfaces will be performed at least as reliably and safely as by means of conventional ones. To fill this gap, criteria and methods were developed which support practical checks of requirements to be applied to hybrid control rooms. This approach is based on state of the art methods and criteria in ergonomics. It makes it possible to analyse and to describe personnel's actions in a consistent and structured way in order to provide the information which is necessary for evaluating human reliability of task performance. Reliability can be evaluated with respect to - accuracy of required information on displays, - networking of tasks, - possibilities of interrupting and cancelling measures which have already been initiated, - possibility to carry out required manuel actions, - level of mental work-strain, - workload level, - probability of erroneous actions. This method is part of a catalogue of recommendations for evaluating hybrid nuclear power plant control rooms. The catalogue also contains recommendations for the design of computerised parts of the man-machine-interface. Application of these design recommendations will help create favourable conditions for an acceptable level of work-strain and for reliable task performance. (orig.) [de

New safety standards of nuclear power station with no requirements of site evaluation. No public dose limit published with possible inappropriateness of reactor site

International Nuclear Information System (INIS)

Takitani, Koichi

2013-01-01

Nuclear Regulation Authority was preparing new safety standards in order to aim at starting safety reviews of existing nuclear power station in July 2013. This article commented on issues of major accident, which was defined as severely damaged core event. Accumulated dose at the site boundary of the Fukushima Daiichi Nuclear Power Station totaled to about 234 mSv on March just after the accident with rare gas of 500 PBq, iodine 131 of 500 PBq, cesium 134 of 10 PBq and cesium 137 of 10 PBq released to the atmosphere, which was beyond 100 mSv. As measures for preventing containment vessel failure after core severely damaged, filtered venting system was required to be installed for low radiological risk to the public. However filter was not effective to rare gas. Accumulated doses at the site boundary of several nuclear power stations after filtered venting with 100% release of rare gas could be estimated to be 2-37 Sv mostly depending on the site condition, which might be surely greater than 100 mSv. Omitting site evaluation for major accident, which was beyond design basis accident, was great concern. (T. Tanaka)

Determination of Power Required through Accelerated Flight with Application to Unmanned Vehicles

Science.gov (United States)

Soltmann, Lars Michael

Power required analysis is an important element of aircraft performance. The primary method for measuring this parameter is the classic PIW-VIW (power and velocity independent of weight) method which was developed in the first half of the 20th century. This method was originally developed for use with manned aircraft and therefore has some shortcomings when applied to unmanned aircraft, specifically those that are remotely piloted. The proposed method estimates the lift and drag models using the maximum likelihood technique which was applied to data acquired through acceleration and deceleration runs under the assumption that the pitch rate and lateral dynamics are negligible. The acceleration runs were performed by applying full throttle while the aircraft was flying just above the stall velocity and allowing it to naturally accelerate to maximum level flight velocity. The deceleration runs were performed in the opposite manner where the throttle was set to zero while the aircraft was ying at maximum velocity and allowed to naturally slow down until stall was reached. The collected data is reduced using the PIW-VIW technique whereby a single power curve is generated that is independent of aircraft weight and air density. Simulations indicate that deviations from the designed maneuvers, such as altitude changes and low pitch rates, are acceptable and do not change the resulting power curves. A hard limit on what constitutes low pitch rate was difficult to establish as system noise played a large role in determining the signal-to-noise ratio limit on the pitch rate. However, based on a model analysis it was concluded that the pitch rate could be safely ignored without consequences to the results. A low cost Raspberry Pi data collection system was designed for use on two test aircraft, the commercially available Nexstar and a reconfigurable research aircraft called Astraeus. Data points using the classic PIW-VIW method were collected during the flight test program

Indian power sector: past, present and future

International Nuclear Information System (INIS)

Varma, C.V.J.; Lal, P.K.

1994-01-01

In India population and economic growth is expected to create serious power shortages triggering the need for new power generation capacity. The situation is worsened on account of stagnant conditions prevailing in the country during the past few years. The opening of economy to the global market is expected to usher in an increased economic growth bringing in its wake greater demand for power. It will, thus, be seen that to cater these requirements the power sector industry in the country will have to grow at a much faster rate in the near future. However, to have a correct perspective of the emerging scenario, it might be worthwhile to have a look at the past patterns of development. (author). 9 refs., 5 tabs

Environmental requirements at hydroelectric power plants

International Nuclear Information System (INIS)

Cada, G.F.

1993-01-01

Hydroelectric power is the most mature and widely implemented of the renewable energy technologies. The energy of flowing water has been used to perform work directly since ancient times, and the use of hydropower turbines to generate electricity traces back to the 19th century. Two commonly used turbine types, the Francis and Kaplan turbines, are essentially refinements of the simple reaction turbine of Hero of Alexandria, dating from about 100 B.C. (NAS 1976). Hydroelectric power production provides over 10% of the net electrical generation in the US, more than petroleum or natural gas and far more than the other renewable energy technologies combined. On a regional basis, hydroelectric power represents 14% of the net electrical power generation in the Rocky Mountain states and nearly 63% along the Pacific Coast. Those states that have the largest percentages of their electricity generated by hydropower (e.g., Idaho, Oregon, Montana, and Washington) also tend to have the lowest average cost of electricity per kilowatt-hour

Advances in high-power rf amplifiers

International Nuclear Information System (INIS)

Tallerico, P.J.

1979-01-01

Several powerful accelerators and storage rings are being considered that will require tens or even hundreds of megawatts of continuous rf power. The economics of such large machines can be dictated by the cost and efficiency of the rf amplifiers. The overall design and performance of such narrow-band amplifiers, operating in the 50- to 1500-MHz region, are being theoretically studied as a function of frequency to determine the optimum rf amplifier output power, gain, efficiency, and dc power requirements. The state of the art for three types of amplifiers (gridded tubes, klystrons, and gyrocons) is considered and the development work necessary to improve each is discussed. The gyrocon is a new device, hence its various embodiments are discussed in detail. The Soviet designs are reviewed and the gyrocon's strengths and weaknesses are compared to other types of microwave amplifiers. The primary advantages of the gyrocon are the very large amount of power available from a single device and the excellent efficiency and stable operation. The klystron however, has much greater gain and is simpler mechanically. At very low frequencies, the small size of the gridded tube makes it the optimum choice for all but the most powerful systems

Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

Science.gov (United States)

Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

1981-01-01

A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study

International Nuclear Information System (INIS)

Tyacke, M.

1993-08-01

This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood

Land-Use Requirements for Solar Power Plants in the United States

Energy Technology Data Exchange (ETDEWEB)

Ong, S.; Campbell, C.; Denholm, P.; Margolis, R.; Heath, G.

2013-06-01

This report provides data and analysis of the land use associated with utility-scale ground-mounted solar facilities, defined as installations greater than 1 MW. We begin by discussing standard land-use metrics as established in the life-cycle assessment literature and then discuss their applicability to solar power plants. We present total and direct land-use results for various solar technologies and system configurations, on both a capacity and an electricity-generation basis. The total area corresponds to all land enclosed by the site boundary. The direct area comprises land directly occupied by solar arrays, access roads, substations, service buildings, and other infrastructure. As of the third quarter of 2012, the solar projects we analyze represent 72% of installed and under-construction utility-scale PV and CSP capacity in the United States.

Statement on safety requirements concerning the long-term operation of the Muehleberg nuclear power station

International Nuclear Information System (INIS)

2012-12-01

This report published by the Swiss Federal Nuclear Safety Inspectorate ENSI investigates the safety requirements with respect to the long-term operation of the Muehleberg nuclear power station in Switzerland. Relevant international requirements and Swiss legal stipulations concerning the long-term operation of the power station are stated. The management of aging processes is looked at. The regular verification of the integrity of various plant components such as containments, piping, steam generation system, etc. is looked at in detail. The state-of-the-art concerning deterministic accident analyses and refitting technology are discussed, as are automated safety systems. The applicable laws, decrees and guidelines are listed in appendices

Power generation using photovoltaic induction in an isolated power network

International Nuclear Information System (INIS)

Kalantar, M.; Jiang, J.

2001-01-01

Owing to increased emphasis on renewable resources, the development of suitable isolated power generators driven by energy sources, the development of suitable isolated power generators driven by energy sources such as photovoltaic, wind, small hydroelectric, biogas and etc. has recently assumed greater significance. A single phase capacitor self excited induction generator has emerged as a suitable candidate of isolated power sources. This paper presents performance analysis of a single phase self-excited induction generator driven by photovoltaic (P V) system for low power isolated stand-alone applications. A single phase induction machine can work as a self-excited induction generator when its rotor is driven at suitable speed by an photovoltaic powered do motor. Its excitation is provided by connecting a single phase capacitor bank at a stator terminals. Either to augment grid power or to get uninterrupted power during grid failure stand-alone low capacity ac generators are used. These are driven by photovoltaic, wind power or I C engines using kerosene, diesel, petrol or biogas as fuel. Self-excitation with capacitors at the stator terminals of the stator terminals of the induction machines is well demonstrated experimentally on a P V powered dc motor-induction machine set. The parameters and the excitation requirements of the induction machine run in self-excited induction generator mode are determined. The effects of variations in prime mover speed,terminal capacitance and load power factor on the machine terminal voltage are studied

Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

Improvement of uranium production efficiency to meet China's nuclear power requirements

International Nuclear Information System (INIS)

Zhang, R.

1997-01-01

Recently China put the Qinshan Nuclear Power Plant, with an installed capacity of 300 MW, in the province of Zhejiang and the Daya Bay Nuclear Power Plant, with a total installed capacity of 2 x 900 MW, in commercial operation. China plans a rapid growth in nuclear power from 1995 to 2010. China's uranium production will therefore also enter a new period with nuclear power increasing. In order to meet the demand of nuclear power for uranium special attention has been paid to both technical progress improvement using management with the aim of reducing the cost of uranium production. The application of the trackless mining technique has enhanced the uranium mining productivity significantly. China has produced a radiometric sorter, model 5421-2 for pre-concentrating uranium run-of-mine ore. This effectively increases the uranium content in mill feed and decreases the operating cost of hydrometallurgical treatment. The in situ leach technique after blasting is applied underground in the Lantian Mine, in addition to the surface heap leaching, and has obtained a perfect result. The concentrated acid-curing, and ferric sulphate trickle leaching process, will soon be used in commercial operation for treating uranium ore grading -5 to -7 mm in size. The annual production capability of the Yining Mine will be extended to 100 tonnes U using improving in situ leaching technology. For the purpose of improving the uranium production efficiency much work has been done optimizing the distribution of production centres. China plans to expand its uranium production to meet the uranium requirements of the developing nuclear power plants. (author). 4 tabs

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition); Seguridad de las centrales nucleares: Diseno. Requisitos de seguridad especificos

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and 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. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. 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.

Operational technology for greater confinement disposal

International Nuclear Information System (INIS)

Dickman, P.T.; Vollmer, A.T.; Hunter, P.H.

1984-12-01

Procedures and methods for the design and operation of a greater confinement disposal facility using large-diameter boreholes are discussed. It is assumed that the facility would be located at an operating low-level waste disposal site and that only a small portion of the wastes received at the site would require greater confinement disposal. The document is organized into sections addressing: facility planning process; facility construction; waste loading and handling; radiological safety planning; operations procedures; and engineering cost studies. While primarily written for low-level waste management site operators and managers, a detailed economic assessment section is included that should assist planners in performing cost analyses. Economic assessments for both commercial and US government greater confinement disposal facilities are included. The estimated disposal costs range from $27 to $104 per cubic foot for a commercial facility and from $17 to $60 per cubic foot for a government facility. These costs are based on average site preparation, construction, and waste loading costs for both contact- and remote-handled wastes. 14 figures, 22 tables

Planning for greater confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Luner, C.; Meshkov, N.K.; Trevorrow, L.E.; Yu, C.

1985-01-01

A report that provides guidance for planning for greater-confinement disposal (GCD) of low-level radioactive waste is being prepared. The report addresses procedures for selecting a GCD technology and provides information for implementing these procedures. The focus is on GCD; planning aspects common to GCD and shallow-land burial are covered by reference. Planning procedure topics covered include regulatory requirements, waste characterization, benefit-cost-risk assessment and pathway analysis methodologies, determination of need, waste-acceptance criteria, performance objectives, and comparative assessment of attributes that support these objectives. The major technologies covered include augered shafts, deep trenches, engineered structures, hydrofracture, improved waste forms, and high-integrity containers. Descriptive information is provided, and attributes that are relevant for risk assessment and operational requirements are given. 10 refs., 3 figs., 2 tabs

Requirement analysis for autonomous systems and intelligent agents in future Danish electric power systems

DEFF Research Database (Denmark)

Saleem, Arshad; Lind, Morten

2010-01-01

we review innovative control architectures in electric power systems such as Microgrids, Virtual power plants and Cell based systems. We evaluate application of autonomous systems and intelligent agents in each of these control architectures particularly in the context of Denmark's strategic energy...... plans. The second part formulates a flexible control architecture for electric power systems with very high penetration of distributed generation. This control architecture is based upon the requirements identified in the first part. We also present development of a software framework to test......Denmark has already achieved a record of 20% penetration of wind power and now moving towards even higher targets with an increasing part of the electricity produced by distributed generators (DGs). In this paper we report work from a sub activity "subgrid design" of the EcoGrid.dk project. First...

A framework for regulatory requirements and industry standards for new nuclear power plants

International Nuclear Information System (INIS)

Duran, Felicia A.; Camp, Allen L.; Apostolakis, George E.; Golay, Michael W.

2000-01-01

This paper summarizes the development of a framework for risk-based regulation and design for new nuclear power plants. Probabilistic risk assessment methods and a rationalist approach to defense in depth are used to develop a framework that can be applied to identify systematically the regulations and standards required to maintain the desired level of safety and reliability. By implementing such a framework, it is expected that the resulting body of requirements will provide a regulatory environment that will ensure protection of the public, will eliminate the burden of requirements that do not contribute significantly to safety, and thereby will improve the market competitiveness of new plants. (author)

ASDEX Upgrade-JT-60U comparison and ECRH power requirements for NTM stabilization in ITER

International Nuclear Information System (INIS)

Urso, L.; Zohm, H.; Maraschek, M.; Poli, E.; Isayama, A.

2010-01-01

Neoclassical tearing modes (NTMs) are experimentally controlled with local electron cyclotron current drive (ECCD) and the island width decay during NTM stabilization is modelled using the so-called modified Rutherford equation (MRE). In this paper, a modelling of the MRE is carried out and simulations of the island width decay are compared with the experimentally observed ones in order to fit the two free machine-independent parameters present in the equation. A systematic study on a database of NTM stabilization discharges from ASDEX Upgrade and JT-60U is done for extrapolating the ECCD power requirements for ITER. The extrapolation to ITER of the NTM stabilization results from ASDEX Upgrade and JT-60U shows that 10 MW of ECCD power are enough to stabilize large NTMs. The 10 MW power estimate for ITER is based on the assumption that the free parameters in the MRE are machine independent. Indeed, this assumption is verified in this paper for ASDEX Upgrade and JT-60U. An interesting consequence of the relatively modest power requirement for ITER is that the installed 20 MW will suffice for simultaneous 2/1 and 3/2 NTM stabilization.

Energy management system for power distribution. Interfaces and data communication requirements

International Nuclear Information System (INIS)

Koponen, P.; Lemstroem, B.; Ikonen, J.

1995-01-01

The opening of the electricity market for competition in Finland creates new requirements for the information systems and data communication in distribution utilities. Energy management systems for distribution utilities are needed with interfaces that make it possible to separate the network business from the energy trade business. However, these interfaces should also support optimization of the whole energy supply system of the country. In this report the interfaces and data communication requirements of the energy management system of the electricity trade business are analyzed. To support this subfunctions of the energy management have been analyzed. It was realized that the amount of necessary data transfer and optimization of the national power system both depend strongly on the general rules of the energy markets. (author)

18 CFR 292.208 - Special requirements for hydroelectric small power production facilities located at a new dam or...

Science.gov (United States)

2010-04-01

... for hydroelectric small power production facilities located at a new dam or diversion. 292.208 Section... requirements for hydroelectric small power production facilities located at a new dam or diversion. (a) A hydroelectric small power production facility that impounds or diverts the water of a natural watercourse by...

Siemens IT solutions for power sector

International Nuclear Information System (INIS)

Lunter, P.

2004-01-01

The cost reduction, flexibility and revenue increase, potential exploitation, productivity increase, and business opportunities exploitation - that is all what can be required in the races for the promonent positioning on the electricity power market. These requirements can be realized by the sophisticated IT solutions hand-tailored to the special requirements of the electric power producers and tradesmen. This approach makes it possible to achieve greater profit. Our solutions 'PROFIT Solutions', that are symbiosis of the most progressive information technologies and the power plant techniques of the company Siemens, satisfy submitted specifications in substantial measure. The system solutions 'PROFIT Solutions' comprise three solution groups: process, operation a business. The solutions of the group 'IT Process Solutions' increase flexibility and manoeuvrability of equipment, improve the efficiency and contribute to more economical operation of the power generation. Solutions 'IT Process Solutions' simplify and shorten the period of power cycles and conduce to higher labour productivity. Solutions group 'IT Process Solutions' approaches equipment to the market - supports the profit strategies, helps quickly and expertly to determine and predict hazards. The extension PROFIT Cockpit means the nuance to the solutions world 'PROFIT Solutions'. The survey about the whole installation is within reach at the simple touch of a button. It is possible to compile the total system part by part from single solutions 'PROFIT Solutions'. As a matter of fact all single parts can be interconnected with already existing solutions. Routines 'PROFIT Solutions' cooperate with all modern control systems. (author)

Thermoelectric power plant legislation in Italy: Public participation

International Nuclear Information System (INIS)

Dell'Anno, P.

1991-01-01

Existing Italian legislation describes public involvement in fossil fuel power plant environmental impacts assessments as merely the opportunity to express interest, since it does not acknowledge, in the usual procedural formulas, any actual role to be played by the public. This paper illustrates this point in its examination of the myriad of procedural requirements prescribed by Italian laws governing power plant feasibility analyses. It demonstrates that the recent addition of the environmental element to the standard economic and technological elements in proposal evaluations requires that efforts be made to reduce the complexity of administrative procedures, and that mechanisms be created to allow the public, who will be most affected by any final ruling, a greater say in the decision making

An overview of some basic design features of Koeberg Nuclear Power Station highlighting how regulatory requirements can influence design

International Nuclear Information System (INIS)

Morrison, A.R.

1985-01-01

The paper attempts to show that licensing requirements significantly influence the design of nuclear power plants. The French designed Pressurised Water Reactor system adopted by Escom at Koeberg has its origins in the General Design Criteria set out in the American Code of Federal Regulations document 10CFR50. Three of the General Design Criteria have been selected for illustrating how the requirements have influenced Koeberg in terms of design, both from a hardware and software view point. The requirements of the criteria on quality standard and records are to a certain extent reflected in the Licensing Branch Guide developed by the Atomic Energy Corporation to address quality assurance. The criterion on containment design sets requirements in respect of containment design which are incorporated in the Koeberg design. The criterion on electric power systems sets many of the basic design requirements for the electrical power supply systems inside and outside the station. The existence of the criterion led Escom to introduce changes in the transmission network to meet the requirements in respect of the independent criteria for the grid connections

Ecology of greater sage-grouse in the Dakotas

Science.gov (United States)

Christopher C. Swanson

2009-01-01

Greater sage-grouse (Centrocercus urophasianus) populations and the sagebrush (Artemisia spp.) communities that they rely on have dramatically declined from historic levels. Moreover, information regarding sage-grouse annual life-history requirements at the eastern-most extension of sagebrush steppe communities is lacking....

Environmental radiation monitoring during visits of nuclear powered warships to Australian ports: requirements, arrangements and procedures

International Nuclear Information System (INIS)

1988-05-01

The Commonwealth Government has determined conditions to be met when nuclear powered warships visit Australian ports. These conditions include a requirement that appropriate State/Territory and Commonwealth authorities provide a radiation monitoring program to determine whether any radioactivity has been discharged or accidently released from a nuclear powered warship in port; to determine actual or potential levels of any consequent exposure to radiation of members of the public; and to provide this information within a timescale that allows remedial action to be taken. Part 1 of this document sets out the requirements of a radiation monitoring program capable of meeting these objectives. The fundamental arrangements and procedures for implementing the requirements are presented at Part 2 and provide a basis for the development of fully detailed, port specific, radiation monitoring programs

Greater trochanteric fracture with occult intertrochanteric extension.

Science.gov (United States)

Reiter, Michael; O'Brien, Seth D; Bui-Mansfield, Liem T; Alderete, Joseph

2013-10-01

Proximal femoral fractures are frequently encountered in the emergency department (ED). Prompt diagnosis is paramount as delay will exacerbate the already poor outcomes associated with these injuries. In cases where radiography is negative but clinical suspicion remains high, magnetic resonance imaging (MRI) is the study of choice as it has the capability to depict fractures which are occult on other imaging modalities. Awareness of a particular subset of proximal femoral fractures, namely greater trochanteric fractures, is vital for both radiologists and clinicians since it has been well documented that they invariably have an intertrochanteric component which may require surgical management. The detection of intertrochanteric or cervical extension of greater trochanteric fractures has been described utilizing MRI but is underestimated with both computed tomography (CT) and bone scan. Therefore, if MRI is unavailable or contraindicated, the diagnosis of an isolated greater trochanteric fracture should be met with caution. The importance of avoiding this potential pitfall is demonstrated in the following case of an elderly woman with hip pain and CT demonstrating an isolated greater trochanteric fracture who subsequently returned to the ED with a displaced intertrochanteric fracture.

47 CFR 15.216 - Disclosure requirements for wireless microphones and other low power auxiliary stations capable...

Science.gov (United States)

2010-10-01

... Intentional Radiators Radiated Emission Limits, Additional Provisions § 15.216 Disclosure requirements for... following disclosure requirements: (1) Such persons must display the consumer disclosure text, as specified... point of sale or lease of each such low power auxiliary station. The text must be displayed in a clear...

Interpreting Space-Mission LET Requirements for SEGR in Power MOSFETs

Science.gov (United States)

Lauenstein, J. M.; Ladbury, R. L.; Batchelor, D. A.; Goldsman, N.; Kim, H. S.; Phan, A. M.

2010-01-01

A Technology Computer Aided Design (TCAD) simulation-based method is developed to evaluate whether derating of high-energy heavy-ion accelerator test data bounds the risk for single-event gate rupture (SEGR) from much higher energy on-orbit ions for a mission linear energy transfer (LET) requirement. It is shown that a typical derating factor of 0.75 applied to a single-event effect (SEE) response curve defined by high-energy accelerator SEGR test data provides reasonable on-orbit hardness assurance, although in a high-voltage power MOSFET, it did not bound the risk of failure.

Nuclear power of the coming century and requirements to the nuclear technology

International Nuclear Information System (INIS)

Orlov, V.; Leonov, V.; Sila-Novitski, A.; Smirnov, V.; Tsikunov, V.; Filin, A.

2001-01-01

Current state of nuclear power in the world has been considered and the reasons for its falling short of the great expectations relating to its vigorous development in the outgoing century are considered. Anticipated energy demand of mankind in the next century is evaluated, suggesting that with exhausted resources of cheap fossil fuel and ecological restrictions it can be satisfied by means of a new nuclear technology meeting the requirements of large-scale power generation in terms of safety and economic indices, moreover, the technology can be elaborated in the context of achievements made in civil and military nuclear engineering. Since the developing countries are the most interested parties, it is just their initiative in the development of nuclear technology at the next stage that could provide an impetus for its actual advance. It is shown that large-scale development of nuclear power, being adequate to increase in energy demand, is possible even if solely large NPP equipped with breeders providing BR≥1 are constructed. Requirements for the reactor and fuel cycle technologies are made, their major aspects being: efficient utilization of Pu accumulated and reduction of U specific consumption by at least an order of magnitude; natural inherent safety and deterministic elimination of accidents involving high radioactive releases; assurance of a balance between radiation hazard posed by radioactive wastes disposed and uranium extracted from the ground; nuclear weapons nonproliferation due to fuel reprocessing ruling out potentiality of Pu diversion; reduction of the new generation reactor costs below the costs of today's LWR. (author)

Emergency ac power systems operating experience at U.S. nuclear power plants - 1976 through 1983

Energy Technology Data Exchange (ETDEWEB)

Battle, R. E. [Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)

1986-02-15

Success and failure data of test and emergency starts of emergency ac power sources (diesel generators) at U.S. nuclear power plants were collected and evaluated to estimate diesel generator reliability parameters. A regression analysis of the estimates of the probability of failure to start based on surveillance test data from 1976 through 1983 indicates that the probability of failure to start has been decreasing. However, the reliability of diesel generator performance during losses of off-site power for 1981 through 1983 was less than expected based on the test data estimates. The failures that occurred during losses of off-site power were reviewed to determine why the calculated failure to start was greater than expected, and possible explanations for this high value are presented. The subsystems involved In diesel generator subsystem failures were categorized to determine whether there were any dominant failure modes. The results indicate that further significant Improvement in diesel generator reliability will require improvement of many subsystems. (author)

NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

A Preliminary Assessment of the Initial Compression Power Requirement in CO2 Pipeline “Carbon Capture and Storage (CCS Technologies”

Directory of Open Access Journals (Sweden)

Abdussalam El-Suleiman

2016-05-01

Full Text Available CO2 captured from fossil-fueled power generation plants is said to be economically transported via pipelines over long distances. The CO2 must be compressed to pipeline specifications using compressors and pumps that are driven by gas turbine (GT or other prime movers. This paper presents the evaluation of actual work transfer or required prime power by modeling the governing equations of compression using the Peng–Robinson equation of state (PR-EOS. A computer code was developed to carry out the modeling and subsequent simulation of the compression power requirement. The simulation of prime mover power was carried out for different technology (head per stage of the compressor ranging from 10-staged compression to double stage compression. The results show that the current technology of the centrifugal compressor could require as much as 23MW of prime mover power to compress 1.5 million tonnes per year of CO2—a projected equivalent CO2 released from a 530MW combined cycle gas turbine (CCGT power generation plant.

How Many Model Evaluations Are Required To Predict The AEP Of A Wind Power Plant?

International Nuclear Information System (INIS)

Murcia, J P; Réthoré, P E; Natarajan, A; Sørensen, J D

2015-01-01

Wind farm flow models have advanced considerably with the use of large eddy simulations (LES) and Reynolds averaged Navier-Stokes (RANS) computations. The main limitation of these techniques is their high computational time requirements; which makes their use for wind farm annual energy production (AEP) predictions expensive. The objective of the present paper is to minimize the number of model evaluations required to capture the wind power plant's AEP using stationary wind farm flow models. Polynomial chaos techniques are proposed based on arbitrary Weibull distributed wind speed and Von Misses distributed wind direction. The correlation between wind direction and wind speed are captured by defining Weibull-parameters as functions of wind direction. In order to evaluate the accuracy of these methods the expectation and variance of the wind farm power distributions are compared against the traditional binning method with trapezoidal and Simpson's integration rules.The wind farm flow model used in this study is the semi-empirical wake model developed by Larsen [1]. Three test cases are studied: a single turbine, a simple and a real offshore wind power plant. A reduced number of model evaluations for a general wind power plant is proposed based on the convergence of the present method for each case. (paper)

Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

International Nuclear Information System (INIS)

2000-01-01

OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants

Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-08-01

OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

Fission nuclear power prospects and its role in meeting global energy needs

International Nuclear Information System (INIS)

Golan, S.

1992-01-01

Nuclear power currently makes an important contribution to world's energy requirements providing 17% of its electricity. But as global warming becomes of greater concern, many ask whether nuclear power can and should contribute more. The author, who is involved in the nuclear power enterprise for 35 years, tries to answer this question affirmative. He holds the view that: a) nuclear fission power is essential to meeting world's energy needs without unduly impairing the global environment; b) by possessing the required attributes discussed in this paper, nuclear fission power can be made societally acceptable; c) the industrialized world should accelerate LMFR deployment while fostering more convenient energy alternatives for the developing world; and d) the HTGR is unique in its ability to augment non-electricity energy needs and could become the technology choice of developing countries for nuclear electricity production. (author). 5 refs., 5 figs., 4 tabs

In-core power sharing and fuel requirement study for a decommissioning Boiling Water Reactor using the linear reactivity model

International Nuclear Information System (INIS)

Chen, Chung-Yuan; Tung, Wu-Hsiung; Yaur, Shung-Jung; Kuo, Weng-Sheng

2014-01-01

Highlights: • Linear reactivity model (LRM) was modified and applied to Boiling Water Reactor. • The power sharing and fuel requirement study of the last cycle and two cycles before decommissioning was implemented. • The loading pattern design concept for the cycles before decommissioning is carried out. - Abstract: A study of in-core power sharing and fuel requirement for a decommissioning BWR (Boiling Water Reactor) was carried out using the linear reactivity model (LRM). The power sharing of each fuel batch was taken as an independent variable, and the related parameters were set and modified to simulate actual cases. Optimizations of the last cycle and two cycles before decommissioning were both implemented; in the last-one-cycle optimization, a single cycle optimization was carried out with different upper limits of fuel batch power, whereas, in the two-cycle optimization, two cycles were optimized with different cycle lengths, along with two different optimization approaches which are the simultaneous optimization of two cycles (MO) and two successive single-cycle optimizations (SO). The results of the last-one-cycle optimization show that it is better to increase the fresh fuel power and decrease the thrice-burnt fuel power as much as possible. It also shows that relaxing the power limit is good to the fresh fuel requirement which will be reduced under lower power limit. On the other hand, the results of the last-two-cycle (cycle N-1 and N) optimization show that the MO is better than SO, and the power of fresh fuel batch should be decreased in cycle N-1 to save its energy for the next cycle. The results of the single-cycle optimization are found to be the same as that in cycle N of the multi-cycle optimization. Besides that, under the same total energy requirement of two cycles, a long-short distribution of cycle length design can save more fresh fuel

Power Control and Monitoring Requirements for Thermal Vacuum/Thermal Balance Testing of the MAP Observatory

Science.gov (United States)

Johnson, Chris; Hinkle, R. Kenneth (Technical Monitor)

2002-01-01

The specific heater control requirements for the thermal vacuum and thermal balance testing of the Microwave Anisotropy Probe (MAP) Observatory at the Goddard Space Flight Center (GSFC) in Greenbelt, Maryland are described. The testing was conducted in the 10m wide x 18.3m high Space Environment Simulator (SES) Thermal Vacuum Facility. The MAP thermal testing required accurate quantification of spacecraft and fixture power levels while minimizing heater electrical emissions. The special requirements of the MAP test necessitated construction of five (5) new heater racks.

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

The trillion dollar power project jackpot

International Nuclear Information System (INIS)

Roseman, E.J.

1994-01-01

International power needs, if not insatiable, are certainly of a magnitude beyond anything heretofore imagined. The international opportunities for independent power development are huge: Power Plants -- $700 to $800 billion worth of the new facilities will be needed by the year 2000; Transmission and Distribution -- Expansion of services will require an additional $300 to $400 billion; and Repowering and Improving Existing Plants -- The estimate is $40-$60 billion. RCG/Hagler, Bailly tracks the international power project development activities of over a hundred developers, and monitors the emerging private power market in Europe, Asia, and Latin America. On behalf of private clients and multi-lateral institutions, the authors have worked in more than three dozen countries in the past two years. There are far-reaching global implications involved in this massive movement toward independent power projects. New levels of international economic growth depend on it. Far greater energy efficiencies must accompany it. Environmental problems which will arise must be recognized and solved. The results from the trillion dollars that are to be invested will be far-reaching, dramatic, and vastly beneficial

NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

International Nuclear Information System (INIS)

1994-08-01

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

Policy planning for nuclear power: an overview of the main issues and requirements

International Nuclear Information System (INIS)

1995-05-01

The report contains information on the political, governmental, economic, financial and technical issues and requirements associated with planning and implementing a safe, economic and reliable nuclear power programme. It highlights the main areas in which policies must be developed and decisions taken, as well as the role and responsibilities of government, the plant owner and national industry. Also presented are the main criteria to assist policy planners in defining options and strategies which can achieve a balance among such objectives as cost effective and efficient electricity production, realistic and acceptable financing arrangements, national development requirements, safety and environmental protection. (NHA)

Problems about the analysis of technical requirements compliance in NPPPCI systems

International Nuclear Information System (INIS)

Perello, M.

1978-01-01

The display of the problems that the analysis of the technical requirements compliance bring along is presented. In the project of nuclear power plants, above all, the influence of national and international standards in the analysis of the adjustment of requirements established by the governments of nuclear safety of the different countries. In the oral presentation greater emphasis is made on the difficulties that the PSAR evaluation brings when the lack of technical standards in the owner country makes necessary the use of other countries rules. (author)

Neutral beam energy and power requirements for expanding radius and full bore startup of tokamak reactors

International Nuclear Information System (INIS)

Houlberg, W.A.; Mense, A.T.; Attenberger, S.E.

1979-09-01

Natural beam power and energy requirements are compared for full density full bore and expanding radius startup scenarios in an elongated plasma, The Next Step (TNS), as a function of beam pulse time and plasma density. Because of the similarity of parameters, the results should also be applicable to Engineering Test Facility (ETF) and International Tokamak Reactor (INTOR) studies. A transport model consisting of neoclassical ion conduction and anomalous electron conduction and diffusion based on ALCATOR scaling leads to average densities in the range approx. 0.8 to 1.2 x 10 14 cm -3 being sufficient for ignition. Neutral deuterium beam energies in the range 120 to 180 keV are adequate for penetration, with the required power injected into the plasma decreasing with increasing beam energy. The neutral beam power decreases strongly with increasing beam pulse length b/sub b/ until t/sub b/ exceeds a few total energy confinement times, yielding b/sub b/ approx. = 4 to 6 s for the TNS plasma

Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants

International Nuclear Information System (INIS)

2016-05-01

Revised to take into consideration findings from the Fukushima Daiichi nuclear power plant accident, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, has introduced some new concepts with respect to the earlier safety standard published in the year 2000. The preparation of SSR-2/1 (Rev. 1) was carried out with constant and intense involvement of IAEA Member States, but some new requirements, because of the novelty of the concepts introduced and the complexity of the issues, are not always interpreted in a unique way. The IAEA is confident that a complete clarification and a full understanding of the new requirements will be available when the supporting safety guides for design and safety assessment of nuclear power plants are prepared. The IAEA expects that the effort devoted to the preparation of this publication, which received input and comments from several Member States and experts, will also facilitate and harmonize the preparation or revision of these supporting standards

Electric power system / emergency power supply

International Nuclear Information System (INIS)

Dorn, P.G.

1980-01-01

One factor of reliability of reactor safety systems is the integrity of the power supply. The purpose of this paper is a review and a discussion of the safety objectives required for the planning, licensing, manufacture and erection of electrical power systems and components. The safety aspects and the technical background of the systems for - the electric auxiliary power supply system and - the emergency power supply system are outlined. These requirements result specially from the safety standards which are the framework for the studies of safety analysis. The overall and specific requirements for the electrical power supply of the safety systems are demonstrated on a 1300 MW standard nuclear power station with a pressurized water reactor. (orig.)

Space Station power system issues

International Nuclear Information System (INIS)

Giudici, R.J.

1985-01-01

Issues governing the selection of power systems for long-term manned Space Stations intended solely for earth orbital missions are covered briefly, drawing on trade study results from both in-house and contracted studies that have been conducted over nearly two decades. An involvement, from the Program Development Office at MSFC, with current Space Station concepts began in late 1982 with the NASA-wide Systems Definition Working Group and continued throughout 1984 in support of various planning activities. The premise for this discussion is that, within the confines of the current Space Station concept, there is good reason to consider photovoltaic power systems to be a venerable technology option for both the initial 75 kW and 300 kW (or much greater) growth stations. The issue of large physical size required by photovoltaic power systems is presented considering mass, atmospheric drag, launch packaging and power transmission voltage as being possible practicality limitations. The validity of searching for a cross-over point necessitating the introduction of solar thermal or nuclear power system options as enabling technologies is considered with reference to programs ranging from the 4.8 kW Skylab to the 9.5 gW Space Power Satellite

Comparison of Standards and Technical Requirements of Grid-Connected Wind Power Plants in China and the United States

Energy Technology Data Exchange (ETDEWEB)

Gao, David Wenzhong [Alternative Power Innovations, LLC; Muljadi, Eduard [National Renewable Energy Lab. (NREL), Golden, CO (United States); Tian, Tian [National Renewable Energy Lab. (NREL), Golden, CO (United States); Miller, Mackay [National Renewable Energy Lab. (NREL), Golden, CO (United States); Wang, Weisheng [China Electric Power Research Inst. (China)

2016-09-01

The rapid deployment of wind power has made grid integration and operational issues focal points in industry discussions and research. Compliance with grid connection standards for wind power plants (WPPs) is crucial to ensuring the reliable and stable operation of the electric power grid. This report compares the standards for grid-connected WPPs in China to those in the United States to facilitate further improvements in wind power standards and enhance the development of wind power equipment. Detailed analyses of power quality, low-voltage ride-through capability, active power control, reactive power control, voltage control, and wind power forecasting are provided to enhance the understanding of grid codes in the two largest markets of wind power. This study compares WPP interconnection standards and technical requirements in China to those in the United States.

Outlook for the power requirements by the northeast U.S. power pool: Who will serve this market?

International Nuclear Information System (INIS)

Anderson, E.P.

1993-01-01

The size of the potential natural gas market in the northeast U.S. and how it will be served are discussed. One of the most promising markets for natural gas in this area is for power generation, using combined-cycle generating units that are efficient and have low environmental impact. It is estimated that by 2002 natural gas requirements for electrical power generation in the northeast could reach 750 billion cubic feet per year. This market will be served through several new gas pipelines and through expansion of the existing pipeline capacity. Projections for electricity production for the northeast, including the New York Power pool, show an increase from 236,423 GWh in 1992 to 275,558 GWh in 2002, an increase of ca 17%. Non-utility generation will increase its share from 14% in 1992 to 26% in 2002. Utility switching to natural gas during summer months to control nitrogen oxide emissions will give natural gas more flexibility to compete with other options to reduce air pollution. Pipeline capacity additions planned for the northeast are reviewed, including the Liberty pipeline, Empire State pipeline, Portland gas transmission system, Minuteman delivery system and Mayflower gas transmission system. There will be more than adequate reliable and flexible pipeline capacity created to meet the future demand for natural gas in this region. 14 figs

MegaFlex Scale-Up Cost & Risk Reduction for >50kW Future Power Demands, Phase I

Data.gov (United States)

National Aeronautics and Space Administration — As the MegaFlex solar array is scaled for power demands greater than 50kW over the next 20 years and deployed load requirements remain high or increase, advanced...

Energy Requirement and Comfort of Gas- and Electric-powered Hot-water Systems

International Nuclear Information System (INIS)

Luedemann, B.; Schmitz, G.

1999-01-01

In view of the continuous reduction in the specific heating energy demand of new buildings the power demand for hot-water supply increasingly dominates the heating supply of residential buildings. Furthermore, the German energy-savings-regulation 2000 (ESVO) is intended to evaluate the techniques installed such as domestic heating or hot-water supply within an overall energetic view of the building. Planning advice for domestic heating, ventilation and hot-water systems in gas-heated, low-energy buildings has therefore been developed in a common research project of the Technical University of Hamburg Harburg (TUHH) and four energy supply companies. In this article different gas-or electricity-based hot-water systems in one family houses and multiple family houses are compared with one another with regard to the aspects of comfort and power requirements considering the user's behaviour. (author)

International requirements for life extension of nuclear power plants; Internationale Anforderungen zur Lebensdauerverlaengerung von Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

Wernicke, Robert [TUeV NORD SysTec GmbH und Co. KG, Abt. Festigkeit und Konstruktion, Hamburg (Germany)

2009-11-15

Lifetime extension or long-term operation of nuclear facilities are topics of great international significance against the backdrop of a fleet of nuclear power plants of which many have reached 2/3 of their planned life. The article deals with the conditions for, and the specific requirements of, seeking long-term operation of nuclear power plants as established internationally and on the basis of IAEA collections. Technically, long-term operation is possible for many of the nuclear power plants in the world because, normally, they were built on the basis of conservative rules and regulations and, as a consequence, incorporate significant additional safety. Application of requirements to specific plants implies assessments of technical safety which show that conservative design philosophies created reserves and, as a consequence, there is an adequate level of safety also in long-term plant operation. For this purpose, the technical specifications must be revised, necessary additions made, and (international) operating experience taken into account and management of aging established. Two examples are presented to show how the approach to long-term plant operation is put into practice on a national level. (orig.)

Professional performance attributes according to accounting entrepreneurs from greater São Paulo

Directory of Open Access Journals (Sweden)

Ivam Ricardo Peleias

2015-06-01

Full Text Available Accounting has a broad activity universe, which requires skilled professionals who are prepared to practice the profession. One possibility is to be an accounting entrepreneur, whose profile requires specific attributes and attitudes. The results reported on in this paper derive from a research developed using the oral history technique, concerning the identification and analysis of attributes valued in the performance of the profession by accounting entrepreneurs from greater São Paulo. A field research was developed, involving face-to-face interviews with a group of seven accounting entrepreneurs of outstanding professional reputation, seeking evidence on the administration of the accounting organization and on the interviewees’ entrepreneurial profile. The theoretical framework was focused on the accounting organizations and the entrepreneurial behavior. The data revealed common attributes and profiles needed to perform the profession among the interviewees and the accounting organizations they manage, such as: they started the organizations in a simple manner, in a family environment; the organizations are structured in a departmentalized manner, delegating powers; they declared having achieved an outstanding position in the accounting segment with great work, dedication and persistence; they execute their activities based on ethics, honesty and seriousness; they look for new challenges and enterprises and target the valuation of the accounting profession.

Is College Pricing Power Pro-Cyclical?

Science.gov (United States)

Altringer, Levi; Summers, Jeffrey

2015-01-01

We define pricing power as a college's ability to increase its net tuition revenue by raising its sticker-price for tuition. The greater is the positive effect of sticker-price increases on net tuition revenue, the greater is the pricing power. We gauge variation in the pricing power of private, non-profit baccalaureate colleges by estimating this…

Systems required during and after an earthquake. Summary report. WWER-1000 nuclear power plants

International Nuclear Information System (INIS)

Monette, P.

1995-01-01

The scope of this document is to list the mechanical, instrumentation and electrical components required during and after earthquake, in order to achieve and maintain safe shutdown conditions of a WWER-1000 type nuclear power plant. The main objective pursued in establishing the systems and equipment list is to provide guidance for the design and implementation of the backfits which are necessary to increase seismic resistance of the components required after earthquake. The presented list is established on generic basis, i.e. it is applicable to any specific WWER-1000

Nuclear power: Preparing for the future. International conference on nuclear power for the 21st century, 21 March 2005, Paris, France

International Nuclear Information System (INIS)

ElBaradei, M.

2005-01-01

This statement discusses a few aspects of the evolving global scenario for nuclear power. All indicators show that an increased level of emphasis on subjects such as fast growing energy demands, security of energy supply, and the risk of climate change are driving a re-consideration, in some quarters, of the need for greater investment in nuclear power. The decisions that emerge from this debate will have long range implications, and require a degree of planning that looks at least several decades into the future. This morning I would like to offer a brief review of the current picture, and to outline a number of issues that, in my view, will be crucial in determining the contribution of nuclear power to the future global energy mix

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

International Nuclear Information System (INIS)

1994-08-01

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

Defining greater-than-class-C low-level radioactive waste

International Nuclear Information System (INIS)

Knecht, M.A.; Oztunali, O.I.

1986-01-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) was signed by President Reagan on January 15, 1986. This act requires the federal government to be responsible for the disposal of greater-than-class-C low-level radioactive waste (LLRW) that is generated commercially by state agencies and by federal entities (other than waste generated by atomic weapons research, development, or testing, or by decommissioning of vessels of the nuclear navy). To plan for disposal, the federal government will require estimates of the volume of waste involved and characterization of this waste. A clear definition of greater-than-class-C LLRW is the first step in determining what wastes will be included in the waste to be received by the federal government. This definition will influence major policy decisions to be made for management of such waste. The purpose of this paper is to examine the existing information on greater-than-class-C LLRW in view of the current definition of such waste and potential changes in this definition - for example, an upper limit on the concentrations of radionuclides in LLRW. The paper identifies further information needs to develop a clear definition of such waste for use in federal planning for acceptance of responsibility for disposal of such waste

Safety related requirements on future nuclear power plants

International Nuclear Information System (INIS)

Niehaus, F.

1991-01-01

Nuclear power has the potential to significantly contribute to the future energy supply. However, this requires continuous improvements in nuclear safety. Technological advancements and implementation of safety culture will achieve a safety level for future reactors of the present generation of a probability of core-melt of less than 10 -5 per year, and less than 10 -6 per year for large releases of radioactive materials. There are older reactors which do not comply with present safety thinking. The paper reviews findings of a recent design review of WWER 440/230 plants. Advanced evolutionary designs might be capable of reducing the probability of significant off-site releases to less than 10 -7 per year. For such reactors there are inherent limitations to increase safety further due to the human element, complexity of design and capability of the containment function. Therefore, revolutionary designs are being explored with the aim of eliminating the potential for off-site releases. In this context it seems to be advisable to explore concepts where the ultimate safety barrier is the fuel itself. (orig.) [de

Siemens IT solutions for power sector. PROFIT solutions

International Nuclear Information System (INIS)

Lunter, P.

2004-01-01

The cost reduction, flexibility and revenue increase, potential exploitation, productivity increase, and business opportunities exploitation - that is all what can be required in the races for the promonent positioning on the electricity power market. These requirements can be realized by the sophisticated IT solutions hand-tailored to the special requirements of the electric power producers and tradesmen. This approach makes it possible to achieve greater profit. Our solutions 'PROFIT Solutions', that are symbiosis of the most progressive information technologies and the power plant techniques of the company Siemens, satisfy submitted specifications in substantial measure. The system solutions 'PROFIT Solutions' comprise three solution groups: process, operation a business. The solutions of the group 'IT Process Solutions' increase flexibility and manoeuvrability of equipment, improve the efficiency and contribute to more economical operation of the power generation. Solutions 'IT Process Solutions' simplify and shorten the period of power cycles and conduce to higher labour productivity. Solutions group 'IT Process Solutions' approaches equipment to the market - supports the profit strategies, helps quickly and expertly to determine and predict hazards. The extension PROFIT Cockpit means the nuance to the solutions world 'PROFIT Solutions'. The survey about the whole installation is within reach at the simple touch of a button. It is possible to compile the total system part by part from single solutions 'PROFIT Solutions'. As a matter of fact all single parts can be interconnected with already existing solutions. Routines 'PROFIT Solutions' cooperate with all modern control systems. (author)

Fission Power System Technology for NASA Exploration Missions

Science.gov (United States)

Mason, Lee; Houts, Michael

2011-01-01

Under the NASA Exploration Technology Development Program, and in partnership with the Department of Energy (DOE), NASA is conducting a project to mature Fission Power System (FPS) technology. A primary project goal is to develop viable system options to support future NASA mission needs for nuclear power. The main FPS project objectives are as follows: 1) Develop FPS concepts that meet expected NASA mission power requirements at reasonable cost with added benefits over other options. 2) Establish a hardware-based technical foundation for FPS design concepts and reduce overall development risk. 3) Reduce the cost uncertainties for FPS and establish greater credibility for flight system cost estimates. 4) Generate the key products to allow NASA decisionmakers to consider FPS as a preferred option for flight development. In order to achieve these goals, the FPS project has two main thrusts: concept definition and risk reduction. Under concept definition, NASA and DOE are performing trade studies, defining requirements, developing analytical tools, and formulating system concepts. A typical FPS consists of the reactor, shield, power conversion, heat rejection, and power management and distribution (PMAD). Studies are performed to identify the desired design parameters for each subsystem that allow the system to meet the requirements with reasonable cost and development risk. Risk reduction provides the means to evaluate technologies in a laboratory test environment. Non-nuclear hardware prototypes are built and tested to verify performance expectations, gain operating experience, and resolve design uncertainties.

Safety requirement of the nuclear power plants, after TMI-2 accident and their possible implementation on Bushehr NPP

International Nuclear Information System (INIS)

Mirhabibi, N.; Tochai, M.T.M.; Ashrafi, A.; Farnoudi, E.

1985-01-01

Based on the lessons learned from the TMI-2 accident and other research and developments, many improvements have been required for the design, manufacturing and operation of nuclear power plants in recent years. These requirements have already been implemented to the plants in operation and considered as new safety requirements for new plants. In the present paper these requirements and their possible implementation on Bushehr NPP are discussed. (Author)

Environmental Impacts of Wind Power Development on the Population Biology of Greater Prairie-Chickens

Energy Technology Data Exchange (ETDEWEB)

Sandercock, Brett K. [Kansas State Univ., Manhattan, KS (United States)

2013-05-22

This report summarizes the results of a seven-year, DOE-funded research project, conducted by researchers from Kansas State University and the National Wind Coordinating Collaborative, to assess the effects of wind energy development in Kansas on the population and reproduction of greater prairie chickens.

Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

Energy Technology Data Exchange (ETDEWEB)

Jung, Insu [Korea Institute of Construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

2014-05-15

Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

International Nuclear Information System (INIS)

Jung, Insu; Kim, Woojung

2014-01-01

Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

New requirements, rules and regulations, and vested rights of nuclear power plants

International Nuclear Information System (INIS)

Raetzke, C.

2006-01-01

The article deals with the question whether new requirements can be imposed on existing nuclear power plants. It was promoted by the fact that the German Federal Ministry for the Environment currently is working on a thorough revision of German nuclear regulations. When looking at backfitting requirements, the all-important question is whether new findings show that the provisions taken in the license to guarantee the 'necessary precautions' (as defined in the German Atomic Energy Act) contain errors or omissions; only in this case can the authority demand that remedial measures, including backfitting, be taken. Beyond that, German nuclear law contains no obligation for operators to improve and develop safety still further. This applies regardless of whether new requirements are justified by new technical possibilities or new scientific analyses or whether they are prompted by a mere abstract re-evaluation of the safety level to be achieved. In the former case, if there are good technical or scientific reasons, the operators, as a rule, will perform backfitting voluntarily. Pursuant to these criteria, the article covers three categories of backfitting requirements and illustrates them by examples. These general principles are also valid when a new set of regulations - as planned by the BMU - are put into effect and applied. They may lead to existing plants not having to comply fully with the requirements contained in new regulations. (orig.)

Some aspects of nuclear power development in Czechoslovakia

International Nuclear Information System (INIS)

Simandl, S.; Stefec, V.

1986-01-01

Some technical and economic aspects of the development of nuclear power in Czechoslovakia are discussed. Specific conditions include the high population density of the territory and related factors as well as the shortage of raw materials for the construction of technological equipment and for the construction of buildings. It is stated that projects of future nuclear power plants should use reserves, such as are available in the standard project of a WWER-1000 nuclear power plant now being used in Temelin, as against foreign nuclear power plants. This mainly includes a bigger built-up area per installed megawatt of power and a greater number of personnel for operation and maintenance. Also discussed is the world-wide growth of capital costs, of construction time and of the number of workers needed for the construction of nuclear power plants. With the exception of the V-2 nuclear power plant the construction time of Czechoslovak nuclear power plants does not exceed world average. The maximum number of workers required for construction, however, compares unfavourably with advanced capitalist countries. Operating costs in Czechoslovakia are more favourable for nuclear power plants than for coal burning power plants and pumped-storage hydroelectric plants. (Z.M.)

Independent Power Producers' view on restructuring in Ontario's electric power sector

International Nuclear Information System (INIS)

Brooks, J.

1996-01-01

The collective views on electricity industry restructuring of the independent power producers in Ontario were summarized by IPPSO's executive director. The Society is fully in agreement with the MacDonald Committee recommendations to privatize power generation in Ontario, and is equally in favor of competitive restructuring that is now underway in Michigan, New York and Quebec, as well as farther afield in the U.S., the U.K., and elsewhere around the world. IPPSO claims that a competitive generation system comprised of current and future IPPSO members could supply the province's power requirements at a cost 20 per cent lower than the present monopolistic system of Ontario Hydro. Add to that no reduction in services to the consumers, increased revenues in the form of taxes to the province, and the prospect of restructuring becomes far less threatening than first perceived. While fully in agreement with the MacDonald Committee's recommendations, IPPSO is opposed to Ontario Hydro's own restructuring plans. Their objection is based on the assessment that the plan would not result in real competition; in reality, it would allow Hydro even greater freedom to continue investing publicly-guaranteed money on a completely dissimilar basis to its competitors

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

A greater decline in female facial attractiveness during middle age reflects women’s loss of reproductive value

Directory of Open Access Journals (Sweden)

Dario eMaestripieri

2014-02-01

Full Text Available Facial attractiveness represents an important component of an individual’s overall attractiveness as a potential mating partner. Perceptions of facial attractiveness are expected to vary with age-related changes in health, reproductive value, and power. In this study, we investigated perceptions of facial attractiveness, power, and personality in two groups of women of pre- and post-menopausal ages (35-50 years and 51-65 years, respectively and two corresponding groups of men. We tested three hypotheses: 1 that perceived facial attractiveness would be lower for older than for younger men and women; 2 that the age-related reduction in facial attractiveness would be greater for women than for men; and 3 that for men, there would be a larger increase in perceived power at older ages. Eighty facial stimuli were rated by 60 (30 male, 30 female middle-aged women and men using online surveys. Our three main hypotheses were supported by the data. Consistent with sex differences in mating strategies, the greater age-related decline in female facial attractiveness was driven by male respondents, while the greater age-related increase in male perceived power was driven by female respondents. In addition, we found evidence that some personality ratings were correlated with perceived attractiveness and power ratings. The results of this study are consistent with evolutionary theory and with previous research showing that faces can provide important information about characteristics that men and women value in a potential mating partner such as their health, reproductive value, and power or possession of resources.

Reassessment and suspension of the nuclear power plant design requirement of the constraint of collective dose per unit of practice. (Requirement 6 (b), Standard AR 3.1.2)

International Nuclear Information System (INIS)

Amado, Valeria A.; Canoba, Analia C.; Curti, Adriana R.; Biaggio, Alfredo L.

2009-01-01

By the middle of 2005, the Nuclear Regulatory Authority (ARN) decided to re-assess the basis of a design requirement applicable to the limitation of nuclear power reactor radioactive discharges. Such requirement, aimed at restricting the discharge of globally dispersed long-lived radionuclides, was in force in Argentina since 1979 and was expressed as a limitation of the collective dose commitment per unit of electrical energy generated. The practical result of such regulatory action was the need to retain C-14 in the Atucha II power reactor under construction as well as in future heavy water reactors to be built in the country, and, later on, to manage it as to assure its isolation from the biosphere during an appropriate period of time. For the above-mentioned reassessment, an ad hoc task group was created and an internal report was presented to the Board of Directors by the middle of 2007. Because of such report the ARN decided to suspend the application of the requirement (i.e. it is not more mandatory, even for Atucha II). The present work presents the main aspects of that report. In particular, it explains the basis of the design requirement and the most important assumptions that triggered it. The differences between the assumptions made at that time and the reality of nuclear power generation at the beginning of the 21st Century, as well as their implications in relation to the requirement are described, including the Suess effect and its impact in the total dose due to C-14. Finally, after explaining in detail the facts that made no longer reasonable to keep in force the above mentioned requirement, the work presents the conclusions that lead the ARN to the suspension of this requirement. (author) [es

EXCESS RF POWER REQUIRED FOR RF CONTROL OF THE SPALLATION NEUTRON SOURCE (SNS) LINAC, A PULSED HIGH-INTENSITY SUPERCONDUCTING PROTON ACCELERATOR

International Nuclear Information System (INIS)

Lynch, M.; Kwon, S.

2001-01-01

A high-intensity proton linac, such as that being planned for the SNS, requires accurate RF control of cavity fields for the entire pulse in order to avoid beam spill. The current design requirement for the SNS is RF field stability within ±0.5% and ±0.5 o [1]. This RF control capability is achieved by the control electronics using the excess RF power to correct disturbances. To minimize the initial capital costs, the RF system is designed with 'just enough' RF power. All the usual disturbances exist, such as beam noise, klystron/HVPS noise, coupler imperfections, transport losses, turn-on and turn-off transients, etc. As a superconducting linac, there are added disturbances of large magnitude, including Lorentz detuning and microphonics. The effects of these disturbances and the power required to correct them are estimated, and the result shows that the highest power systems in the SNS have just enough margin, with little or no excess margin

Greater-confinement disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive wastes include a broad spectrum of wastes that have different radionuclide concentrations, half-lives, and physical and chemical properties. Standard shallow-land burial practice can provide adequate protection of public health and safety for most low-level wastes, but a small volume fraction (about 1%) containing most of the activity inventory (approx.90%) requires specific measures known as ''greater-confinement disposal'' (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics. This paper presents an overview of the factors that must be considered in planning the application of methods proposed for providing greater confinement of low-level wastes. 27 refs

Evaluation of the applicability of existing nuclear power plant regulatory requirements in the U.S. to advanced small modular reactors.

Energy Technology Data Exchange (ETDEWEB)

LaChance, Jeffrey L.; Wheeler, Timothy A.; Farnum, Cathy Ottinger; Middleton, Bobby D.; Jordan, Sabina Erteza; Duran, Felicia Angelica; Baum, Gregory A.

2013-05-01

The current wave of small modular reactor (SMR) designs all have the goal of reducing the cost of management and operations. By optimizing the system, the goal is to make these power plants safer, cheaper to operate and maintain, and more secure. In particular, the reduction in plant staffing can result in significant cost savings. The introduction of advanced reactor designs and increased use of advanced automation technologies in existing nuclear power plants will likely change the roles, responsibilities, composition, and size of the crews required to control plant operations. Similarly, certain security staffing requirements for traditional operational nuclear power plants may not be appropriate or necessary for SMRs due to the simpler, safer and more automated design characteristics of SMRs. As a first step in a process to identify where regulatory requirements may be met with reduced staffing and therefore lower cost, this report identifies the regulatory requirements and associated guidance utilized in the licensing of existing reactors. The potential applicability of these regulations to advanced SMR designs is identified taking into account the unique features of these types of reactors.

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

International Nuclear Information System (INIS)

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

1976-01-01

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

Greater confinement disposal of radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive waste (LLW) includes a broad spectrum of different radionuclide concentrations, half-lives, and hazards. Standard shallow-land burial practice can provide adequate protection of public health and safety for most LLW. A small volume fraction (approx. 1%) containing most of the activity inventory (approx. 90%) requires specific measures known as greater-confinement disposal (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics

Licensing evaluation of CANDU-PHW nuclear power plants relative to U.S. regulatory requirements

International Nuclear Information System (INIS)

Erp, J.B. van

1978-01-01

Differences between the U.S. and Canadian approach to safety and licensing are discussed. U.S. regulatory requirements are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to current Regulatory Requirements and Guides. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S. These modifications are proposed solely for the purpose of maintaining consistency within the current U.S. regulatory system and not out of a need to improve the safety of current-design CANDU-PHW nuclear power plants. A number of issues are identified which still require resolution. Most of these issues are concerned with design areas not (yet) covered by the ASME code. (author)

Ultrasonic scalpel causes greater depth of soft tissue necrosis compared to monopolar electrocautery at standard power level settings in a pig model

Science.gov (United States)

2012-01-01

Background Ultrasonic scalpel (UC) and monopolar electrocautery (ME) are common tools for soft tissue dissection. However, morphological data on the related tissue alteration are discordant. We developed an automatic device for standardized sample excision and compared quality and depth of morphological changes caused by UC and ME in a pig model. Methods 100 tissue samples (5 × 3 cm) of the abdominal wall were excised in 16 pigs. Excisions were randomly performed manually or by using the self-constructed automatic device at standard power levels (60 W cutting in ME, level 5 in UC) for abdominal surgery. Quality of tissue alteration and depth of coagulation necrosis were examined histopathologically. Device (UC vs. ME) and mode (manually vs. automatic) effects were studied by two-way analysis of variance at a significance level of 5%. Results At the investigated power level settings UC and ME induced qualitatively similar coagulation necroses. Mean depth of necrosis was 450.4 ± 457.8 μm for manual UC and 553.5 ± 326.9 μm for automatic UC versus 149.0 ± 74.3 μm for manual ME and 257.6 ± 119.4 μm for automatic ME. Coagulation necrosis was significantly deeper (p < 0.01) when UC was used compared to ME. The mode of excision (manual versus automatic) did not influence the depth of necrosis (p = 0.85). There was no significant interaction between dissection tool and mode of excision (p = 0.93). Conclusions Thermal injury caused by UC and ME results in qualitatively similar coagulation necrosis. The depth of necrosis is significantly greater in UC compared to ME at investigated standard power levels. PMID:22361346

A PLC generic requirements and specification for safety-related applications in nuclear power plants

International Nuclear Information System (INIS)

Han, Jea Bok; Lee, C. K.; Lee, D. Y.

2001-12-01

This report presents the requirements and specification to be applied to the generic qualification of programmable Logic Controller(PLC), which is being developed as part of the KNICS project, 'Development of the Digital Reactor Safety Systems' of which purpose is the application to safety-related instrumentation and control systems in nuclear power plants. This report defines the essential and critical characteristics that shall be included as part of a PLC design for safety-related application. The characteristics include performance, reliability, accuracy, the overall response time from an input to the PLC exceeding it trip condition to the resulting outputs, and the specification of processors and memories in digital controller. It also specifies the quality assurance process for software development, dealing with executive software, firmware, application software tools for developing the application software, and human machine interface(HMI). In addition, this report reviews the published standards and guidelines that are required for the PLC development and the quality assurance processes such as environment requirements, seismic withstand requirements, EMI/RFI withstand requirements, and isolation test

Lightweight Damage Tolerant, High-Temperature Radiators for Nuclear Power and Propulsion

Science.gov (United States)

Craven, Paul D.; SanSoucie, Michael P.

2015-01-01

NASA is increasingly emphasizing exploration to bodies beyond near-Earth orbit. New propulsion systems and new spacecraft are being built for these missions. As the target bodies get further out from Earth, high energy density systems, e.g., nuclear fusion, for propulsion and power will be advantageous. The mass and size of these systems, including supporting systems such as the heat exchange system, including thermal radiators, will need to be as small as possible. Conventional heat exchange systems are a significant portion of the total thermal management mass and size. Nuclear electric propulsion (NEP) is a promising option for high-speed, in-space travel due to the high energy density of nuclear fission power sources and efficient electric thrusters. Heat from the reactor is converted to power for use in propulsion or for system power. The heat not used in the power conversion is then radiated to space as shown in figure 1. Advanced power conversion technologies will require high operating temperatures and would benefit from lightweight radiator materials. Radiator performance dictates power output for nuclear electric propulsion systems. Pitch-based carbon fiber materials have the potential to offer significant improvements in operating temperature, thermal conductivity, and mass. These properties combine to allow significant decreases in the total mass of the radiators and significant increases in the operating temperature of the fins. A Center-funded project at NASA Marshall Space Flight Center has shown that high thermal conductivity, woven carbon fiber fins with no matrix material, can be used to dissipate waste heat from NEP systems and because of high specific power (kW/kg), will require less mass and possibly less total area than standard metal and composite radiator fins for radiating the same amount of heat. This project uses an innovative approach to reduce the mass and size required for the thermal radiators to the point that in-space NEP and power

Survey on maintenance skills required for nuclear power plant periodic inspections

International Nuclear Information System (INIS)

Hamasaki, Kenichi

2008-01-01

In this study, we conducted a trend survey regarding the problem of passing on senior workers' skills and knowledge to young employees in industries in general, and an interview survey of skilled workers engaged in maintenance work during periodic inspections at a nuclear power plant. These surveys aimed to obtain useful information for maintaining and improving the quality of future maintenance work during nuclear power plant periodic inspections. The trend survey of industries found that the 'Year 2007 Problem (difficulties associated with the start of mass retirements of baby-boomers)' was often takenup in various fields and that many companies were concerned about losing their accumulated skills and know-how. To ensure that skills are smoothly passed on to the younger generation, companies have taken various measures, such as development of plans for passing on skills and knowledge, introduction of the Meister system and implementation of workshops by skilled workers. The interview survey of skilled workers engaged in maintenance work of mechanical equipment during periodic inspections at Nuclear Power Plant A found that various skills were required in maintenance work. Regarding perceived differences between skilled and unskilled maintenance workers, many respondents believed that the largest difference was in terms of time taken to carry out specific procedures. Some maintenance companies have increasingly fewer skilled workers than before or face aging of skilled personnel. As future concerns, respondents cited the loss of skills that have been acquired through experience in construction and in handling of troubles and failures. Differences were observed among companies in the degree to which skills have been passed on to the younger generation. As a reason why skills are not successfully passed on, respondents cited communication problems due to age differences between senior and young workers and other problems that were also observed in other industries

Secure equality and greater-than tests with sublinear online complexity

DEFF Research Database (Denmark)

Lipmaa, Helger; Toft, Tomas

2013-01-01

Secure multiparty computation (MPC) allows multiple parties to evaluate functions without disclosing the private inputs. Secure comparisons (testing equality and greater-than) are important primitives required by many MPC applications. We propose two equality tests for ℓ-bit values with O(1) online...

How Many Model Evaluations Are Required To Predict The AEP Of A Wind Power Plant?

DEFF Research Database (Denmark)

Murcia Leon, Juan Pablo; Réthoré, Pierre-Elouan; Natarajan, Anand

2015-01-01

(AEP) predictions expensive. The objective of the present paper is to minimize the number of model evaluations required to capture the wind power plant's AEP using stationary wind farm flow models. Polynomial chaos techniques are proposed based on arbitrary Weibull distributed wind speed and Von Misses...... distributed wind direction. The correlation between wind direction and wind speed are captured by defining Weibull-parameters as functions of wind direction. In order to evaluate the accuracy of these methods the expectation and variance of the wind farm power distributions are compared against...... the traditional binning method with trapezoidal and Simpson's integration rules. The wind farm flow model used in this study is the semi-empirical wake model developed by Larsen [1]. Three test cases are studied: a single turbine, a simple and a real offshore wind power plant. A reduced number of model...

Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

Energy Technology Data Exchange (ETDEWEB)

Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

Balancing computation and communication power in power constrained clusters

Science.gov (United States)

Piga, Leonardo; Paul, Indrani; Huang, Wei

2018-05-29

Systems, apparatuses, and methods for balancing computation and communication power in power constrained environments. A data processing cluster with a plurality of compute nodes may perform parallel processing of a workload in a power constrained environment. Nodes that finish tasks early may be power-gated based on one or more conditions. In some scenarios, a node may predict a wait duration and go into a reduced power consumption state if the wait duration is predicted to be greater than a threshold. The power saved by power-gating one or more nodes may be reassigned for use by other nodes. A cluster agent may be configured to reassign the unused power to the active nodes to expedite workload processing.

Institutional innovations required for widespread use of nuclear power

International Nuclear Information System (INIS)

Johnson, W.R.

1992-01-01

The social and economic benefits of additional electrical generating capacity in lesser developed countries are unquestioned, and a case can be made from economic and environmental considerations that much of this capacity should be nuclear powered. Obstacles to the introduction of nuclear power in the developing world include lack of a technical infrastructure and capital cost. Manpower shortage also detracts from a country's ability to effectively regulate a nuclear power enterprise. Two variations on the traditional institutional methods for supplying and regulating nuclear electric power are proposed. The first would be independent international companies that would design, finance, build, operate and maintain nuclear power stations, and sell electricity to local systems. The second would be an international safety regulatory system that could offer uniform, effective regulations and enforcement of the entire nuclear power enterprise at a level consistent with accepted world standards. These proposals coupled with the modular Advanced Liquid Metal Reactor based on Integral Fast Reactor technology would make possible a safe, economically feasible nuclear power operation that could be located anywhere in the world. (author). 7 refs

Power requirements at the VHTR/HTE interface for hydrogen production

International Nuclear Information System (INIS)

Vilim, R.B.

2007-01-01

The power requirements at the interface between the High Temperature Electrolysis (HTE) process and the Very High Temperature Reactor (VHTR) were investigated. The study was performed using a network systems code that linked together individual component models for boiler, condenser, turbine, compressor, pump, gas-to-gas heat exchanger, electrolyser, and reactor and properties for water, hydrogen, oxygen, nitrogen, and helium. A species mixture model supported the use of mixtures of gases in each component model. The requirements for a reference design with a dedicated high temperature process heat loop are given. In general the quantity and quality of the process heat needed by the HTE process is a function of how the electrolyser is operated. Operating at higher voltage increases throughput and resistive heating providing the opportunity to recuperate this heat and supplant a large fraction of high temperature reactor heat. Any shortfall can be added by electrical heaters in the HTE plant. Eliminating the associated high temperature heat exchanger from the nuclear plant in this manner would significantly improve safety and maintainability. Low temperature process heat is still needed to vaporize water for the HTE process but this can be obtained at very low cost from VHTR waste heat rejected to the ultimate heat sink. (author)

A solar powered wireless computer mouse. Industrial design concepts

Energy Technology Data Exchange (ETDEWEB)

Reich, N.H.; Van Sark, W.G.J.H.M.; Alsema, E.A.; Turkenburg, W.C. [Department of Science, Technology and Society, Copernicus Institute, Utrecht University, Heidelberglaan 2, 3584 CS Utrecht (Netherlands); Veefkind, M.; Silvester, S. [Industrial Design Engineering, Delft University of Technology, Landbergstraat 15, 2628 CE Delft (Netherlands)

2009-02-15

A solar powered wireless computer mouse (SPM) was chosen to serve as a case study for the evaluation and optimization of industrial design processes of photovoltaic (PV) powered consumer systems. As the design process requires expert knowledge in various technical fields, we assessed and compared the following: appropriate selection of integrated PV type, battery capacity and type, possible electronic circuitries for PV-battery coupling, and material properties concerning mechanical incorporation of PV into the encasing. Besides technical requirements, ergonomic aspects and design aesthetics with respect to good 'sun-harvesting' properties influenced the design process. This is particularly important as simulations show users can positively influence energy balances by 'sun-bathing' the PV mouse. A total of 15 SPM prototypes were manufactured and tested by actual users. Although user satisfaction proved the SPM concept to be feasible, future research still needs to address user acceptance related to product dimensions and user willingness to pro-actively 'sun-bath' PV powered products in greater detail. (author)

Greater happiness for a greater number: Is that possible in Austria?

NARCIS (Netherlands)

R. Veenhoven (Ruut)

2011-01-01

textabstractWhat is the final goal of public policy? Jeremy Bentham (1789) would say: greater happiness for a greater number. He thought of happiness as subjective enjoyment of life; in his words as “the sum of pleasures and pains”. In his time the happiness of the great number could not be measured

Greater happiness for a greater number: Is that possible in Germany?

NARCIS (Netherlands)

R. Veenhoven (Ruut)

2009-01-01

textabstractWhat is the final goal of public policy? Jeremy Bentham (1789) would say: greater happiness for a greater number. He thought of happiness as subjective enjoyment of life; in his words as “the sum of pleasures and pains”. In his time the Happiness of the great number could not be measured

The AGS Booster main ring power supply system

International Nuclear Information System (INIS)

Soukas, A.; Hughes, K.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

1989-01-01

The AGS Booster is being designed as a very versatile particle accelerator. Its primary function is to be a high quality injector to the currently operating Alternating Gradient Synchrotron (AGS). The Booster/AGS combination will produce proton intensities greater than 5 x 10 13 protons per pulse (ppp), and accelerate heavy ions, with mass up to 200, to a maximum energy of 15 GeV per atomic mass unit (GeV/amu). The power supply for the Booster Main Ring (BMRPS) has to accommodate a wide range of cycles and a wide range of operating parameters. The cycles range from storage for several seconds to rapid cycling at 7.5 Hz. The peak output power is 18 MW. This paper will describe the AGS Booster machine powering requirements, the choice of power supply, the a.c. circuit tie-in and its associated problems and some of the details of the design of the BMRPS. 9 refs., 2 figs

A study of thermal-hydraulic requirements for increasing the power rates for natural-circulation boiling water reactors

International Nuclear Information System (INIS)

Yasuo, A.; Inada, F.; Hidaka, M.

1992-01-01

In this paper, the feasibility of higher power rates for natural-circulation boiling water reactors (BWRs) is studied with the objective of examining the flexibility of the plant power rate in constructing such plants to cope with the increasing demand for electricity. By applying existing one-dimensional design codes, the riser heights necessary to meet two major thermal-hydraulic requirements, i.e., critical power and core stability, are systematically calculated. Several restrictions on the maximum diameter and height of the pressure vessel are also considered because these restrictions could make construction impossible or drastically increase the construction costs. A very simple map of the dominant parameters for higher power rates is obtained. It is concluded that natural-circulation BWRs of >1000 MW (electric) will be feasible within the restrictions considered here

Analysis of Plug Load Capacities and Power Requirements in Commercial Buildings: Preprint

Energy Technology Data Exchange (ETDEWEB)

Sheppy, M.; Torcellini, P.; Gentile-Polese, L.

2014-08-01

Plug and process load power requirements are frequently overestimated because designers often use estimates based on 'nameplate' data, or design assumptions are high because information is not available. This generally results in oversized heating, ventilation, and air-conditioning systems; increased initial construction costs; and increased energy use caused by inefficiencies at low, part-load operation. Rightsizing of chillers in two buildings reduced whole-building energy use by 3%-4%. If an integrated design approach could enable 3% whole-building energy savings in all U.S. office buildings stock, it could save 34 TBtu of site energy per year.

Dispatchable Solar Power Plant Project

Energy Technology Data Exchange (ETDEWEB)

Price, Henry [Solar Dynamics LLC, Broomfield, CO (United States)

2018-01-31

As penetration of intermittent renewable power increases, grid operators must manage greater variability in the supply and demand on the grid. One result is that utilities are planning to build many new natural gas peaking power plants that provide added flexibility needed for grid management. This report discusses the development of a dispatchable solar power (DSP) plant that can be used in place of natural gas peakers. Specifically, a new molten-salt tower (MST) plant has been developed that is designed to allow much more flexible operation than typically considered in concentrating solar power plants. As a result, this plant can provide most of the capacity and ancillary benefits of a conventional natural gas peaker plant but without the carbon emissions. The DSP system presented was designed to meet the specific needs of the Arizona Public Service (APS) utility 2017 peaking capacity request for proposals (RFP). The goal of the effort was to design a MST peaker plant that had the operational capabilities required to meet the peaking requirements of the utility and be cost competitive with the natural gas alternative. The effort also addresses many perceived barriers facing the commercial deployment of MST technology in the US today. These include MST project development issues such as permitting, avian impacts, visual impacts of tower CSP projects, project schedule, and water consumption. The DSP plant design is based on considerable analyses using sophisticated solar system design tools and in-depth preliminary engineering design. The resulting DSP plant design uses a 250 MW steam power cycle, with solar field designed to fit on a square mile plot of land that has a design point thermal rating of 400 MWt. The DSP plant has an annual capacity factor of about 16% tailored to deliver greater than 90% capacity during the critical Arizona summer afternoon peak. The table below compares the All-In energy cost and capacity payment of conventional combustion turbines

Requirements for the retrofitting an extension of the maximum voltage power grid from the point of view of environmental protection and cultivated landscape work

International Nuclear Information System (INIS)

2013-01-01

The project on the requirements for the retrofitting an extension of the maximum voltage power grid from the point of view of environmental protection and cultivated landscape work includes contributions on the following topics: the development of the European transmission grid, the grid extension law, restrictions for the power grid and their infrastructure, requirements for the regulations concerning the realization of the transnational grid extension, inclusion of the public - public acceptance - communication, requirements concerning the environmental compensation law, overhead line - underground cable - health hazards, ecological effects of overhead lines and underground cables, infrastructural projects, power supply in the future, structural relief by photovoltaics.

Requirements and analysis of electromagnetic compatibility of safety-related instrumentation and control system in nuclear power plants

International Nuclear Information System (INIS)

Liu Sujuan

2002-01-01

The state-of-the-art instrumentation and control system and the influence of their application to the electromagnetic compatibility is analyzed. Based on the present situation of nuclear safety in China and relevant experiences from other countries, the author tries to probe into the requirements and test methods about how safety-related instrument and control system to accommodate electromagnetic interference, radio-frequency interference and power surges in the environments of nuclear power plant so as to develop Chinese safety standards

The contribution of nuclear energy to the meeting of Italy's electric power requirements

International Nuclear Information System (INIS)

Angelini, A.M.

1977-01-01

The paper discusses ENEL's policy in the development of nuclear energy, which assigns to this source the role of meeting almost all of Italy's additional future power requirements. This is a position taken some time ago and already outlined on the occasion of the Geneva Conference of 1971. The policy is based on a number of factors, reviewed in the paper, which differentiate, at least in quantitative terms, Italy's situation from that of most industrialized countries. Among these factors stand out the scarcity of natural resources, including energy sources available in Italy. An extensive recourse to nuclear energy is the best way to achieve that diversification of energy supplies vital to the Italian economy which, because of the very lack of natural resources, is predominantly based on processing. While the Caorso Nuclear Power Plant (840 MW) is due to go into service soon, ENEL's nuclear plan, recently approved by the Government, calls for the construction of the four 1,000-MW units already on order and of 16 additional units, of the same size, divided into two 8-units blocks, to be decided on respectively in the very near future and before the end of 1977. The necessary flexibility of the plan concerning the nuclear units that will go into service by the 1986 is ensured by the subdivision into blocks, with provision for the postponement of the second, 8-units block in the country's economy development requires a revision in electric power forecasts. The paper then considers in particular the integration between the nuclear plan and ENEL's extensive plan for pumped-storage hydro-electric power plants and the related technical and economic advantages which also extend to an international scope. The paper concludes the review of Italy's nuclear plan by stressing two essential problems: financing and the availability of sites for nuclear power plants. Upon their timely and satisfactory solution depends the actual construction of the plants by the scheduled dates

Requirements and operation of decentralised power plants in the changing power market

International Nuclear Information System (INIS)

Hoenings, Norbert; Hornig, Niels; Steinbach, Sebastian

2014-01-01

E.ON plans and realises distributed industrial power plants on the basis of contracting schemes. Target is to reduce energy costs without investment by the customer himself. Gas turbine CHP plants are very flexible and offer many possibilities for the operator to adjust optimally to a constantly changing energy market. This aspect is becoming increasingly important due to the increasing share of renewables. However, the economic situation for CHP plants has deteriorated significantly, due to the current market situation distorted by the subsidised renewable power generation. (orig.)

Supplementary quality assurance requirements for installation, inspection, and testing of structural concrete and structural steel during the construction phase of nuclear power plants

International Nuclear Information System (INIS)

Anon.

1974-01-01

This standard sets forth the supplementary quality assurance requirements for installation, inspection, and testing of structural concrete and structural steel for nuclear power plant construction. The requirements may also be extended to other appropriate parts of nuclear power plants when specified in contract documents. This standard is intended to be used in conjunction with ANSI N45.2

Site infrastructure as required during the construction and erection of nuclear power plants

International Nuclear Information System (INIS)

Haas, K.F.; Wagner, H.

1978-01-01

In general, in an exchange of experience on constructing nuclear power plants priority is given to design and lay-out, financing, quality assurance etc., but in this paper an attempt has been made to describe range and type of site infrastructure required during construction and erection. Site infrastructure will make considerable demands on the planning, supply of material and maintenance that may result from the frequently very isolated location of power plant sites. Examples for specific values and experiences are given for a nuclear power plant with two units on the 1300-MW type at present under construction of the Persian Gulf in Iran. Data concerning the site infrastructure, including examples, are given and explained on the basis of graphs. The site is split up into a technical and a social infrastructure. The main concern of the technical site infrastructure is the timely provision and continuous availability of electric energy, water, communication grids, workshops, warehouses, offices, transport and handling facilities, as well as the provision of heavy load roads, harbour facilities, etc. The social site infrastructure in general comprises accommodation, food supplies and the care and welfare of all site personnel, which includes a hospital, school, self-service shop, and sport and recreation facilities. (author)

Manpower requirements for quality assurance during operation

International Nuclear Information System (INIS)

Pratt, J.M.; Sollenberger, L.G.

1982-01-01

As a result of the Three Mile Island accident and the findings presented in various investigatory reports, some fundamental changes are taking place in the role and scope of quality assurance. Recent changes to United States national codes, guides and standards are analysed in order to identify the principles involved. This analysis shows that the scope of the programme is being extended beyond the equipment designated 'nuclear safety related' and greater emphasis is being placed upon the independent verification of the satisfactory performance of activities affecting safety. Such fundamental changes could lead to a significant increase in the number of quality assurance personnel required to support an operating nuclear power plant. The evolving quality assurance organization at Three Mile Island is used to illustrate how these fundamental changes could affect the quality assurance organization and manpower requirements. (author)

Small-Scale Low Cost Solid Oxide Fuel Cell Power Systems

Energy Technology Data Exchange (ETDEWEB)

S. D. Vora

2008-02-01

Progress in tasks seeking greater cell power density and lower cost through new cell designs, new cell materials and lower operating temperature is summarized. The design of the program required Proof-of-Concept unit of residential capacity scale is reviewed along with a summary of results from its successful test. Attachment 1 summarizes the status of cell development. Attachment 2 summarizes the status of generator design, and Attachment 3 of BOP design.

Economic analysis vs. capital-recovery requirements of power reactor decommissioning

International Nuclear Information System (INIS)

Ferguson, J.S.

1980-01-01

As a consultant to electric utilities the author often becomes involved in the development of policy for capital recovery and in the determination of depreciation rates that will implement the policy. Utility capital recovery is controlled by generally accepted depreciation accounting practices and by regulatory commission accounting rules and, as a result, can differ significantly from engineering economics. Those involved with decommissioning of power reactors should be aware of the depreciation accounting and regulatory framework that dictates capital recovery requirements, whether their involvement is related to engineering economics or capital recovery. This presentation defines that framework, points out several significant implications (particularly tax), describes several conforming capital-recovery methods, describes several techniques that have been used with the decommissioning component in economic analysis of alternative energy sources, and discusses why those involved in economic analysis should learn the accounting and regulatory framework for capital recovery

Grid-Tied Photovoltaic Power System

Science.gov (United States)

Eichenberg, Dennis J.

2011-01-01

A grid-tied photovoltaic (PV) power system is connected directly to the utility distribution grid. Facility power can be obtained from the utility system as normal. The PV system is synchronized with the utility system to provide power for the facility, and excess power is provided to the utility. Operating costs of a PV power system are low compared to conventional power technologies. This method can displace the highest-cost electricity during times of peak demand in most climatic regions, and thus reduce grid loading. Net metering is often used, in which independent power producers such as PV power systems are connected to the utility grid via the customers main service panels and meters. When the PV power system is generating more power than required at that location, the excess power is provided to the utility grid. The customer pays the net of the power purchased when the on-site power demand is greater than the onsite power production, and the excess power is returned to the utility grid. Power generated by the PV system reduces utility demand, and the surplus power aids the community. Modern PV panels are readily available, reliable, efficient, and economical, with a life expectancy of at least 25 years. Modern electronics have been the enabling technology behind grid-tied power systems, making them safe, reliable, efficient, and economical with a life expectancy equal to the modern PV panels. The grid-tied PV power system was successfully designed and developed, and this served to validate the basic principles developed, and the theoretical work that was performed. Grid-tied PV power systems are reliable, maintenance- free, long-life power systems, and are of significant value to NASA and the community. Of particular value are the analytical tools and capabilities that have been successfully developed. Performance predictions can be made confidently for grid-tied PV systems of various scales. The work was done under the NASA Hybrid Power Management (HPM

Material property requirements for application leak-before-break technology on nuclear power plant high-energy piping

International Nuclear Information System (INIS)

Li Chengliang; Deng Xiaoyun; Yin Zhiying; Liu Meng

2012-01-01

The application of leak-before-break (LBB) technology on nuclear power plant high-energy piping systems can improve their safety and economy, while propose some new requirements on testing material properties. The U.S. Nuclear Regulatory Commission's LBB related standard review plan and implementation specifications were analyzed, and test items, object, temperature, quantity and thermal aging effect of five general requirements were summarized. In addition, four key testing technical requirements, such as specimen size, side grooves, strain range and the orientation of specimens were also discussed to ensure the test data usefulness, representativeness and integrity. This study can provide some guidance for the aforementioned test program on domestic materials. (authors)

Liquid metal engineering aspects of a commercial-sized power plant based on the hylife converter concept

International Nuclear Information System (INIS)

Hoffman, N.J.; McDowell, M.W.

1979-12-01

A study of a commercial fusion plant based on the High Yield Lithium Injection Fusion Energy (HYLIFE) converter has been performed. A net efficiency of 33.3% was derived for a plant using 2-1/4 Cr - 1 Mo ferritic steel as structural alloy. Use of a thick lithium fall to protect structural materials from the deleterious effects of pellet thermonuclear burn allows the structure to last the life of the plant without replacement. Both mechanical pumps and EM pumps are analyzed for this application. The power requirement for the lithium fall mechanical pumps is approx. 20 MWe. This is a relatively insignificant 1.6% of the gross electrical power output of the plant of approx. 1250 MWe. An EM pump has a greater electrical requirement but the lesser head (NPSH) requirement of an EM pump appears to be a marked advantage since this affects the size of the lithium inventory. The preferred tritium separation method appears to be that developed by Argonne National Laboratory which involves mixing lithium into an immiscible liquid having a greater affinity for hydrogen isotopes, with subsequent electrolytic separation. The immiscible liquid under consideration is a lithium bromide-lithium fluoride-lithium chloride mixture

Power requirements and environmental impact of a pedelec. A case study based on real-life applications

Energy Technology Data Exchange (ETDEWEB)

Abagnale, Carmelina, E-mail: c.abagnale@unina.it; Cardone, Massimo, E-mail: massimo.cardone@unina.it; Iodice, Paolo, E-mail: paolo.iodice@unina.it; Strano, Salvatore, E-mail: salvatore.strano@unina.it; Terzo, Mario, E-mail: m.terzo@unina.it; Vorraro, Giovanni, E-mail: giovanni.vorraro@unina.it

2015-07-15

This paper describes the methodologies to appraise the power requests and environmental analysis of an electrically assisted bicycle under real driving conditions, also containing regulations and technical-science-related aspects. For this purpose, in this study, the on-road test program of an electrically assisted bicycle was executed in the urban area of Naples on different test tracks, so a general assessment about its driving behavior under several driving conditions was performed. The power requirements in different typical riding situations were estimated by a procedure based on the experimental kinematic parameters that characterize the driving dynamics collected during the real-life applications. An environmental analysis was also performed, with a methodology that takes into account the environmental assessment of a moped by measuring the experimental moped exhaust emissions of the regulated pollutants. Starting from the results acquired during the different test samples, besides, an assessment of the electric traction offered by this pedelec on the driving comfort was evaluated for different riding situations. - Highlights: • The power requirements of a pedelec in typical riding conditions were identified. • The estimated electricity consumption for battery recharging was defined. • An environmental valuation of the tested pedelec and of a moped was performed. • Emissions that could be saved utilizing a pedelec instead of a moped were derived.

Power requirements and environmental impact of a pedelec. A case study based on real-life applications

International Nuclear Information System (INIS)

Abagnale, Carmelina; Cardone, Massimo; Iodice, Paolo; Strano, Salvatore; Terzo, Mario; Vorraro, Giovanni

2015-01-01

This paper describes the methodologies to appraise the power requests and environmental analysis of an electrically assisted bicycle under real driving conditions, also containing regulations and technical-science-related aspects. For this purpose, in this study, the on-road test program of an electrically assisted bicycle was executed in the urban area of Naples on different test tracks, so a general assessment about its driving behavior under several driving conditions was performed. The power requirements in different typical riding situations were estimated by a procedure based on the experimental kinematic parameters that characterize the driving dynamics collected during the real-life applications. An environmental analysis was also performed, with a methodology that takes into account the environmental assessment of a moped by measuring the experimental moped exhaust emissions of the regulated pollutants. Starting from the results acquired during the different test samples, besides, an assessment of the electric traction offered by this pedelec on the driving comfort was evaluated for different riding situations. - Highlights: • The power requirements of a pedelec in typical riding conditions were identified. • The estimated electricity consumption for battery recharging was defined. • An environmental valuation of the tested pedelec and of a moped was performed. • Emissions that could be saved utilizing a pedelec instead of a moped were derived

Legislative framework and regulatory requirements for the introduction of nuclear power

International Nuclear Information System (INIS)

Ha-Vinh, Phuong

1975-01-01

The adoption of appropriate legislation is to be considered as a prerequisite to the introduction of nuclear power in view of the issues that need to be regulated. Preparatory steps should be started at the earliest stage in conjunction with the planning of nuclear power projects. The primary objectives of a licensing scheme are to ensure safety, public health and environmental protection as well as financial protection for third parties in case of nuclear incident. For licensing purposes, a legislative framework and regulatory determinations are required. Within such a framework and pursuant to such regulatory determinations, the elaboration of safety standards, rules, guides and enforcement procedures is to be considered of paramount importance. To this end a number of international recommendations and advisory material prepared by the IAEA provide useful guidance. A licensing process would normally be split into several stages relating to site approval, construction permit, pre-operational tests, and operating licence, each stage being subject to safety assessments and reviews as determined by regulations. Financial protection against nuclear damage has also to be insured. A special regime of nuclear liability has been established by international conventions, based on the principle of strict liability of the operator of a nuclear installation. As a result of such channelling of liability to him, his liability is limited in amount and time. This liability system has the dual purpose of ensuring appropriate protection for potential victims and of relieving the nuclear industry from unlimited liability risks, which would impede practical applications of atomic energy. For the elaboration of nuclear legislation and specialized regulations the Agency's advisory services have proved to be of help to countries embarking on a nuclear power programme. (author)

Flexibility in Europe's power sector — An additional requirement or an automatic complement?

International Nuclear Information System (INIS)

Bertsch, Joachim; Growitsch, Christian; Lorenczik, Stefan; Nagl, Stephan

2016-01-01

By 2050, the European Union aims to reduce greenhouse gases by more than 80%. The EU member states have therefore declared to strongly increase the share of renewable energy sources (RES-E) in the next decades. Given a large deployment of wind and solar capacities, there are two major impacts on electricity systems: First, the electricity system must be flexible enough to cope with the volatile RES-E generation, i.e., ramp up supply or ramp down demand on short notice. Second, sufficient back-up capacities are needed during times with low feed-in from wind and solar capacities. This paper analyzes whether there is a need for additional incentive mechanisms for flexibility in electricity markets with a high share of renewables. For this purpose, we simulate the development of the European electricity markets up to the year 2050 using a linear investment and dispatch optimization model. Flexibility requirements are implemented in the model via ramping constraints and provision of balancing power. We found that an increase in fluctuating renewables has a tremendous impact on the volatility of the residual load and consequently on the flexibility requirements. However, any market design that incentivizes investments in least (total system) cost generation investment does not need additional incentives for flexibility. The main trigger for investing in flexible resources is the achievable full load hours and the need for backup capacity. In a competitive market, the cost-efficient technologies that are most likely to be installed, i.e., gas-fired power plants or flexible CCS plants, provide flexibility as a by-product. Under the condition of system adequacy, flexibility never poses a challenge in a cost-minimal capacity mix. Therefore, any market design incentivizing investments in efficient generation thus provides flexibility as an inevi complement. - Highlights: • We analyze flexibility in electricity systems with a high share of renewables. • For scenario

Power Requirements Determined for High-Power-Density Electric Motors for Electric Aircraft Propulsion

Science.gov (United States)

Johnson, Dexter; Brown, Gerald V.

2005-01-01

Future advanced aircraft fueled by hydrogen are being developed to use electric drive systems instead of gas turbine engines for propulsion. Current conventional electric motor power densities cannot match those of today s gas turbine aircraft engines. However, if significant technological advances could be made in high-power-density motor development, the benefits of an electric propulsion system, such as the reduction of harmful emissions, could be realized.

Investigation of high-alpha lateral-directional control power requirements for high-performance aircraft

Science.gov (United States)

Foster, John V.; Ross, Holly M.; Ashley, Patrick A.

1993-01-01

Designers of the next-generation fighter and attack airplanes are faced with the requirements of good high angle-of-attack maneuverability as well as efficient high speed cruise capability with low radar cross section (RCS) characteristics. As a result, they are challenged with the task of making critical design trades to achieve the desired levels of maneuverability and performance. This task has highlighted the need for comprehensive, flight-validated lateral-directional control power design guidelines for high angles of attack. A joint NASA/U.S. Navy study has been initiated to address this need and to investigate the complex flight dynamics characteristics and controls requirements for high angle-of-attack lateral-directional maneuvering. A multi-year research program is underway which includes groundbased piloted simulation and flight validation. This paper will give a status update of this program that will include a program overview, description of test methodology and preliminary results.

Component Selection, Accelerated Testing, and Improved Modeling of AMTEC Systems for Space Power (abstract)

Science.gov (United States)

Williams, R. M.; Jeffries-Nakamura, B.; Ryan, M. A.; Underwood, M. L.; Suitor, J.; O'Connor, D.

1993-01-01

Alkali metal thermal to electric converter (AMTEC) designs for space power are numerous, but selection of materials for construction of long-lived AMTEC devices has been limited to electrodes, current collectors, and the solid electrolyte. AMTEC devices with lifetimes greater than 5 years require careful selection and life testing of all hot-side components. The likely selection of a remote condensed design for initial flight test and probable use with a GPHS in AMTEC powered outer planet probes requires the device to be constructed to tolerate T greater than 1150K, as well as exposure to Na(sub (g)), and Na(sub (liq)) on the high pressure side. The temperatures involved make critical high strength and chemical resistance to Na containing Na(sub 2)O. Selection among materials which can be worked should not be driven by ease of fabricability, as high temperature stability is the critical issue. These concepts drive the selection of Mo alloys for Na(sub (liq)) containment in AMTEC cells for T to 1150K operation, as they are significantly stronger than comparable NB or Ta alloys, are less soluble in Na(sub (liq)) containing dissolved Na(sub 2)O, are workable compared to W alloys (which might be used for certain components), and are ductile at the T greater than 500K of proposed AMTEC modules in space applications.

Requirements for class 1, 2, and 3 pressure-retaining systems and components in CANDU nuclear power plants

International Nuclear Information System (INIS)

1991-09-01

This third edition of CAN/CSA-N285.1 supersedes the 1981 and 1975 editions. It provides the specific requirements for design, fabrication, and installation of Class 1, 2 and 3 pressure-retaining systems and components in CANDU nuclear power plants, and over pressure protection of the heat transport system. The general requirements for pressure-retaining systems and components are given in CSA Standard CAN/CSA-N285.0, with which Class 1, 2 and 3 systems and components must also comply

Licensing requirements regarding the qualification of operating personnel in nuclear power plants

International Nuclear Information System (INIS)

Fechner, J.B.

1981-01-01

The legal requirements regarding the qualifications of operating personnel in nuclear power plants in the Federal Republic of Germany are outlined as in article 7 of the Atomic Energy Act. For the responsible operating personnel the requisite competence and reliability are legally required; for subordinate personnel the law requires only the necessary knowledge. The requisite competence and the necessary knowledge have been further specified in a set of guidelines by the authorities; work on specification of reliability requirements is under way. Essential elements of the requisite competence of responsible operating personnel are their professional qualification, their safety-related knowledge, their abilities, their practical experience, and - for the responsible shift personnel - their nuclear, plant-related training as well as a written and oral examination. Requalification is indispensible for keeping the requisite competence on a level in accordance with the current state of science and technology. Facts concerning the personal reliability of the responsible operating personnel are assessed by the competent authorities on the basis of information available at other state institutions. For the responsible shift personnel, physical and psychological fitness are important factors contributing to their reliability. The necessary knowledge subordinate operating personnel must possess with respect to plant safety and safety of the personnel is assured via instruction on safety and via special briefings at the working place. Lack of safety-related knowledge has to be compensated for by assigning an experienced permanent supervisor for each activity in question. Current work on qualification of operating personnel concentrates on training, including simulator training, of responsible shift personnel. (author)

A comparison of energy conversion systems for meeting the power requirements of manned rover for Mars missions

International Nuclear Information System (INIS)

El-Genk, M.S.; Morley, N.; Cataldo, R.; Bloomfield, H.

1990-01-01

Minimizing system mass for interplanetary missions is of utmost importance in order to keep launch cost within reasonable bounds. For a manned Mars rover, powered by a nuclear reactor power system, the choice of the energy conversion system can play a significant role in lowering the overall system mass. Not only is the mass of the conversion unit affected by the choice, but also the masses of the reactor core, waste heat rejection system, and the radiation shield which are strongly influenced by the system conversion efficiency and operating condition. Several types of conversion systems are of interest for a nuclear reactor Mars manned application. These conversion systems include: free piston Stirling engines, He/XE closed Brayton cycle (CBC), CO 2 open Brayton, and SiGe/GaP thermoelectric. Optimization studies are conducted to determine the impact of the conversion system on the overall mass of the nuclear power system as well as the mobility power requirement of the Rover vehicle

Lean Maintenance Applied to Improve Maintenance Efficiency in Thermoelectric Power Plants

OpenAIRE

Orlando Duran; Andrea Capaldo; Paulo Andrés Duran Acevedo

2017-01-01

Thermoelectric power plants consist of a set of critical equipment that require high levels of availability and reliability. Due to this, maintenance of these physical assets is gaining momentum in industry. Maintenance is considered as an activity that contributes to improving the availability, efficiency and productivity of each piece of equipment. Several techniques have been used to achieve greater efficiencies in maintenance, among which we can find the lean maintenance philosophy. Despi...

ALSTOM supercritical steam plants meet Polish market challenges and power generator's requirements

Energy Technology Data Exchange (ETDEWEB)

Twardowski, A.

2007-07-01

From the early 1990s the age and technical performance of most of the Polish power plants required urgent investment including rehabilitation and/or replacement. This was necessary as power demand was increasing continuously in parallel with country GDP growth. Poland's joining the EU in May 2005 caused additional obligations related to limitation of emissions by Poland as a country and specifically by the Polish power sector. The first big project focussed on replacement of old equipment, improvement of electricity production efficiency and reduction of environmental impact by rehabilitation of Units 1-6 in Turow power plant. This is briefly described in the presentation. The latest and the biggest project is the construction of a new supercritical, lignite fired 833 MW unit in BOT Belchatow PP awarded to ALSTOM in December 2004 as a full term key contract. In addition to a new power block the project included: a new desulfurisation plant; a complete close circle cooling system; a new electrical system control system, and water treatment system; a coal handling system connecting the new unit with lignite transportation system from the open mine to the existing plant; hydraulic ash and slug systems; and an electrostatic precipitator. The unit has reduced NOx emissions to the level below 200 mg/Nm{sup 3} thanks to low emission burners. Particulate emissions are below 30 mg/Nm{sup 3}, SOx emissions are below 220 mg/Nm{sup 3}; CO{sub 2} emissions are lowered and cooling water consumption reduced. Special noise protection systems and special design of some systems has greatly reduced the noise level. 2 photos.

The role of advanced nuclear power technologies in developing countries: Criteria and design requirements

International Nuclear Information System (INIS)

1990-02-01

The document includes the papers presented at the following two technical committee meetings organized by the IAEA: Technical Committee Meeting and Workshop on Criteria for the Introduction of Advanced Nuclear Power Technologies for Specific Applications in Developing Countries, Vienna, 27-30 June 1988 (14 papers) and Technical Committee Meeting and Workshop on Design Requirements for the Application of Advanced Concepts in Developing Countries, Vienna, 6-9 December 1988 (16 papers). A separate abstract was prepared for each of these papers

Special safety requirements applied to Brazilian nuclear power plant

International Nuclear Information System (INIS)

Lepecki, W.P.S.; Hamel, H.J.E.; Koenig, N.; Vieira, P.C.R.; Fritzsche, J.C.

1981-01-01

Some safety aspects of the Angra 2 and 3 nuclear power plants are presented. An analysis of the civil and mechanical project of these nuclear power plant having in view a safety analysis is done. (E.G.) [pt

Manpower requirements in the nuclear power industry, 1982-1991

International Nuclear Information System (INIS)

Johnson, R.C.

1982-09-01

The objective of this study is to project occupational employment needs, created by growth and employee turnover, for the nuclear power industry over the next decade. Employment data for 1981 were collected in a survey conducted by the Institute of Nuclear Power Operations of its 60 member utilities. The data were analyzed statistically to identify factors that account for variations in power plant staffing and the number of off-site nuclear support personnel employed by a utility. Total employment in the nuclear power industry is predicted to increase from 54,400 in 1981 to 73,600 in 1991. Nuclear generating capacity will increase from 58 to 124 gigawatts, based on the midline forecast of the Energy Information Administration. The projections assume that current regulations will remain in effect and no new plans for additional generating facilities will be initiated

Baseline requirements for assessment of mining impact using biological monitoring

International Nuclear Information System (INIS)

Humphrey, C.L.; Dostine, P.L.

1995-01-01

Biological monitoring programmes for environmental protection should provide for both early detection of possible adverse effects, and assessment of the ecological significance of these effects. Monitoring techniques are required that include responses sensitive to the impact, that can be subjected to rigorous statistical analysis and for which statistical power is high. Such issues in baseline research of 'what and how to measure?' and 'for how long?' have been the focus of a programme being developed to monitor and assess effects of mining operations on the essentially pristine, freshwater ecosystems of the Alligator Rivers Region (ARR) in tropical northern Australia. Application of the BACIP (Before, After, Control, Impact, Paired differences) design, utilizing a form of temporal replication, to univariate (single species) and multivariate (community) data is described. The BACIP design incorporates data from single control and impact sites. We argue for modification of the design for particular studies conducted in streams, to incorporate additional independent control sites from adjacent catchment. Inferential power, by way of (i) more confidently attributing cause to an observed change and (ii) providing information about the ecological significance of the change, will be enhanced using a modified BACIP design. In highly valued environments such as the ARR, monitoring programmes require application of statistical tests with high power to guarantee that an impact no greater than a prescribed amount has gone undetected. A minimum number of baseline years using the BACIP approach would therefore be required in order to achieve some desired level of statistical power. This paper describes the results of power analyses conducted on 2-5 years (depending upon the technique) of baseline data from streams of the ARR and discuss the implications of these results for management. 44 refs., 1 tab., 3 figs

Safety of power transformers, power supplies, reactors and similar products - Part 1: General requirements and tests

CERN Document Server

International Electrotechnical Commission. Geneva

1998-01-01

This International Standard deals with safety aspects of power transformers, power supplies, reactors and similar products such as electrical, thermal and mechanical safety. This standard covers the following types of dry-type transformers, power supplies, including switch mode power supplies, and reactors, the windings of which may be encapsulated or non-encapsulated. It has the status of a group safety publication in accordance with IEC Guide 104.

An Approach to Establish Design Requirements for Human-System Interface (HSI) of Automatic Systems in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Nuraslinda, Anuar; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-05-15

This paper aims to demonstrate an approach to establish the design requirements for automatic systems in nuclear power plant (NPP) by using a powerful tool called Itemized Sequence Diagram (ISD). The process starts with function allocation by defining a set of levels of automation (LOAs). Then, task allocation is done using the ISD and finally the design requirements are established by examining the interaction points between human operator and automation, which are all located on the interface as modeled in the ISD. The strengths of this approach are discussed and a suggestion to integrate with that of the methodology employed to produce the existing guidelines or guidance is included in this paper. Some issues of automation have been addressed earlier in this paper and 12 design requirements that address human-system interaction were suggested by using the ISD as a tool to identify the interaction points between human operator and automation. The integration of the proposed approach in this paper with that of existing guidance could result in the new issue identification that would call for the establishment of new guidance. For example, Requirement 11 states that the HSI should provide the means for take-over from automatic to manual control was not mentioned in the existing guidance.

Ankle and Midfoot Power During Walking and Stair Ascent in Healthy Adults.

Science.gov (United States)

DiLiberto, Frank E; Nawoczenski, Deborah A; Houck, Jeff

2018-02-27

Ankle power dominates forward propulsion of gait, but midfoot power generation is also important for successful push off. However, it is unclear if midfoot power generation increases or stays the same in response to propulsive activities that induce larger external loads and require greater ankle power. The purpose of this study was to examine ankle and midfoot power in healthy adults during progressively more demanding functional tasks. Multi-segment foot motion (tibia, calcaneus, forefoot) and ground reaction forces were recorded as participants (N=12) walked, ascended a standard step, and ascended a high step. Ankle and midfoot positive peak power and total power, and the proportion of midfoot to ankle total power were calculated. One-way repeated measures ANOVAs were conducted to evaluate differences across tasks. Main effects were found for ankle and midfoot peak and total powers (all p power (p = .331). Ankle and midfoot power significantly increased across each task. Midfoot power increased in proportion to ankle power and in congruence to the external load of a task. Study findings may serve to inform multi-segment foot modeling applications and internal mechanistic theories of normal and pathological foot function.

Survey of extreme load design regulatory agency licensing requirements for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Stevenson, J D

1976-04-01

Since 1965, when extreme load requirements began to be considered explicitly in nuclear power plant design, there has been a gradual divergence in requirements imposed by national regulatory agencies. However, nuclear plant safety is an international problem because of the potential international effects of any postulated plant failure. For this reason this paper has been prepared in an attempt to highlight the differences in national criteria currently used in the extreme load design of nuclear plant facilities. No attempt has been made to evaluate the relative merit of the criteria established by the various national regulatory agencies. This paper presents the results of a recent survey made of national atomic energy regulatory agencies and major nuclear steam supply design agencies, which requested a summary of current licensing criteria associated with earthquake, extreme wind (tornado), flood, airplane crash and accident (pipe break) loads applicable within the various national jurisdictions. Also presented are a number of comparisons which are meant to illustrate the differences in national regulatory criteria.

Survey of extreme load design regulatory agency licensing requirements for nuclear power plants

International Nuclear Information System (INIS)

Stevenson, J.D.

1976-01-01

Since 1965, when extreme load requirements began to be considered explicitly in nuclear power plant design, there has been a gradual divergence in requirements imposed by national regulatory agencies. However, nuclear plant safety is an international problem because of the potential international effects of any postulated plant failure. For this reason this paper has been prepared in an attempt to highlight the differences in national criteria currently used in the extreme load design of nuclear plant facilities. No attempt has been made to evaluate the relative merit of the criteria established by the various national regulatory agencies. This paper presents the results of a recent survey made of national atomic energy regulatory agencies and major nuclear steam supply design agencies, which requested a summary of current licensing criteria associated with earthquake, extreme wind (tornado), flood, airplane crash and accident (pipe break) loads applicable within the various national jurisdictions. Also presented are a number of comparisons which are meant to illustrate the differences in national regulatory criteria. (Auth.)

Predicting Greater Prairie-Chicken Lek Site Suitability to Inform Conservation Actions.

Directory of Open Access Journals (Sweden)

Torre J Hovick

Full Text Available The demands of a growing human population dictates that expansion of energy infrastructure, roads, and other development frequently takes place in native rangelands. Particularly, transmission lines and roads commonly divide rural landscapes and increase fragmentation. This has direct and indirect consequences on native wildlife that can be mitigated through thoughtful planning and proactive approaches to identifying areas of high conservation priority. We used nine years (2003-2011 of Greater Prairie-Chicken (Tympanuchus cupido lek locations totaling 870 unique leks sites in Kansas and seven geographic information system (GIS layers describing land cover, topography, and anthropogenic structures to model habitat suitability across the state. The models obtained had low omission rates (0.81, indicating high model performance and reliability of predicted habitat suitability for Greater Prairie-Chickens. We found that elevation was the most influential in predicting lek locations, contributing three times more predictive power than any other variable. However, models were improved by the addition of land cover and anthropogenic features (transmission lines, roads, and oil and gas structures. Overall, our analysis provides a hierarchal understanding of Greater Prairie-Chicken habitat suitability that is broadly based on geomorphological features followed by land cover suitability. We found that when land features and vegetation cover are suitable for Greater Prairie-Chickens, fragmentation by anthropogenic sources such as roadways and transmission lines are a concern. Therefore, it is our recommendation that future human development in Kansas avoid areas that our models identified as highly suitable for Greater Prairie-Chickens and focus development on land cover types that are of lower conservation concern.

Active convergence between the Lesser and Greater Caucasus in Georgia: Constraints on the tectonic evolution of the Lesser-Greater Caucasus continental collision

Science.gov (United States)

Sokhadze, G.; Floyd, M.; Godoladze, T.; King, R.; Cowgill, E. S.; Javakhishvili, Z.; Hahubia, G.; Reilinger, R.

2018-01-01

We present and interpret newly determined site motions derived from GPS observations made from 2008 through 2016 in the Republic of Georgia, which constrain the rate and locus of active shortening in the Lesser-Greater Caucasus continental collision zone. Observation sites are located along two ∼160 km-long profiles crossing the Lesser-Greater Caucasus boundary zone: one crossing the Rioni Basin in western Georgia and the other crossing further east near the longitude of Tbilisi. Convergence across the Rioni Basin Profile occurs along the southern margin of the Greater Caucasus, near the surface trace of the north-dipping Main Caucasus Thrust Fault (MCTF) system, and is consistent with strain accumulation on the fault that generated the 1991 MW6.9 Racha earthquake. In contrast, convergence along the Tbilisi Profile occurs near Tbilisi and the northern boundary of the Lesser Caucasus (near the south-dipping Lesser Caucasus Thrust Fault), approximately 50-70 km south of the MCTF, which is inactive within the resolution of geodetic observations (< ± 0.5 mm/yr) at the location of the Tbilisi Profile. We suggest that the southward offset of convergence along strike of the range is related to the incipient collision of the Lesser-Greater Caucasus, and closing of the intervening Kura Basin, which is most advanced along this segment of the collision zone. The identification of active shortening near Tbilisi requires a reevaluation of seismic hazards in this area.

Technical evaluation of RETS-required reports for Zion Nuclear Power Station, Units 1 and 2 for 1983

International Nuclear Information System (INIS)

Young, T.E.; Magleby, E.H.

1985-01-01

A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Commonwealth Edison's Zion Nuclear Power Station during 1983. The two periodic reports reviewed: (1) were the Effluent and Waste Disposal Semiannual Report, July-December 1983, and (2) the Radioactive Waste and Environmental Monitoring Annual Report - 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

Review on the Strength Development Required for the Concrete Structure of Nuclear Power Plant under Cold Weather Conditions

Energy Technology Data Exchange (ETDEWEB)

Koh, Kyung Teak; Park, Chun Jin; Ryu, Gum Sung; Kim, Do Gyeum; Lee, Jang Hwa [Korea Institute of Construction Technology, Goyang (Korea, Republic of)

2011-10-15

As a part of a Department of Energy-Nuclear According to the specifications for the construction execution for a nuclear power plant (NPP), the cold weather concrete should be facilitated that comply with the regulations of ACI-306R. Here, in terms of the standards applied to the cold weather concrete, such concrete should be applied in the case where the daily average temperature is 5 .deg. C or less. So, according to the analysis on the average temperature in winter over the last one year at each NPP construction area, it was found that such had lowered by about 0.5 - 2 .deg. C as compared to the temperature during the normal years (the last ten years) and the number of days applied to the cold weather concrete according to the ACI regulations was shown as 83, so as around 1/4 of year falls into the cold weather conditions and furthermore the recent weather is getting severe, it is necessary to perform the appropriate insulation curing for the cold weather concrete. On the other hand, according to the regulations with regards to the curing conditions for cold weather concrete, the insulation curing of such should be appropriately performed under an environment of 5 .deg. C or greater until the strength of 3.5 MPa (500 Psi) develops. Likewise, according to the regulations regarding the cold weather concrete in the domestic concrete specifications, the insulation curing should be performed until a strength development of 5 MPa (715 Psi) considering the safety factor indicated to the ACI regulation under the temperature of 5 .deg. C or greater. According to the above-mentioned regulations, the NPP structure is required to develop a minimum strength of 5 MPa or greater, and to maintain such important qualities, including strength development, early anti-freezing and duality under cold weather conditions. However, even though the early strength of 5 MPa or greater is secured under the recent abnormal weather conditions and cold weather conditions, if the structure is

Wind Farms’ Spatial Distribution Effect on Power System Reserves Requirements

DEFF Research Database (Denmark)

Sørensen, Poul Ejnar; Cutululis, Nicolaos Antonio

2010-01-01

The wind power development during last millennium was typically based on small wind turbines dispersed over large areas, leading to a significant smoothing of the wind power fluctuations in a power system balancing area. The present development goes towards much larger wind farms, concentrated...

Lessons in power: Lyndon Johnson revealed. A conversation with historian Robert A. Caro.

Science.gov (United States)

Caro, Robert A

2006-04-01

No one can lead who does not first acquire power, and no leader can be great who does not know how to use that power. The trouble is that the combination of the two skills is rare. Amassing power requires ambition, a focused pragmatism, and a certain ruthlessness that is often at odds with the daring, idealistic vision needed to achieve great things with that power. The tension is as real in business as it is in politics. This magazine is replete with examples of successful senior managers who could not make the switch from ambitious executive to corporate leader because they did not know what to do with the power they had so expertly accumulated. Robert Caro is a student of power. For the past 27 years, the two-time Pulitzer prize-winning biographer of Robert Moses and Lyndon Johnson has focused on the question of how Johnson amassed and wielded power. Caro's deep understanding of the inner workings of power offers senior executives a nuanced picture of leadership at the highest level. In this wide-ranging conversation, Caro shares his insights about the nature of power, the complexity of ambition, and the role that the greater good can play in the making of a leader. Power doesn't always corrupt, he insists. But what it invariably does is reveal a leader's true nature. "Today, when CEOs have acquired more and more power to change our lives," Caro says,"they have become like presidents in their own right, and they, too, need to align themselves with something greater than themselves if they hope to become truly great leaders."

Study on VSC HVDC Modeling and Control Strategies for Wind Power Integration

DEFF Research Database (Denmark)

Korompili, Asimenia; Wu, Qiuwei

Recently, more and more offshore wind farms have been integrated to the power systems. In the next years, these offshore power plants are going to be rated at higher capacities and located in larger distances from the coast. This results in greater interest in the transmission technologies, which....... Finally, more specific requirements are given for the grid connection of offshore wind farms through HVDC systems. These rules derived from the combination of grid codes for the integration of offshore wind farms and grid codes for the operation of HVDC transmission systems, connecting power plants...... are available for the grid connection of the offshore wind farms. In this report various transmission systems are presented. Precisely, the HVAC systems, which have dominated up until now in the power transfer sector, are briefly analysed, by providing their advantages, as well as the bottlenecks that occur...

The power to resist: The relationship between power, stigma, and negative symptoms in schizophrenia

Science.gov (United States)

Campellone, Timothy R.; Caponigro, Janelle M.; Kring, Ann M.

2014-01-01

Stigmatizing beliefs about mental illness can be a daily struggle for people with schizophrenia. While investigations into the impact of internalizing stigma on negative symptoms have yielded mixed results, resistance to stigmatizing beliefs has received little attention. In this study, we examined the linkage between internalized stigma, stigma resistance, negative symptoms, and social power, or perceived ability to influence others during social interactions among people with schizophrenia. Further, we sought to determine whether resistance to stigma would be bolstered by social power, with greater power in relationships with other possibly buffering against motivation/pleasure negative symptoms. Fifty-one people with schizophrenia or schizoaffective disorder completed measures of social power, internalized stigma, and stigma resistance. Negative symptoms were assessed using the Clinical Assessment Interview for Negative Symptoms (CAINS). Greater social power was associated with less internalized stigma and negative symptoms as well as more stigma resistance. Further, the relationship between social power and negative symptoms was partially mediated by stigma resistance. These findings provide evidence for the role of stigma resistance as a viable target for psychosocial interventions aimed at improving motivation and social power in people with schizophrenia. PMID:24326180

The power to resist: the relationship between power, stigma, and negative symptoms in schizophrenia.

Science.gov (United States)

Campellone, Timothy R; Caponigro, Janelle M; Kring, Ann M

2014-02-28

Stigmatizing beliefs about mental illness can be a daily struggle for people with schizophrenia. While investigations into the impact of internalizing stigma on negative symptoms have yielded mixed results, resistance to stigmatizing beliefs has received little attention. In this study, we examined the linkage between internalized stigma, stigma resistance, negative symptoms, and social power, or perceived ability to influence others during social interactions among people with schizophrenia. Further, we sought to determine whether resistance to stigma would be bolstered by social power, with greater power in relationships with other possibly buffering against motivation/pleasure negative symptoms. Fifty-one people with schizophrenia or schizoaffective disorder completed measures of social power, internalized stigma, and stigma resistance. Negative symptoms were assessed using the Clinical Assessment Interview for Negative Symptoms (CAINS). Greater social power was associated with less internalized stigma and negative symptoms as well as more stigma resistance. Further, the relationship between social power and negative symptoms was partially mediated by stigma resistance. These findings provide evidence for the role of stigma resistance as a viable target for psychosocial interventions aimed at improving motivation and social power in people with schizophrenia. © 2013 Published by Elsevier Ireland Ltd.

The power and robustness of maximum LOD score statistics.

Science.gov (United States)

Yoo, Y J; Mendell, N R

2008-07-01

The maximum LOD score statistic is extremely powerful for gene mapping when calculated using the correct genetic parameter value. When the mode of genetic transmission is unknown, the maximum of the LOD scores obtained using several genetic parameter values is reported. This latter statistic requires higher critical value than the maximum LOD score statistic calculated from a single genetic parameter value. In this paper, we compare the power of maximum LOD scores based on three fixed sets of genetic parameter values with the power of the LOD score obtained after maximizing over the entire range of genetic parameter values. We simulate family data under nine generating models. For generating models with non-zero phenocopy rates, LOD scores maximized over the entire range of genetic parameters yielded greater power than maximum LOD scores for fixed sets of parameter values with zero phenocopy rates. No maximum LOD score was consistently more powerful than the others for generating models with a zero phenocopy rate. The power loss of the LOD score maximized over the entire range of genetic parameters, relative to the maximum LOD score calculated using the correct genetic parameter value, appeared to be robust to the generating models.

Correlations between power and test reactor data bases

International Nuclear Information System (INIS)

Guthrie, G.L.; Simonen, E.P.

1989-02-01

Differences between power reactor and test reactor data bases have been evaluated. Charpy shift data has been assembled from specimens irradiated in both high-flux test reactors and low-flux power reactors. Preliminary tests for the existence of a bias between test and power reactor data bases indicate a possible bias between the weld data bases. The bias is nonconservative for power predictive purposes, using test reactor data. The lesser shift for test reactor data compared to power reactor data is interpreted primarily in terms of greater point defect recombination for test reactor fluxes compared to power reactor fluxes. The possibility of greater thermal aging effects during lower damage rates is also discussed. 15 refs., 5 figs., 2 tabs

Low Power Design with High-Level Power Estimation and Power-Aware Synthesis

CERN Document Server

Ahuja, Sumit; Shukla, Sandeep Kumar

2012-01-01

Low-power ASIC/FPGA based designs are important due to the need for extended battery life, reduced form factor, and lower packaging and cooling costs for electronic devices. These products require fast turnaround time because of the increasing demand for handheld electronic devices such as cell-phones, PDAs and high performance machines for data centers. To achieve short time to market, design flows must facilitate a much shortened time-to-product requirement. High-level modeling, architectural exploration and direct synthesis of design from high level description enable this design process. This book presents novel research techniques, algorithms,methodologies and experimental results for high level power estimation and power aware high-level synthesis. Readers will learn to apply such techniques to enable design flows resulting in shorter time to market and successful low power ASIC/FPGA design. Integrates power estimation and reduction for high level synthesis, with low-power, high-level design; Shows spec...

Requirements for a Hydrogen Powered All-Electric Manned Helicopter

Science.gov (United States)

Datta, Anubhav

2012-01-01

The objective of this paper is to set propulsion system targets for an all-electric manned helicopter of ultra-light utility class to achieve performance comparable to combustion engines. The approach is to begin with a current two-seat helicopter (Robinson R 22 Beta II-like), design an all-electric power plant as replacement for its existing piston engine, and study performance of the new all-electric aircraft. The new power plant consists of high-pressure Proton Exchange Membrane fuel cells, hydrogen stored in 700 bar type-4 tanks, lithium-ion batteries, and an AC synchronous permanent magnet motor. The aircraft and the transmission are assumed to remain the same. The paper surveys the state of the art in each of these areas, synthesizes a power plant using best available technologies in each, examines the performance achievable by such a power plant, identifies key barriers, and sets future technology targets to achieve performance at par with current internal combustion engines.

Requirements for, and training and certification of, quality assurance technicians for nuclear power plants

International Nuclear Information System (INIS)

Saiz, A.; Mir, A.; Serrano, J.

1982-01-01

The paper examines the requirements for, and training and certification of, technicians working in a quality assurance department at periods when the site, the main supplier and the engineering firm are being selected for construction, commissioning and operation of a light-water nuclear power plant with an output of approximately 1000 MW(e). In determining the system to be applied for the present work, account is taken of the special fields of engineering, supply, commissioning and operation. To this end, an analysis is made of the necessary organization, pointing out the number of technicians in each of the phases mentioned, and the necessary experience and knowledge required for discharging the functions indicated and for obtaining the appropriate certification. The second generation of Spanish nuclear power stations - about 7500MW(e) - demonstrated the need for quality assurance technicians. The Spanish Atomic Forum, a member of Foratom, is the first Spanish body to deal with the problem of training of such technicians at the national level through holding of seminars. This led to the appearance (in April 1974) of the first publication in Spanish on these techniques, a document which is still being used for teaching purposes. Later, it was the university and the professional associations which, with the support of the State Administration, undertook to provide this instruction. The paper also analyses Spanish experience in the teaching of quality assurance techniques during the period 1975-80, describing the programmes and contents of the courses

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

Power market competition

International Nuclear Information System (INIS)

Kelly, J.

1998-01-01

In the Unites States the prospect of greater competition in wholesale power market was immediately eclipsed by talk of retail competition. Attempts to move to retail competition have been costly and complex. Prudent public policy and economic analyses suggest that retail competition not be implemented until it can first be demonstrated that effective competition exists in wholesale power markets [it

Advancing U.S. Strategic Communication through Greater Civilian-Military Coordination and Integration

Science.gov (United States)

2012-06-01

WARFIGHTING SCHOOL ADVANCING U.S. STRATEGIC COMMUNICATION THROUGH GREATER CIVILIAN-MILITARY COORDINATION AND INTERGRATION by Wendy A. Kolls U.S... products synchronized with the actions of all instruments of national power." Department af Defense Dictionary of Military and Associated Terms...the "British street," the "American street," and the "Israeli street.ŗ Selling "Brand America" If the " product " was America, then the thinking in

High power valve regulated lead-acid batteries for new vehicle requirements

Science.gov (United States)

Trinidad, Francisco; Sáez, Francisco; Valenciano, Jesús

The performance of high power VRLA ORBITAL™ batteries is presented. These batteries have been designed with isolated cylindrical cells, providing high reliability to the recombination process, while maintaining, at the same time, a very high compression (>80 kPa) over the life of the battery. Hence, the resulting VRLA modules combine a high rate capability with a very good cycle performance. Two different electrochemically active material compositions have been developed: high porosity and low porosity for starting and deep cycle applications, respectively (depending on the power demand and depth of discharge). Although, the initial performance of the starting version is higher, after a few cycles the active material of the deep cycle version is fully developed, and this achieves the same high rate capability. Both types are capable of supplying the necessary reliability for cranking at the lowest temperature (-40°C). Specific power of over 500 W/kg is achievable at a much lower cost than for nickel-metal hydride systems. Apart from the initial performance, an impressive behaviour of the cycling version has been found in deep cycle applications, due to the highly compressed and high density active material. When submitted to continuous discharge-charge cycles at 75% (IEC 896-2 specification) and 100% (BCI deep cycle) DoD, it has been found that the batteries are still healthy after more than 1000 and 700 cycles, respectively. However, it has been proven that the application of an IUi algorithm (up to 110% of overcharging) with a small constant current charging period at the end of the charge is absolutely necessary to achieve the above results. Without the final boosting period, the cycle life of the battery could be substantially shortened. The high specific power and reliability observed in the tests carried out, would allow ORBITAL™ batteries to comply with the more demanding requirements that are being introduced in conventional and future hybrid electric

Professional performance attributes according to accounting entrepreneurs from greater São Paulo

OpenAIRE

Ivam Ricardo Peleias; Rafael Augusto Lourenço; Marcos Reinaldo Severino Peters; Carlos Eduardo Farcin Lavarda

2015-01-01

Accounting has a broad activity universe, which requires skilled professionals who are prepared to practice the profession. One possibility is to be an accounting entrepreneur, whose profile requires specific attributes and attitudes. The results reported on in this paper derive from a research developed using the oral history technique, concerning the identification and analysis of attributes valued in the performance of the profession by accounting entrepreneurs from greater São Paulo. A fi...

Economic requirements for competitive laser fusion power production

International Nuclear Information System (INIS)

Hogan, W.J.; Meier, W.R.

1986-01-01

An economic model of a laser fusion commercial power plant is used to identify the design and operating regimes of the driver, target and reaction chamber that will result in economic competitiveness with future fission and coal plants. The authors find that, for a plant with a net power of 1 GW/sub e/, the cost of the driver must be less than $0.4 to 0.6 B, and the recirculating power fraction must be less than 25%. Target gain improvements at low driver energy are the most beneficial but also the most difficult to achieve. The optimal driver energy decreases with increasing target technology. The sensitivity of the cost of electricity to variations in cost and performance parameters decreases with increasing target technology. If chamber pulse rates of a few Hz can be achieved, then gains of 80-100 are sufficient, and higher pulse rates do not help much. Economic competitiveness becomes more difficult with decreasing plant size. Finally, decreasing the cost of the balance of plant has the greatest beneficial effect on economic competitiveness

Greater happiness for a greater number: Is that possible? If so how? (Arabic)

NARCIS (Netherlands)

R. Veenhoven (Ruut); E. Samuel (Emad)

2012-01-01

textabstractWhat is the final goal of public policy? Jeremy Bentham (1789) would say: greater happiness for a greater number. He thought of happiness as subjective enjoyment of life; in his words as “the sum of pleasures and pains”. In his time, the happiness of the great number could not be

Human factors in atomic power plant

International Nuclear Information System (INIS)

Kawano, Ryutaro

1997-01-01

To ensure safety should have priority over all other things in atomic power plants. In Chernobyl accident, however, various human factors including the systems for bulb check after inspection and communication, troubles in the interface between hardwares such as warning speakers and instruments, and their operators, those in education and training for operators and those in the general management of the plant have been pointed out. Therefore, the principles and the practical measures from the aspect of human factors in atomic power plants were discussed here. The word, ''human factor'' was given a definition in terms of the direct cause and the intellectual system. An explanatory model for human factors, model SHEL constructed by The Tokyo Electric Power Co., Ltd., Inc. was presented; the four letter mean software(S), hardware(H), environment(E) and liveware(L). In the plants of the company, systemic measures for human error factors are taken now in all steps not only for design, operation and repairing but also the step for safety culture. Further, the level required for the safety against atomic power is higher in the company than those in other fields. Thus, the central principle in atomic power plants is changing from the previous views that technology is paid greater importance to a view regarding human as most importance. (M.N.)

Shape Biased Low Power Spin Dependent Tunneling Magnetic Field Sensors

Science.gov (United States)

Tondra, Mark; Qian, Zhenghong; Wang, Dexin; Nordman, Cathy; Anderson, John

2001-10-01

Spin Dependent Tunneling (SDT) devices are leading candidates for inclusion in a number of Unattended Ground Sensor applications. Continued progress at NVE has pushed their performance to 1OOs of pT I rt. Hz 1 Hz. However, these sensors were designed to use an applied field from an on-chip coil to create an appropriate magnetic sensing configuration. The power required to generate this field (^100mW) is significantly greater than the power budget (^lmW) for a magnetic sensor in an Unattended Ground Sensor (UGS) application. Consequently, a new approach to creating an ideal sensing environment is required. One approach being used at NVE is "shape biasing." This means that the physical layout of the SDT sensing elements is such that the magnetization of the sensing film is correct even when no biasing field is applied. Sensors have been fabricated using this technique and show reasonable promise for UGS applications. Some performance trade-offs exist. The power is easily tinder 1 MW, but the sensitivity is typically lower by a factor of 10. This talk will discuss some of the design details of these sensors as well as their expected ultimate performance.

Fracture toughness requirements of reactor vessel material in evaluation of the safety analysis report of nuclear power plants

International Nuclear Information System (INIS)

Widia Lastana Istanto

2011-01-01

Fracture toughness requirements of reactor vessel material that must be met by applicants for nuclear power plants construction permit has been investigated in this paper. The fracture toughness should be described in the Safety Analysis Reports (SARs) document that will be evaluated by the Nuclear Energy Regulatory Agency (BAPETEN). Because BAPETEN does not have a regulations or standards/codes regarding the material used for the reactor vessel, especially in the fracture toughness requirements, then the acceptance criteria that applied to evaluate the fracture toughness of reactor vessel material refers to the regulations/provisions from the countries that have been experienced in the operation of nuclear power plants, such as from the United States, Japan and Korea. Regulations and standards used are 10 CFR Part 50, ASME and ASTM. Fracture toughness of reactor vessel materials are evaluated to ensure compliance of the requirements and provisions of the Regulatory Body and the applicable standards, such as ASME or ASTM, in order to assure a reliability and integrity of the reactor vessels as well as providing an adequate safety margin during the operation, testing, maintenance, and postulated accident conditions over the reactor vessel lifetime. (author)

Emergency power systems at nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

The Effect of Aortic Compliance on Left Ventricular Power Requirement

Science.gov (United States)

Pahlevan, Niema; Gharib, Morteza

2009-11-01

Aortic compliance depends on both geometry and mechanical properties of the aorta. Reduction in arterial compliance has been associated with aging, smoking, and multiple cardiovascular diseases. Increased stiffness of the aorta affects the wave dynamics in the aorta by increasing both pulse pressure amplitude and wave speed. We hypothesized that decreased aortic compliance leads to an increased left ventricular power requirement for a fixed cardiac output due to altered pulse pressure and pulse wave velocity. We used a computational approach using the finite element method for solid and fluid domains coupled to each other by using the direct coupling method. A nonlinear material model was used for the solid wall. The fluid flow model was considered to be Newtonian, incompressible, and laminar. The simulation was performed for a heart rate of 75 beats per minute for six different compliances while keeping the cardiac output and the peripheral resistance constant. The results show a trend towards increased left ventricular energy expenditure per cycle with decreased compliance. The relevance of these findings to clinical observations will be discussed.

The Future of Economic Power

OpenAIRE

Malanciuc Bogdan Simion

2014-01-01

The importance of power in the development of society is undeniable. The power relations between national economies are more and more important and should be considered in every international economics analysis. Economic power has become the bedrock of both the military and the political power. Today the balance of economic power is shifting. The emerging states (China in the first place) are now demanding a greater role in global politics, challenging the existing international order dominat...

Power requirements reducing of FBG based all-optical switching

Science.gov (United States)

Scholtz, Ľubomír.; Solanská, Michaela; Ladányi, Libor; Müllerová, Jarmila

2017-12-01

Although Fiber Bragg gratings (FBGs) are well known devices, their using as all-optical switching elements has been still examined. Current research is focused on optimization of their properties for their using in future all-optical networks. The main problem are high switching intensities needed for achieving the changes of the transmission state. Over several years switching intensities have been reduced from hundreds of GW/cm2 to tens of MW/cm2 by selecting appropriate gratings and signal parameters or using suitable materials. Two principal nonlinear effects with similar power requirements can result in the bistable transmission/reflection of an input optical pulse. In the self-phase modulation (SPM) regime switching is achieved by the intense probe pulse itself. Using cross-phase modulation (XPM) a strong pump alters the FBG refractive index experienced by a weak probe pulse. As a result of this the detuning of the probe pulse from the center of the photonic band gap occurs. Using of XPM the effect of modulation instability is reduced. Modulation instability which is the main SPM degradation mechanism. We focused on nonlinear FBGs based on chalcogenide glasses which are very often used in various applications. Thanks to high nonlinear parameters chalcogenide glasses are suitable candidates for reducing switching intensities of nonlinear FBGs.

Experiences of power-up rating in Taiwan

International Nuclear Information System (INIS)

Liao, C. C.; Lai, S. Y.; Chen, Y. B.

2010-10-01

Taiwan has six nuclear power reactors in operation, and two advanced reactors under construction. Measurement Uncertainty Recapture (MU R) type power up rates have been implemented for all the operating units. MU Rs are less than 2 percent and are achieved by using more advanced feedwater flow measurement devices to more precisely measure feedwater flow, which is used to calculate reactor thermal power. The other two types of power up rates are stretch power up rates (SPU) and extended power up rates (EPU). SPU are typically up to 7 percent and EPU are greater that 7 percent but less than 20%. The Atomic Energy Council (Aec) regulates the maximum thermal power level at which a nuclear power plant may operate. In order to increase the rated thermal power of a plant, utility needs to submit an application to the Aec for approval. Detailed safety analysis is required and will be thoroughly reviewed by Aec special task force to ensure the plant safety after implementing the power up rate. Important findings will be documented in the safety evaluation reports. In 2006, Tai power submitted Kuosheng nuclear power plants MU R application, which was the first power up rate application in Taiwan. Till middle of 2009, Tai power has completed the MU R project for all the existing units. The actual thermal power up rates of the six units are whit in the range of 0.3% to 1.5%, resulting in net 56.3 M We increase. Following the success of MU R, Tai power has lunched another project for SPU. In order to enhance the regulatory review process, Aec has drafted a guideline for SPU and EPU by mainly referencing U.S. experience. This guideline shall be beneficial to both licensee and regulatory body in either document preparation or safety review work for the future power up rate applications. (Author)

Simulation of RF power and multi-cusp magnetic field requirement for H{sup −} ion sources

Energy Technology Data Exchange (ETDEWEB)

Pathak, Manish [Ion Source Lab., Proton Linac & Superconducting Cavities Division, Raja Ramanna Centre for Advanced Technology, Indore, Madhya Pradesh 452013 (India); Senecha, V.K., E-mail: kumarvsen@gmail.com [Ion Source Lab., Proton Linac & Superconducting Cavities Division, Raja Ramanna Centre for Advanced Technology, Indore, Madhya Pradesh 452013 (India); Homi Bhabha National Institute, Raja Ramanna Centre for Advanced Technology, Indore, Madhya Pradesh 452013 (India); Kumar, Rajnish; Ghodke, Dharmraj V. [Ion Source Lab., Proton Linac & Superconducting Cavities Division, Raja Ramanna Centre for Advanced Technology, Indore, Madhya Pradesh 452013 (India)

2016-12-01

A computer simulation study for multi-cusp RF based H{sup −} ion source has been carried out using energy and particle balance equation for inductively coupled uniformly dense plasma considering sheath formation near the boundary wall of the plasma chamber for RF ion source used as high current injector for 1 Gev H{sup −} Linac project for SNS applications. The average reaction rates for different reactions responsible for H{sup −} ion production and destruction have been considered in the simulation model. The RF power requirement for the caesium free H{sup -} ion source for a maximum possible H{sup −} ion beam current has been derived by evaluating the required current and RF voltage fed to the coil antenna using transformer model for Inductively Coupled Plasma (ICP). Different parameters of RF based H{sup −} ion source like excited hydrogen molecular density, H{sup −} ion density, RF voltage and current of RF antenna have been calculated through simulations in the presence and absence of multicusp magnetic field to distinctly observe the effect of multicusp field. The RF power evaluated for different H{sup −} ion current values have been compared with the experimental reported results showing reasonably good agreement considering the fact that some RF power will be reflected from the plasma medium. The results obtained have helped in understanding the optimum field strength and field free regions suitable for volume emission based H{sup −} ion sources. The compact RF ion source exhibits nearly 6 times better efficiency compare to large diameter ion source.

Substantial reductions of input energy and peak power requirements in targets for heavy ion fusion

International Nuclear Information System (INIS)

Mark, J.W.K.; Pan, Y.L.

1986-01-01

Two ways of reducing the requirements of the heavy ion driver for inertial confinement fusion (ICF) target implosion are described. Compared to estimates of target gain not using these methods, the target input energy and peak power may be reduced by about a factor of two with the use of the hybrid-implosion concept. Another factor of two reduction in input energy may be obtained with the use of spin-polarized DT fuel in the ICF target

The existing Nordic regulating power market. FlexPower WP1 - Report 1

Energy Technology Data Exchange (ETDEWEB)

Bang, C.; Fock, F.; Togeby, M.

2011-06-15

The FlexPower project investigates the possibility of using broadcasted dynamic electricity prices as a simple and low cost means to activating a large number of flexible small-scale power units. The aim is to provide regulating power via an aggregated response from the numerous units on a volunteer basis. The report provides a brief historical and contextual background of the Nordic electricity market. Thereafter it goes into greater detail describing the Nordic regulating power market, both how it functions in practice, and examining some of the historical trends from a Danish perspective. (LN)

Assessment of Joystick control during the performance of powered wheelchair driving tasks

Directory of Open Access Journals (Sweden)

Routhier François

2011-05-01

Full Text Available Abstract Background Powered wheelchairs are essential for many individuals who have mobility impairments. Nevertheless, if operated improperly, the powered wheelchair poses dangers to both the user and to those in its vicinity. Thus, operating a powered wheelchair with some degree of proficiency is important for safety, and measuring driving skills becomes an important issue to address. The objective of this study was to explore the discriminate validity of outcome measures of driving skills based on joystick control strategies and performance recorded using a data logging system. Methods We compared joystick control strategies and performance during standardized driving tasks between a group of 10 expert and 13 novice powered wheelchair users. Driving tasks were drawn from the Wheelchair Skills Test (v. 4.1. Data from the joystick controller were collected on a data logging system. Joystick control strategies and performance outcome measures included the mean number of joystick movements, time required to complete tasks, as well as variability of joystick direction. Results In simpler tasks, the expert group's driving skills were comparable to those of the novice group. Yet, in more difficult and spatially confined tasks, the expert group required fewer joystick movements for task completion. In some cases, experts also completed tasks in approximately half the time with respect to the novice group. Conclusions The analysis of joystick control made it possible to discriminate between novice and expert powered wheelchair users in a variety of driving tasks. These results imply that in spatially confined areas, a greater powered wheelchair driving skill level is required to complete tasks efficiently. Based on these findings, it would appear that the use of joystick signal analysis constitutes an objective tool for the measurement of powered wheelchair driving skills. This tool may be useful for the clinical assessment and training of powered

The basic concepts of a fuel-power detector for nuclear power reactors

International Nuclear Information System (INIS)

Lynch, G.F.

1979-01-01

Fuel power is proposed as an alternative to neutron or gamma-ray flux for control and safety functions in CANDU power reactors. To satisfy in-core power monitoring requirements, a detector whose dynamic response corresponds to the heat production rate in the fuel is needed. This report explores the concept of tailoring the response characteristics of a mixed-response self-powered flux detector to match the requirements of an ideal fuel-power detector. (author)

From the world and asian energy demand and environmental requirement to foresee the prospect of Guangdong nuclear power development

International Nuclear Information System (INIS)

Qiu Wenfeng

1999-01-01

The world economy development depends on the development of energy resource. The general energy resource which is mainly fossil fuel will bring damage to the global environment. To stop the global environment becoming worse, cleaner energy will be used in the twenty-first century. The situation which the Guangdong economic growth rate is higher than that of inland average will not change in short period. Economic development requires the suitable electric power supply. The foreground of Guangdong electric power development will be hopeful. To develop electric power is to develop coal, oil, gas, nuclear, hydroelectric and the other renewable power. As to Guangdong, because the environmental pollution is quite serious, it is impossible to develop much more coal-fired power plants. Our country is oil net importer, oil-fired power plants are also restricted. It is acceptable to import natural gas in appropriate degree to generate electricity in the near future to improve environment. To develop hydraulic power is more and more difficult in Guangdong. The hydraulic power from the southwest of China is only as the complement of the Guangdong energy resource, and it is impossible to primarily solve the energy shortage problem. Sunlight, wind, ocean power and terrestrial heat etc. are clean renewable energy, but they can't be used as the wholesale stable industry power. So to develop nuclear power is the certain selection to solve the energy shortage problem and reduce the environmental pollution in Guangdong. (author)

Public power costs less

International Nuclear Information System (INIS)

Moody, D.

1993-01-01

The reasons why residential customers of public power utilities paid less for power than private sector customers is discussed. Residential customers of investor-owned utilities (IOU's) paid average rates that were 28% above those paid by customers by possibly owned systems during 1990. The reasons for this disparity are that management costs faced by public power systems are below those of private power companies, indicating a greater efficiency of management among public power systems, and customer accounts expenses averaged $33.00 per customer for publicly owned electric utilities compared to $39.00 per customer for private utilities

Hybrid wind power balance control strategy using thermal power, hydro power and flow batteries

OpenAIRE

Gelažanskas, Linas; Baranauskas, Audrius; Gamage, Kelum A.A.; Ažubalis, Mindaugas

2016-01-01

The increased number of renewable power plants pose threat to power system balance. Their intermittent nature makes it very difficult to predict power output, thus either additional reserve power plants or new storage and control technologies are required. Traditional spinning reserve cannot fully compensate sudden changes in renewable energy power generation. Using new storage technologies such as flow batteries, it is feasible to balance the variations in power and voltage within very short...

Modernisation for maintaining and improving safety at Nordic nuclear power plants

International Nuclear Information System (INIS)

Hammer, L.; Wahlstroem, B.; Simola, K.

1998-02-01

The safety practices in Finland and Sweden are described and compared in regard of effecting modernisation for safety of the nuclear plants in the two countries, considering new technology and advancing safety requirements as proposed for new reactors. Particular attention is given to strategies for applying new safety requirements to reactors built to earlier standards, and to the interplay between the nuclear utilities and the safety authorities. Overviews are given of past and current modernisation of the nuclear power plants in Finland and Sweden. The management procedures in controlling the implementation of modifications to the nuclear power plants are described and discussed in regard of prevailing differences between Finnish and Swedish practices. A formal modelling technique (SADT) was applied for capture of the essential contents of the relevant documented procedures. Two examples of recent plant modifications in the Finnish nuclear plants in Olkiluoto and Loviisa are described and discussed in greater detail. Recommendations are given. (au)

Modeling ecological minimum requirements for distribution of greater sage-grouse leks: implications for population connectivity across their western range, U.S.A.

Science.gov (United States)

Knick, Steven T; Hanser, Steven E; Preston, Kristine L

2013-06-01

Greater sage-grouse Centrocercus urophasianus (Bonaparte) currently occupy approximately half of their historical distribution across western North America. Sage-grouse are a candidate for endangered species listing due to habitat and population fragmentation coupled with inadequate regulation to control development in critical areas. Conservation planning would benefit from accurate maps delineating required habitats and movement corridors. However, developing a species distribution model that incorporates the diversity of habitats used by sage-grouse across their widespread distribution has statistical and logistical challenges. We first identified the ecological minimums limiting sage-grouse, mapped similarity to the multivariate set of minimums, and delineated connectivity across a 920,000 km(2) region. We partitioned a Mahalanobis D (2) model of habitat use into k separate additive components each representing independent combinations of species-habitat relationships to identify the ecological minimums required by sage-grouse. We constructed the model from abiotic, land cover, and anthropogenic variables measured at leks (breeding) and surrounding areas within 5 km. We evaluated model partitions using a random subset of leks and historic locations and selected D (2) (k = 10) for mapping a habitat similarity index (HSI). Finally, we delineated connectivity by converting the mapped HSI to a resistance surface. Sage-grouse required sagebrush-dominated landscapes containing minimal levels of human land use. Sage-grouse used relatively arid regions characterized by shallow slopes, even terrain, and low amounts of forest, grassland, and agriculture in the surrounding landscape. Most populations were interconnected although several outlying populations were isolated because of distance or lack of habitat corridors for exchange. Land management agencies currently are revising land-use plans and designating critical habitat to conserve sage-grouse and avoid endangered

Modeling ecological minimum requirements for distribution of greater sage-grouse leks: implications for population connectivity across their western range, U.S.A.

Science.gov (United States)

Knick, Steven T.; Hanser, Steven E.; Preston, Kristine L.

2013-01-01

Greater sage-grouse Centrocercus urophasianus (Bonaparte) currently occupy approximately half of their historical distribution across western North America. Sage-grouse are a candidate for endangered species listing due to habitat and population fragmentation coupled with inadequate regulation to control development in critical areas. Conservation planning would benefit from accurate maps delineating required habitats and movement corridors. However, developing a species distribution model that incorporates the diversity of habitats used by sage-grouse across their widespread distribution has statistical and logistical challenges. We first identified the ecological minimums limiting sage-grouse, mapped similarity to the multivariate set of minimums, and delineated connectivity across a 920,000 km2 region. We partitioned a Mahalanobis D2 model of habitat use into k separate additive components each representing independent combinations of species–habitat relationships to identify the ecological minimums required by sage-grouse. We constructed the model from abiotic, land cover, and anthropogenic variables measured at leks (breeding) and surrounding areas within 5 km. We evaluated model partitions using a random subset of leks and historic locations and selected D2 (k = 10) for mapping a habitat similarity index (HSI). Finally, we delineated connectivity by converting the mapped HSI to a resistance surface. Sage-grouse required sagebrush-dominated landscapes containing minimal levels of human land use. Sage-grouse used relatively arid regions characterized by shallow slopes, even terrain, and low amounts of forest, grassland, and agriculture in the surrounding landscape. Most populations were interconnected although several outlying populations were isolated because of distance or lack of habitat corridors for exchange. Land management agencies currently are revising land-use plans and designating critical habitat to conserve sage-grouse and avoid endangered

Education and training requirements of nuclear power plant personnel

International Nuclear Information System (INIS)

Donato, R.; Perlas, C.A.; Conti, E.

1978-01-01

This bibliography was compiled by the Scientific Library staff to help in the intensified training program being undertaken by the Philippine Atomic Energy Commission (PAEC) for the nuclear power plant personnel of the Philippines' first nuclear power reactor. This bibliography covers the period 1955 - 1976 of the Nuclear Science Abstracts and is composed of 281 entries. Arrangement of these entries is by broad subject category

Fuel-Cell-Powered Vehicle with Hybrid Power Management

Science.gov (United States)

Eichenberg, Dennis J.

2010-01-01

Figure 1 depicts a hybrid electric utility vehicle that is powered by hydrogenburning proton-exchange-membrane (PEM) fuel cells operating in conjunction with a metal hydride hydrogen-storage unit. Unlike conventional hybrid electric vehicles, this vehicle utilizes ultracapacitors, rather than batteries, for storing electric energy. This vehicle is a product of continuing efforts to develop the technological discipline known as hybrid power management (HPM), which is oriented toward integration of diverse electric energy-generating, energy-storing, and energy- consuming devices in optimal configurations. Instances of HPM were reported in five prior NASA Tech Briefs articles, though not explicitly labeled as HPM in the first three articles: "Ultracapacitors Store Energy in a Hybrid Electric Vehicle" (LEW-16876), Vol. 24, No. 4 (April 2000), page 63; "Photovoltaic Power Station With Ultracapacitors for Storage" (LEW- 17177), Vol. 27, No. 8 (August 2003), page 38; "Flasher Powered by Photovoltaic Cells and Ultracapacitors" (LEW-17246), Vol. 27, No. 10 (October 2003), page 37; "Hybrid Power Management" (LEW-17520), Vol. 29, No. 12 (December 2005), page 35; and "Ultracapacitor-Powered Cordless Drill" (LEW-18116-1), Vol. 31, No. 8 (August 2007), page 34. To recapitulate from the cited prior articles: The use of ultracapacitors as energy- storage devices lies at the heart of HPM. An ultracapacitor is an electrochemical energy-storage device, but unlike in a conventional rechargeable electrochemical cell or battery, chemical reactions do not take place during operation. Instead, energy is stored electrostatically at an electrode/electrolyte interface. The capacitance per unit volume of an ultracapacitor is much greater than that of a conventional capacitor because its electrodes have much greater surface area per unit volume and the separation between the electrodes is much smaller.

Quality assurance requirements for installation, inspection, and testing of structural concrete and structural steel during the construction phase of nuclear power plants

International Nuclear Information System (INIS)

1975-04-01

This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to quality assurance requirements for installation, inspection, and testing of structural concrete and structural steel during the construction phase of nuclear power plants. This guide applies to all types of nuclear power plants. (U.S.)

Hypothetical requirements on number of personnel in Czechoslovak nuclear power plants

International Nuclear Information System (INIS)

Halik, J.

1990-01-01

The structural changes of Czechoslovak power prevent prediction of labor force development by extrapolating the existing development trends. Nuclear power demands a different qualification and occupation structure of the labor force than conventional power generation. The prediction of the number of personnel is based on data on the expected installed capacity and on its commissioning. The following organizational structures are envisaged for a nuclear power plant: the divisions of the Director, of production, maintenance, radiation safety and quality control, technology and investment, economics and personnel. A total of 15,654 personnel are envisaged for nuclear power plants in 2005. A brief comparison is submitted of labor demands in nuclear power plants in Czechoslovakia and in the world. (M.D.). 1 fig., 4 tabs., 3 refs

Are powerful females powerful enough? Acceleration in gravid green iguanas (Iguana iguana).

Science.gov (United States)

Scales, Jeffrey; Butler, Marguerite

2007-08-01

One demand placed exclusively on the musculoskeletal system of females is maintaining locomotor performance with an increasing load over the reproductive cycle. Here, we examine whether gravid (i.e., "pregnant") iguanas can increase their force and power production to support, stabilize, and accelerate the additional mass of a clutch of eggs. At any acceleration, gravid iguanas produced very high mechanical power (average total power = 673 w/kg; total peak power = 1175 w/kg). While the increase in total power was partly a result of greater propulsive power (average propulsive power = 25% higher, peak propulsive power = 38% higher), increased vertical power (roughly 200% increase) was the main contributor. Gravid iguanas were also able to increase peak forces (propulsive = 23%, mediolateral = 44%, vertical = 42%), and step duration (44%) resulting in greater impulses (i.e., the sum of force produced during a step) to accelerate, balance, and support their increased mass. The increase in step duration and smaller increase in peak propulsive force suggests that gravid iguanas may be force-limited in the direction of motion. We discuss how biomechanical constraints due to females' reproductive role may influence the evolution of the female musculoskeletal systems and contribute to the evolution and maintenance of ecological dimorphism in lizards.

Technology in the policy process - controlling nuclear power

International Nuclear Information System (INIS)

Collingridge, D.

1983-01-01

The discussion in this book is built around nuclear power. The technology of nuclear power is shown to have features which make it inflexible in the sense that, once built, it is difficult and expensive to control. If inflexible technology is to be avoided, it is crucially important to be able to identify this failing at an early stage in the technology's development, before it has acquired an immunity to political control. Again, this problem is approached through the example of nuclear power, in particular the breeder reactor. The breeder is shown to be even less flexible than today's nuclear technology, because it will have higher capital costs, be of greater capital intensity, longer lead time, larger unit size, and will require more infrastructure for its operation. If this is developed, the breeder will be even less open to political control than the nuclear plant of the present. To put it another way, its planning will be even more open to errors and whatever errors are made will be even more costly than for existing nuclear technology. It is therefore even less of a socially and economically acceptable technology than today's nuclear power. (author)

Simplified High-Power Inverter

Science.gov (United States)

Edwards, D. B.; Rippel, W. E.

1984-01-01

Solid-state inverter simplified by use of single gate-turnoff device (GTO) to commutate multiple silicon controlled rectifiers (SCR's). By eliminating conventional commutation circuitry, GTO reduces cost, size and weight. GTO commutation applicable to inverters of greater than 1-kilowatt capacity. Applications include emergency power, load leveling, drives for traction and stationary polyphase motors, and photovoltaic-power conditioning.

Antares laser power amplifier

International Nuclear Information System (INIS)

Stine, R.D.; Ross, G.F.; Silvernail, C.

1979-01-01

The overall design of the Antares laser power amplifier is discussed. The power amplifier is the last stage of amplification in the 100-kJ Antares laser. In the power amplifier a single, cylindrical, grid-controlle, cold-cathode electron gun is surrounded by 12 large-aperture CO 2 electron-beam sustained laser discharge sectors. Each power amplifier will deliver 18 kJ and the six modules used in Antares will produce the required 100 kJ for delivery to the target. A large-scale interaction between optical, mechanical, and electrical disciplines is required to meet the design objectives. Significant component advances required by the power amplifier design are discussed

A CASE STUDY OF CHINA ́S WIND POWER RESOURCES

Directory of Open Access Journals (Sweden)

Xue Yanping

2013-11-01

Full Text Available At present, China is the largest energy producer and the second largest energy consumer in the world. With the increasing pressure to cut GHS emissions and to improve energy efficiency, China is now changing its traditional energy mix, mainly through consuming more renewable energy instead of fossil energy. This change has resulted in a policy adjustment which in turn boosts the utilization of the wind power resources. However, the development of the wind power resources in China is confronted with some significant challenges, such as greater installed electricity capacity than the electricity generation, greater electricity generation than the electricity transmission capacity and greater inland wind power generation than the offshore wind power generation. Therefore, the further development of China’s wind power electricity in the coming years depends largely on the ways these challenges will be addressed.

Active power control strategies for inverter-based distributed power generation adapted to grid-fault ride-through requirements

NARCIS (Netherlands)

Wang, F.; Duarte, J.L.; Hendrix, M.A.M.

2009-01-01

Distributed power generation is expected to deliver power into the grid without interruption during voltage dips. To improve system ride-through capabilities, a generalized active power control strategy is proposed for grid-interfacing inverters. Specifically, a current reference generation strategy

Market power monitoring and mitigation in the US wholesale power markets

Energy Technology Data Exchange (ETDEWEB)

Helman, Udi [Federal Energy Regulatory Commission, 888 First Street, N.E., Washington, DC 20426 (United States)

2006-05-15

Under current statutory requirements, the Federal Energy Regulatory Commission (FERC) must ensure that prices in US wholesale power markets are 'just and reasonable'. This has been interpreted by the agency and the courts as requiring the monitoring and mitigation of undue market power. This paper focuses on generation market power. Prior to electricity sector restructuring, wholesale bilateral power trading took place among vertically integrated monopoly utilities trading at the margin or between small independent producers and the utilities. Under those conditions, the authorization of trading at market prices, called 'market-based rates', required only that the generation supplier pass a simple market share screen for market power. As restructuring unfolded, and market conditions changed, there has been a steady evolution in FERC's market power mitigation rules, encompassing (a) changes in the market power assessment required for granting market-based rates and related methods for merger approval, and (b) development and refinement of new techniques for screening and mitigating offers into the organized day-ahead and real-time markets operated by Independent System Operators (ISOs) and Regional Transmission Organizations (RTOs). This paper reviews these changes to date, as FERC continues to clarify its approved rules and procedures. It also examines recent methods for quantitative market power analysis that could augment current procedures or supplant them, as found appropriate. (author)

Preliminary design of high-power wave-guide/transmission system for multimegawatt CW requirements of 100 MeV proton Linac

International Nuclear Information System (INIS)

Shrivastava, Purushottam; Wanmode, Y.D.; Hannurkar, P.R.

2002-01-01

Development of a 100 MeV CW proton Linac has been planned at CAT. This Linac will be needing CW rf power in the frequency ranges of 350 MHz and 700 MHz for its RFQ and DTL/CCDTL/SFDTL structures respectively. The power to the accelerating structures will be produced by either 1 MW CW or 250 kW CW klystron/inductive output tubes (HOM IOTs). The power needed by respective feed points in the structure is max. 250 kW which will be powered by splitting the power from 1 MW klystron/klystrode into four channels by using a wave-guide system. In case of using 250 kW tubes the power to the structures will be provided directly from each tube. Two types of wave-guide transmission system have been considered, viz WR 2300 for 350 MHz rf needs and WR 1500 for 700 MHz rf needs. The typical wave-guide system has been designed using the 1 MW CW klystron followed by wave-guide filter, dual directional coupler, high-power circulator, three 3 dB magic TEE power dividers to split the main channel into four equal channels of 250 kW each. Each individual channel has dual directional couplers, flexible wave-guide sections and high power ceramic vacuum window. The circulator and each power divider is terminated into the isolated ports by high power CW loads. Out of the four channels three channels have phase shifters. Present paper describes the technological aspects and design specifications-considerations for these stringent requirements. (author)

Overview of systems requirements for impact fusion power

International Nuclear Information System (INIS)

Williams, J.M.; Booth, L.A.; Krakowski, R.A.

1979-01-01

The development of impact fusion power reactor concepts is very limited at this time. Key systems factors in arriving at practical concepts will be conception of credible systems and subsystems which promise an acceptable overall energy balance and development of target/projectile designs and gain versus projectile energy curves which allow system design tradeoffs to be accomplished. Important system parameters will be subsystem efficiencies (particularly the accelerator), target/projectile gain as a function of target design, circulating power fraction or engineering gain, system pulse repetition rate, size/cost scaling of components, containment cavity design limits, maximum yield, minimum economical yield, minimum projectile velocity and energy, and overall economics. When more detailed conceptual designs are available, then system tradeoffs and performance optimization will be possible

Committed emissions from existing and planned power plants and asset stranding required to meet the Paris Agreement

Science.gov (United States)

Pfeiffer, Alexander; Hepburn, Cameron; Vogt-Schilb, Adrien; Caldecott, Ben

2018-05-01

Over the coming decade, the power sector is expected to invest ~7.2 trillion USD in power plants and grids globally, much of it into CO2-emitting coal and gas plants. These assets typically have long lifetimes and commit large amounts of (future) CO2 emissions. Here, we analyze the historic development of emission commitments from power plants and compare the emissions committed by current and planned plants with remaining carbon budgets. Based on this comparison we derive the likely amount of stranded assets that would be required to meet the 1.5 °C–2 °C global warming goal. We find that even though the growth of emission commitments has slowed down in recent years, currently operating generators still commit us to emissions (~300 GtCO2) above the levels compatible with the average 1.5 °C–2 °C scenario (~240 GtCO2). Furthermore, the current pipeline of power plants would add almost the same amount of additional commitments (~270 GtCO2). Even if the entire pipeline was cancelled, therefore, ~20% of global capacity would need to be stranded to meet the climate goals set out in the Paris Agreement. Our results can help companies and investors re-assess their investments in fossil-fuel power plants, and policymakers strengthen their policies to avoid further carbon lock-in.

Wind Power Utilization Guide.

Science.gov (United States)

1981-09-01

The expres- sions for the rotor torque for a Darrieus machine can be found in Reference 4.16. The Darrieus wind turbine offers the following... turbine generators, wind -driven turbines , power conditioning, wind power, energy conservation, windmills, economic ana \\sis. 20 ABS 1"ACT (Conti,on... turbines , power conditioning requirements, siting requirements, and the economics of wind power under different conditions. Three examples are given to

Emerging Changes in the Worldwide Power Sector: The Assets of Thermal Power

Energy Technology Data Exchange (ETDEWEB)

Moliere, Michel; Girardot, Amelie; Jones, Robert M.

2007-07-01

In forthcoming decades we will see major changes in the landscape of the worldwide power sector as CO2 management and incipient hydrocarbon scarcity exert their increasing influence. The power generation community must be prepared to satisfy a particularly complex and challenging set of requirements. These issues include curbing CO2 emissions, coping with surging primary energy prices, and compliance with regional and local emissions requirements such as SOx and NOx-while maintaining maximum efficiency. In this context, as confirmed by International Energy Agency forecasts, thermal power will maintain a prominent position in overall power generation since it enables the large capacity additions required in emerging countries. Thanks to their reliable assets (such as energy efficiency and environment) gas turbine-based power systems, including Gas Turbine Combined Cycles (GTCC) and Combined Heat & Power (CHP), will continue to be major contributors to worldwide power generation. However, evolving changes in the spectrum of fuels will create an additional challenge for power generation equipment manufacturers-requiring innovative technologies in fuel processing, combustion, and emission controls to address these needs. This paper reviews the factors underlining the changing power generation environment worldwide, including the increasing scarcity of conventional fuels and the growing interest in biofuels and hydrogen. Insights will be offered into various technologies needed to support the growing need for increased fuel flexibility.

Collection and evalution of abnormal occurrences in German nuclear power plants

International Nuclear Information System (INIS)

Hoffmeister

1976-01-01

The systematic consideration of operating experiences which must be recorded, collected and evaluated, is important for the realisation of the aim of greater safety in nuclear power stations. Since commissioning of the first nuclear power stations in West Germany all significant events were communicated to the 'Laender' authorities responsible for controlling compliance with the licensing requirements. The evaluation of these events assured that the necessary consequences were carried out to prevent any recurrence. A systematic consideration of the operating experiences, however, was missing; therefore our institute was made responsible by the Federal Ministry of the Interior with the agreement of the 'Laender' authorities to record, collect and evaluate in accordance with reporting criteria and a classification system related to safety relevance. (orig./RW) [de

Real-time impact of power balancing on power system operation with large scale integration of wind power

DEFF Research Database (Denmark)

Basit, Abdul; Hansen, Anca Daniela; Sørensen, Poul Ejnar

2017-01-01

Highly wind power integrated power system requires continuous active power regulation to tackle the power imbalances resulting from the wind power forecast errors. The active power balance is maintained in real-time with the automatic generation control and also from the control room, where...... power system model. The power system model takes the hour-ahead regulating power plan from power balancing model and the generation and power exchange capacities for the year 2020 into account. The real-time impact of power balancing in a highly wind power integrated power system is assessed...

COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE

International Nuclear Information System (INIS)

Colarusso, Angela; Crowe, Bruce; Cochran, John R.

2003-01-01

Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance

Thermal neutron measurement using the instrumented test bundle and assessment of maximum linear power in HANARO

Energy Technology Data Exchange (ETDEWEB)

Lee, C. S.; Seo, C. K.; Lee, B. C.; Kim, H. N.; Kang, B. W. [KAERI, Taejon (Korea, Republic of)

2000-10-01

The HANARO fuel, U{sub 3}Si-Al, has been developed by AECL and tested in NRU reactor. Due to the lack of the data performed under the high power, the repetitive conduct of the irradiation test was required under the power greater than 108kW/m, which is the estimated maximum linear power in the design stage. Accordingly, the instrumented test bundle with SPND(Self Powered Neutron Detector) was fabricated and its irradiation test was performed in IR2 of HANARO. The measured thermal neutron flux with SPND is compared with calculation results by HANAFMS(HANARO Fuel Management System). The difference in the measured and calculated thermal flux values are below {+-}11% and the accuracy of the linear power predicted by HANAFMS is consequently accompanied. Therefore, it is believed that the maximum linear power above 120kW/m is achieved during the irradiation test of the test bundle.

Space Power Free-Piston Stirling Engine Scaling Study

Science.gov (United States)

Jones, D.

1989-01-01

The design feasibility study is documented of a single cylinder, free piston Stirling engine/linear alternator (FPSE/LA) power module generating 150 kW-electric (kW sub e), and the determination of the module's maximum feasible power level. The power module configuration was specified to be a single cylinder (single piston, single displacer) FPSE/LA, with tuning capacitors if required. The design requirements were as follows: (1) Maximum electrical power output; (2) Power module thermal efficiency equal to or greater than 20 percent at a specific mass of 5 to 8 kg/kW(sub e); (3) Heater wall temperature/cooler wall temperature = 1050 K/525 K; (4) Sodium heat-pipe heat transport system, pumped loop NaK (sodium-potassium eutectic mixture) rejection system; (5) Maximum power module vibration amplitude = 0.0038 cm; and (6) Design life = 7 years (60,000 hr). The results show that a single cylinder FPSE/LA is capable of meeting program goals and has attractive scaling attributes over the power range from 25 to 150 kW(sub e). Scaling beyond the 150 kW(sub e) power level, the power module efficiency falls and the power module specific mass reaches 10 kg/kW(sub e) at a power output of 500 kW(sub e). A discussion of scaling rules for the engine, alternator, and heat transport systems is presented, along with a detailed description of the conceptual design of a 150 kW(sub e) power module that meets the requirements. Included is a discussion of the design of a dynamic balance system. A parametric study of power module performance conducted over the power output range of 25 to 150 kW(sub e) for temperature ratios of 1.7, 2.0, 2.5, and 3.0 is presented and discussed. The results show that as the temperature ratio decreases, the efficiency falls and specific mass increases. At a temperature ratio of 1.7, the 150 kW(sub e) power module cannot satisfy both efficiency and specific mass goals. As the power level increases from 25 to 150 kW(sub e) at a fixed temperature ratio, power

Power requirements and battery life measurement for wireless transmission between two nodes in different mediums

Directory of Open Access Journals (Sweden)

Radouane Karli

2017-06-01

Full Text Available One of the most important roles of the wireless sensor networks (WSN is to avoid wiring costs, be self-sustainable and be able to function for several years. However, due to the slow progress in battery technology, power continues to be a limited resource in wireless sensor communication and electric energy storage remains to be an important issue. On the other hand, if batteries must be replaced often, many remote sensing applications may become impractical. Therefore, batteries with long life on the order of several years are needed. This paper is an extension of work originally presented in The 5th International Conference on Electronic Devices, Systems and Applications to investigate further the power requirements for wireless data transfer between two nodes using batteries with different capacities (55 mAh, 550 mAh and 5500 mAh. In particular, the effect of a propagation medium such as air, distilled water and engine oil on the wireless communication inside a one meter long metallic pipe was investigated. Our first result shows a successful transmission of wireless signal through air, distilled water and oil medium with very low transmission losses. The second result shows that an increase in the battery capacity will increase the two-node wireless sensor operation time even in different propagation medium. This result can be used to determine the required battery capacity for extending the WSN operation time.

Rationale for nonlinear dose response functions of power greater or less than one

International Nuclear Information System (INIS)

Baum, J.W.

1977-08-01

Risk estimates and radiation protection standards are generally made using a nonthreshold premise and linear extrapolations from existing data to estimate biological radiation effects at lower doses and at lower dose rates. This seems reasonable in light of the variety of shapes of dose-effect relations which have been observed both in animal studies and in human epidemiological studies. An unexplained observation in several studies was a response which followed a power function of dose with exponent less than one. One explanation offered for this type of response in humans was a postulated population of heterogeneous sensitivity. An alternate, though related, way of considering this question is in terms of multiple-stresses, and this postulate is discussed

Reactor power control device

International Nuclear Information System (INIS)

Doi, Kazuyori.

1981-01-01

Purpose: To automatically control the BWR type reactor power by simple and short-time searching the load pattern nearest to the required pattern at a nuclear power plant side. Constitution: The reactor power is automatically regulated by periodical modifying of coefficients fitting to a reactor core model, according as a required load pattern. When a load requirement pattern is given, a simulator estimates the total power change and the axial power distribution change from a xenon density change output calculated by a xenon dynamic characteristic estimating device, and a load pattern capable of being realized is searched. The amount to be recirculated is controlled on the basis of the load patteren thus searched, and the operation of the BWR type reactor is automatically controlled at the side of the nuclear power plant. (Kamimura, M.)

Dynamic-energetic balance of agricultural tractors: active systems for the measurement of the power requirements in static tests and under field conditions

Directory of Open Access Journals (Sweden)

Daniele Pochi

2013-09-01

Full Text Available Modern tractors are characterized by the introduction of devices designed to increase the operative performances of the machines, such as systems for monitoring and controlling various functions (through a massive use of electronics and hydraulics, or deputed to improve the comfort of the driver (paying more attention to ergonomics, air-conditioning, noise and vibration. Such devices need energy to be operated, affecting the energetic balance of the tractor. In this context, the availability of suitable methodologies and instrumental systems could be useful to provide objective, accurate and reliable measurements of the performances of the tractors under different conditions, also considering the power requirements from ancillary services and/or simulating the coupling with operating machines. The tests on the performances of tractors are now made using different methods, including the trial codes issued by the OECD Codes. Beyond their undoubted validity, they fix standard test conditions that often do not adequately represent the operative reality, so that, much remains to investigate on the actual performances provided by the tractors. From this point of view and with reference to fixed point tests, a test bench was developed for the measurement of the power required by various devices, such as transmission and air conditioning. It was used in experimental tests on a tracked tractor and on a wheeled tractor, aimed at validating the test device, measuring the power absorption related to the rotational speed of the organs of propulsion and to the characteristics curves, in order to quantify the power drawn by the transmission and by the air conditioning and assess the residual power for other tractor functions. As to field conditions, a study is being conducted at CRA-ING, within the project PTO (Mi.P.A.A.F., to develop a mobile test bench aimed at evaluating the power required by different operations, such as self displacement, traction, use of

Evaluation of a microwave high-power reception-conversion array for wireless power transmission

Science.gov (United States)

Dickinson, R. M.

1975-01-01

Initial performance tests of a 24-sq m area array of rectenna elements are presented. The array is used as the receiving portion of a wireless microwave power transmission engineering verification test system. The transmitting antenna was located at a range of 1.54 km. Output dc voltage and power, input RF power, efficiency, and operating temperatures were obtained for a variety of dc load and RF incident power levels at 2388 MHz. Incident peak RF intensities of up to 170 mW/sq cm yielded up to 30.4 kW of dc output power. The highest derived collection-conversion efficiency of the array was greater than 80 percent.

Ground Shock Resistant of Buried Nuclear Power Plant Facility

International Nuclear Information System (INIS)

Ornai, D.; Adar, A.; Gal, E.

2014-01-01

Nuclear Power Plant (NPP) might be subjected to hostile attacks such as Earth Penetrating Weapons (EPW) that carry explosive charges. Explosions of these weapons near buried NPP facility might cause collapse, breaching, spalling, deflection, shear, rigid body motion (depending upon the foundations), and in-structure shock. The occupants and the equipment in the buried facilities are exposed to the in-structure motions, and if they are greater than their fragility values than occupants might be wounded or killed and the equipment might be damaged, unless protective measures will be applied. NPP critical equipment such as pumps are vital for the normal safe operation since it requires constant water circulation between the nuclear reactor and the cooling system, including in case of an immediate shut down. This paper presents analytical- semi empirical formulation and analysis of the explosion of a penetrating weapon with a warhead of 100kgs TNT (Trinitrotoluene) that creates ground shock effect on underground NPP structure containing equipment, such as a typical pump. If the in-structure spectral shock is greater than the pump fragility values than protective measures are required, otherwise a real danger to the NPP safety might occur

Requirements and criteria for choosing sites suitable for the construction of nuclear installations and power stations

International Nuclear Information System (INIS)

1978-05-01

The present document explains the selection criteria for areas in Italy suitable for the installation of nuclear power stations to be included in the 'National Site Map' provided for in Section 23 of Act No 393 of 2 August 1975. It represents the results of a thorough investigation into the various aspects of the problem of siting nuclear power stations, at the present stage of technology, taking into account the effect of the installations on the environment and the effect of the environment on the installations. The essential aim is to demonstrate that the requirements derived from these analyses, and on which there was full consultation with the other controlling bodies of European countries (in particular, France, Great Britain and West Germany) ensure the optimum choice of areas from the point of view of safety and public health. (author)

Power control of the Angra-2 Nuclear Power Plant

International Nuclear Information System (INIS)

Souza Mendes, J.E. de

1986-01-01

The systems for the power control of the Nuclear Power Plant Angra 2 have a high degree of automation so that few operator actions are required during power operation. The power control strategy and the operation principles of the control systems, here presented, make possible a great flexibility of the Plant operation. (Author) [pt

Assessment of Power Potential of Tidal Currents and Impacts of Power Extraction on Flow Conditions in Indonesia

Science.gov (United States)

Orhan, Kadir; Mayerle, Roberto

2017-04-01

Climate change is an urgent and potentially irreversible threat to human societies and the planet and thus requires an effective and appropriate response, with a view to accelerating the reduction of global greenhouse gas emissions. At this point, a worldwide shift to renewable energy is crucial. In this study, a methodology comprising of the estimates of power yield, evaluation of the effects of power extraction on flow conditions, and near-field investigations to deliver wake characteristics, recovery and interactions is described and applied to several straits in Indonesia. Site selection is done with high-resolution, three-dimensional flow models providing sufficient spatiotemporal coverage. Much attention has been given to the meteorological forcing, and conditions at the open sea boundaries to adequately capture the density gradients and flow fields. Model verifications using tidal records show excellent agreement. Sites with adequate depth for the energy conversion using horizontal axis tidal turbines, average kinetic power density greater than 0.5 kW/m2, and surface area larger than 0.5km2 are defined as energy hotspots. Spatial variation of the average extractable electric power is determined, and annual tidal energy resource is estimated for the straits in question. The results showed that the potential for tidal power generation in Indonesia is likely to exceed previous predictions reaching around 4,800MW. Models with higher resolutions have been developed to assess the impacts of devices on flow conditions and to resolve near-field turbine wakes in greater detail. The energy is assumed to be removed uniformly by sub-grid scale arrays of turbines. An additional drag force resulting in dissipation of the pre-existing kinetic power from 10% to 60% within a flow cross-section is introduced to capture the impacts. k-ɛ model, which is a second order turbulence closure model is selected to involve the effects of the turbulent kinetic energy and turbulent

Man as a protective barrier in nuclear power technology: the requirements, viewed by the Federal Minister for Home Affairs

International Nuclear Information System (INIS)

Fechner, J.B.

1981-06-01

Evaluation of nuclear power plant incidents frequently reveals man as a major element of risk. Yet, in a nuclear power plant man has the function of an important protective barrier, either by maintaining the plant, by detecting and limiting faults or incidents, or by taking proper measures in accidents. This is true despite, or perhaps because of, the high degree of plant automation. For this reason, it is indispensable that a high level of engineered plant safeguards be accompanied by a minimum of faults contributed by human action. This implies that the staff and their working conditions must meet the same stringent safety requirements as the nuclear power plant proper. Reactor manufacturers, nuclear power plant operators and the responsible authorities try to optimize this human contribution. The Federal Ministry of the Interior, through its Special Technical Guidelines and its continuation training measures, occupies an important position in this respect. Further measures and ordinances are being prepared by that Ministry

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)

Greater power and computational efficiency for kernel-based association testing of sets of genetic variants.

Science.gov (United States)

Lippert, Christoph; Xiang, Jing; Horta, Danilo; Widmer, Christian; Kadie, Carl; Heckerman, David; Listgarten, Jennifer

2014-11-15

Set-based variance component tests have been identified as a way to increase power in association studies by aggregating weak individual effects. However, the choice of test statistic has been largely ignored even though it may play an important role in obtaining optimal power. We compared a standard statistical test-a score test-with a recently developed likelihood ratio (LR) test. Further, when correction for hidden structure is needed, or gene-gene interactions are sought, state-of-the art algorithms for both the score and LR tests can be computationally impractical. Thus we develop new computationally efficient methods. After reviewing theoretical differences in performance between the score and LR tests, we find empirically on real data that the LR test generally has more power. In particular, on 15 of 17 real datasets, the LR test yielded at least as many associations as the score test-up to 23 more associations-whereas the score test yielded at most one more association than the LR test in the two remaining datasets. On synthetic data, we find that the LR test yielded up to 12% more associations, consistent with our results on real data, but also observe a regime of extremely small signal where the score test yielded up to 25% more associations than the LR test, consistent with theory. Finally, our computational speedups now enable (i) efficient LR testing when the background kernel is full rank, and (ii) efficient score testing when the background kernel changes with each test, as for gene-gene interaction tests. The latter yielded a factor of 2000 speedup on a cohort of size 13 500. Software available at http://research.microsoft.com/en-us/um/redmond/projects/MSCompBio/Fastlmm/. heckerma@microsoft.com Supplementary data are available at Bioinformatics online. © The Author 2014. Published by Oxford University Press.

LHC Power Distribution

CERN Document Server

Pedersen, J

1999-01-01

The power distribution for the LHC machine and its experiments will be realised making extensive use of the existing infrastructure for the LEP. The overall power requirement is approximately the same, about 125 MW. The load distribution will however change. The even points will loose in importance and the points 1 and 5 will, due to the installation of ATLAS and CMS, gain. A thorough reorganisation of the 18 kV distribution will thus be necessary. Due to the important cryogenic installations required for the LHC, the 3.3 kV distribution system, supplying mainly cryogenic compressors, will be extended with a number of new substations. The important number of new surface buildings, underground caverns and other underground structures all will receive general service installations: Lighting and power. The new injection tunnels will require complete installations: A.C. supplies for the power converters and for general service, and D.C. cabling for the magnets of the beam line. Special safe power installations ar...

Wind farm - A power source in future power systems

DEFF Research Database (Denmark)

Chen, Zhe; Blaabjerg, Frede

2009-01-01

wind turbines and wind farms, and then introduces the wind power development and wind farms. An optimization platform for designing electrical systems of offshore wind farms is briefed. The major issues related to the grid connection requirements and the operation of wind turbines/farms in power......The paper describes modern wind power systems, introduces the issues of large penetration of wind power into power systems, and discusses the possible methods of making wind turbines/farms act as a power source, like conventional power plants in power systems. Firstly, the paper describes modern...... systems are illustrated....

QA manpower requirement for nuclear power plants

International Nuclear Information System (INIS)

Link, M.

1980-01-01

To ensure the quality of the plant, QA activities are to be performed by the owner, the main contractor, the subcontractors and the Licensing Authority. The responsibilities of the QA-personnel of these organizations comprise as a minimum the control of the quality assurance systems and the proof of the quality requirements. Numbers of the required QA-personnel, designated for different tasks and recommended educational levels and professional qualifications will be given. (orig./RW)

Autonomously managed electrical power systems

Science.gov (United States)

Callis, Charles P.

1986-01-01

The electric power systems for future spacecraft such as the Space Station will necessarily be more sophisticated and will exhibit more nearly autonomous operation than earlier spacecraft. These new power systems will be more reliable and flexible than their predecessors offering greater utility to the users. Automation approaches implemented on various power system breadboards are investigated. These breadboards include the Hubble Space Telescope power system test bed, the Common Module Power Management and Distribution system breadboard, the Autonomusly Managed Power System (AMPS) breadboard, and the 20 kilohertz power system breadboard. Particular attention is given to the AMPS breadboard. Future plans for these breadboards including the employment of artificial intelligence techniques are addressed.

Review of the State-of-the-Art in Power Electronics Suitable for 10-KW Military Power Systems

Energy Technology Data Exchange (ETDEWEB)

Staunton, R.H.

2003-12-19

The purpose of this report is to document the technological opportunities of integrating power electronics-based inverters into a TEP system, primarily in the 10-kW size range. The proposed enhancement offers potential advantages in weight reduction, improved efficiency, better performance in a wider range of generator operating conditions, greater versatility and adaptability, and adequate reliability. In order to obtain strong assurance of the availability of inverters that meet required performance and reliability levels, a market survey was performed. The survey obtained positive responses from several manufacturers in the motor drive and distributed generation industries. This study also includes technology reviews and assessments relating to circuit topologies, reliability issues, vulnerability to pulses of electromagnetic energy, potential improvements in semiconductor materials, and potential performance improvement through cryogenics.

Liquid Wall Options for Tritium-Lean Fast Ignition Inertial Fusion Energy Power Plants

International Nuclear Information System (INIS)

Reyes, S.; Schmitt, R.C.; Latkowski, J.F.; Durbin, S.G.' Sanz, J.

2002-01-01

In an inertial fusion energy (FE) thick-liquid chamber design such as HYLEE-II, a molten-salt is used to attenuate neutrons and protect the chamber structures from radiation damage. In the case of a fast ignition inertial fusion system, advanced targets have been proposed that may be self-sufficient in terms of tritium breeding (i.e., the amount of tritium bred in target exceeds the amount burned). This aspect allows for greater freedom when selecting a liquid for the protective blanket, given that lithium-bearing compounds are no longer required. The present work assesses the characteristics of many single, binary, and ternary molten-salts using the NIST Properties of Molten Salts Database. As an initial screening, salts were evaluated for their safety and environmental (S and E) characteristics, which included an assessment of waste disposal rating, contact dose, and radioactive afterheat. Salts that passed the S and E criteria were then evaluated for required pumping power. The pumping power was calculated using three components: velocity head losses, frictional losses, and lifting power. The results of the assessment are used to identify those molten-salts that are suitable for potential liquid-chamber fast-ignition IFE concepts, from both the S and E and pumping power perspective. Recommendations for further analysis are also made

Power source device for thermonuclear device

International Nuclear Information System (INIS)

Ozaki, Akira.

1992-01-01

The present invention provides a small sized and economical power source device for a thermonuclear device. That is, the device comprises a conversion device having a rated power determined by a power required during a plasma current excitation period and a conversion device having a rated power determined by a power required during a plasma current maintaining period, connected in series to each other. Then, for the former conversion device, power is supplied from an electric power generator and, for the latter, power is supplied from a power system. With such a constitution, during the plasma electric current maintaining period for substantially continuous operation, it is possible to conduct bypassing paired operation for the former conversion device while the electric power generator is put under no load. Further, since a short period rated power may be suffice for the former conversion device and the electric power generator having the great rated power required for the plasma electric current excitation period, they can be reduced in the size and made economical. On the other hand, since the power required for the plasma current maintaining period is relatively small, the capacity of the continuous rated conversion device may be small, and the power can be received from the power system. (I.S.)

Radar Waveform Pulse Analysis Measurement System for High-Power GaN Amplifiers

Science.gov (United States)

Thrivikraman, Tushar; Perkovic-Martin, Dragana; Jenabi, Masud; Hoffman, James

2012-01-01

This work presents a measurement system to characterize the pulsed response of high-power GaN amplifiers for use in space-based SAR platforms that require very strict amplitude and phase stability. The measurement system is able to record and analyze data on three different time scales: fast, slow, and long, which allows for greater detail of the mechanisms that impact amplitude and phase stability. The system is fully automated through MATLAB, which offers both instrument control capability and in-situ data processing. To validate this system, a high-power GaN HEMT amplifier operated in saturation was characterized. The fast time results show that variations to the amplitude and phase are correlated to DC supply transients, while long time characteristics are correlated to temperature changes.

The injection equipment of future high-speed DI diesel engines with respect to power and pollution requirements

Energy Technology Data Exchange (ETDEWEB)

Dolenc, A. (Monobloc Dieselmotoren GmbH, Vienna (AT))

1990-01-01

The development of high specific output DI diesel engines started at the low-speed end some 50 years ago primarily for marine and traction applications. Movement towards the high-speed end has been slow but steady with the majority of truck engines being very conservatively rated. There has been recent major effort on the automotive car and light commercial vehicle diesel application leading to lightweight DI diesel engines with an engine speed of 4000-5000 r/min and a rated power of 50 kW/litre displacement. These are expected to be on the market in a short period of time. The key point of this development has been the injection equipment including combustion control. In this area the use of modulated injection has the possibility of solving power and pollution requirements. (author).

Lessons from American-German nuclear power plant construction. Quality, safety and costs of an attempt to integrate American and German nuclear power plant technology

International Nuclear Information System (INIS)

Buchwald, K.

1979-05-01

The 1300 MW nuclear power plant at Muelheim-Kaerlich has been under construction since the beginning of 1975. It is being equipped with a pressurised water reactor which has been adapted to the German client's requirements and German licensing practice, based on a license held by Babcock and Wilcox USA (B and W). The problems which have arisen in making this adaptation are the result of different requirements in the USA and the Federal Republic of Germany which make it very difficult to integrate the two technologies. Full integration will almost certainly be impossible, but integration to the widest possible extent is important because it might mean both greater safety and reduced costs. In this article it is intended to show where the problems of integration lie and how they might perhaps be overcome. (author)

Main phases of siting for nuclear power plants with review of required investigations

International Nuclear Information System (INIS)

Malbasa, N.

1984-01-01

The purpose of the article is a short description of the main phases in the process of siting for nuclear power plants as interpreted and applied by the Institut za elektroprivredu, Zagreb in the screening, comparison and evaluation of the sites for NPPs in the SR of Croatia. The scope and purpose, as well as review of required data and investigations for each particular phase are given. Common used methods for the comparison of sites are described and example of rejection criteria applicable for early phases of the siting is proposed. It is given a list of the most important activities which detailed analysis id indispensable for ending of the evaluation and getting a site permit from the regulatory body. A legal and regulatory basis for carrying out the siting process is also described. (author)

Virginia power nuclear power station engineer training program

International Nuclear Information System (INIS)

Williams, T.M.; Haberstroh-Timpano, S.

1987-01-01

In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

Consideration of the legal system required for achievement of current nuclear power plant construction programmes

International Nuclear Information System (INIS)

Castellon Fernandez, E.; Forum Atomico Espanol, Madrid)

1976-01-01

The extensive nuclear power plant construction programmes currently in progress in western countries require updating of the legislation in force in this field, especially as regards the following: acquisition of the sites necessary by means of a national planning programme of available sites; simplification of formalities concerning issuance of administrative licenses; revision of the principle of absolute and exclusive liability of the nuclear operator which forms the basis of the third party liability system for nuclear damage; radioactive waste management and decommissioning of nuclear plants. Furthermore, this new legislation should be harmonized between the different countries concerned. (N.E.A.) [fr

Electrical power systems for Space Station

Science.gov (United States)

Simon, W. E.

1984-01-01

Major challenges in power system development are described. Evolutionary growth, operational lifetime, and other design requirements are discussed. A pictorial view of weight-optimized power system applications shows which systems are best for missions of various lengths and required power level. Following definition of the major elements of the electrical power system, an overview of element options and a brief technology assessment are presented. Selected trade-study results show end-to-end system efficiencies, required photovoltaic power capability as a function of energy storage system efficiency, and comparisons with other systems such as a solar dynamic power system.

An economically viable space power relay system

Science.gov (United States)

Bekey, Ivan; Boudreault, Richard

1999-09-01

This paper describes and analyzes the economics of a power relay system that takes advantage of recent technological advances to implement a system that is economically viable. A series of power relay systems are described and analyzed which transport power ranging from 1,250 megawatts to 5,000 megawatts, and distribute it to receiving sites at transcontinental distances. Two classes of systems are discussed—those with a single reflector and delivering all the power to a single rectenna, and a second type which has multiple reflectors and distributes it to 10 rectenna sites, sharing power among them. It is shown that when offering electricity at prices competitive to those prevalent in developed cities in the US that a low IRR is inevitable, and economic feasibility of a business is unlikely. However, when the target market is Japan where the prevalent electricity prices are much greater, that an IRR exceeding 65% is readily attainable. This is extremely attractive to potential investors, making capitalization of a venture likely. The paper shows that the capital investment required for the system can be less than 1 per installed watt, contributing less than 0.02 /KW-hr to the cost of energy provision. Since selling prices in feasible regions range from 0.18 to over 030 $/kW-hr, these costs are but a small fraction of the operating expenses. Thus a very large IRR is possible for such a business.

Power distribution, the environment, and public health. A state-level analysis

International Nuclear Information System (INIS)

Boyce, James K.; Klemer, Andrew R.; Templet, Paul H.; Willis, Cleve E.

1999-01-01

This paper examines relationships among power distribution, the environment, and public health by means of a cross-sectional analysis of the 50 US states. A measure of inter-state variations in power distribution is derived from data on voter participation, tax fairness, Medicaid access, and educational attainment. We develop and estimate a recursive model linking the distribution of power to environmental policy, environmental stress, and public health. The results support the hypothesis that greater power inequality leads to weaker environmental policies, which in turn lead to greater environmental degradation and to adverse public health outcomes

Power distribution, the environment, and public health. A state-level analysis

Energy Technology Data Exchange (ETDEWEB)

Boyce, James K. [Department of Economics, University of Massachusetts, Amherst, MA 01003 (United States); Klemer, Andrew R. [Department of Biology, University of Minnesota, Duluth, MN (United States); Templet, Paul H. [Institute of Environmental Studies, Louisiana State University, Baton Rouge, LA (United States); Willis, Cleve E. [Department of Resource Economics, University of Massachusetts, Amherst, MA 01003 (United States)

1999-04-15

This paper examines relationships among power distribution, the environment, and public health by means of a cross-sectional analysis of the 50 US states. A measure of inter-state variations in power distribution is derived from data on voter participation, tax fairness, Medicaid access, and educational attainment. We develop and estimate a recursive model linking the distribution of power to environmental policy, environmental stress, and public health. The results support the hypothesis that greater power inequality leads to weaker environmental policies, which in turn lead to greater environmental degradation and to adverse public health outcomes.

Power distribution, the environment, and public health. A state-level analysis

Energy Technology Data Exchange (ETDEWEB)

Boyce, James K. [Department of Economics, University of Massachusetts, Amherst, MA 01003 (United States); Klemer, Andrew R. [Department of Biology, University of Minnesota, Duluth, MN (United States); Templet, Paul H. [Institute of Environmental Studies, Louisiana State University, Baton Rouge, LA (United States); Willis, Cleve E. [Department of Resource Economics, University of Massachusetts, Amherst, MA 01003 (United States)

1999-04-15

This paper examines relationships among power distribution, the environment, and public health by means of a cross-sectional analysis of the 50 US states. A measure of inter-state variations in power distribution is derived from data on voter participation, tax fairness, Medicaid access, and educational attainment. We develop and estimate a recursive model linking the distribution of power to environmental policy, environmental stress, and public health. The results support the hypothesis that greater power inequality leads to weaker environmental policies, which in turn lead to greater environmental degradation and to adverse public health outcomes

Recent applications of microprocessor-based instruments in nuclear power stations

International Nuclear Information System (INIS)

Cash, N.R.; Dennis, U.E.

1988-01-01

The incorporation of microprocessors in the design of nuclear power plant instrumentation has led to levels of measurement and control not available previously. In addition to the expected expansion of functional (system) capability, numerous desirable features now are possible. The added ability to both self-calibrate and perform compensation algorithms has led to dramatic improvements in accuracies, response times, and noise rejection. Automated performance checking and self-testing simplify troubleshooting and required periodic surveillance. Alphanumeric displays allow both menu-driven operation and user-prompting, which, in turn, contribute to mistake avoidance. New features of these microprocessor-based instruments are of specific benefit in nuclear power reactors, were safety is of prime concern. Greater reliability and accuracy can be provided. Shortened calibration, surveillance, and repair times reduce the exposure to unnecessary challenges of the plant's protection systems that can arise from spurious noise signals

Multi-port power router and its impact on resilient power grid systems

Science.gov (United States)

Kado, Yuichi; Iwatsuki, Katsumi; Wada, Keiji

2016-02-01

We propose a Y-configuration power router as a unit cell to easily construct a power delivery system that can meet many types of user requirements. The Y-configuration power router controls the direction and magnitude of power flow among three ports regardless of DC and AC. We constructed a prototype three-way isolated DC/DC converter that is the core unit of the Y-configuration power router and tested the power flow control operation. Experimental results revealed that our methodology based on the governing equation was appropriate for the power flow control of the three-way DC/DC converter. In addition, the hexagonal distribution network composed of the power routers has the ability to easily interchange electric power between autonomous microgrid cells. We also explored the requirements for communication between energy routers to achieve dynamic adjustments of energy flow in a coordinated manner and its impact on resilient power grid systems.

Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program

Energy Technology Data Exchange (ETDEWEB)

Tyacke, M.

1993-08-01

This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.

Defence in depth for electric power supplies in Indian nuclear power plants

International Nuclear Information System (INIS)

Gupta, S.K.; Srivasista, K.; Solanki, R.B.

2009-01-01

The purpose of electric power supply system in a nuclear power plant is to supply and distribute reliable electric power to safety related systems and systems important to safety in various forms, arrangements and combinations of redundancy and diversity in order to perform safety functions required during operational states and design basis events (DBE) such as shutting down the reactor, maintaining the reactor in safe shutdown state, containment isolation and reactor core cooling preventing significant release of radioactive material to the environment. Hence the design basis of electric power supply systems includes identification of DBE that require power supplies, adequacy of redundancy and diversity, environmental conditions to which electric equipment are qualified, identification of loads requiring interrupted and uninterrupted power supplies, time sequence in which emergency loads are to be supplied in case of interruption, provisions for maintaining and testing, consideration for minimum duration capability of emergency power supplies during station blackout etc. Based on operation experience, results of probability safety assessment and certain weaknesses noticed in defence in depth of electric power supply systems, several continuous design improvements have been made in Indian nuclear power plants during operating phase and life extension. Instituting various tests during initial commissioning, subsequent operation and life extension has ensured high standards of performance of electric power supplies. Some of these aspects are highlighted in this paper

Evolution of Onsite and Offsite Power Systems in US Nuclear Power Plants

International Nuclear Information System (INIS)

Mathew, Roy K.

2015-01-01

The AC electric power system is the source of power for station auxiliaries during normal operation and for the reactor protection system and emergency safety features during abnormal and accident conditions. Since the construction of early plants in US, the functional adequacy and requirements of the offsite power systems, safety and non safety related onsite electric power systems have changed considerably to ensure that these systems have adequate redundancy, independence, quality, maintenance and testability to support safe shutdown of the nuclear plant. The design of AC systems has evolved from a single train to multiple (up to four) redundant trains in the current evolutionary designs coupled with other auxiliary AC systems. The early plants were designed to cope with a Loss of Offsite Power (LOOP) event through the use of onsite power supplies only. However operating experience has indicated that onsite and offsite power AC power systems can fail due to natural phenomena (earthquakes, lightning strikes, fires, geomagnetic storms, tsunamis, etc.) or operational abnormalities such as loss of a single phase, switching surges or human error. The onsite DC systems may not be adequately sized to support plant safe shutdown over an extended period if AC power cannot be restored within a reasonable time. This paper will discuss the requirements to improve availability and reliability of offsite and onsite alternating current (AC) power sources to U.S. Nuclear Power Plants. In addition, the paper will discuss the requirements and guidance beyond design basis events. (author)

Simultaneous bilateral isolated greater trochanter fracture

Directory of Open Access Journals (Sweden)

Maruti Kambali

2013-01-01

Full Text Available A 48-year-old woman sustained simultaneous isolated bilateral greater trochanteric fracture, following a road traffic accident. The patient presented to us 1 month after the injury. She presented with complaints of pain in the left hip and inability to walk. Roentgenograms revealed displaced comminuted bilateral greater trochanter fractures. The fracture of the left greater trochanter was reduced and fixed internally using the tension band wiring technique. The greater trochanter fracture on the right side was asymptomatic and was managed conservatively. The patient regained full range of motion and use of her hips after a postoperative follow-up of 6 months. Isolated fractures of the greater trochanter are unusual injuries. Because of their relative rarity and the unsettled controversy regarding their etiology and pathogenesis, several methods of treatment have been advocated. Furthermore, the reports of this particular type of injury are not plentiful and the average textbook coverage afforded to this entity is limited. In our study we discuss the mechanism of injury and the various treatment options available.

The role of elastic energy in activities with high force and power requirements: a brief review.

Science.gov (United States)

Wilson, Jacob M; Flanagan, Eamonn P

2008-09-01

The purpose of this article is to provide strength and conditioning practitioners with an understanding of the role of elastic energy in activities with high force and power requirements. Specifically, the article covers 1) the nature of elasticity and its application to human participants, 2) the role of elastic energy in activities requiring a stretch-shorten cycle such as the vertical jump, 3) the role of muscular stiffness in athletic performance, 4) the control of muscular stiffness through feedforward and feedback mechanisms, and 5) factors affecting muscular stiffness. Finally, practical applications are provided. In this section, it is suggested that the storage and reuse of elastic energy is optimized at relatively higher levels of stiffness. Because stiffness decreases as fatigue ensues as well as with stretching before an event, the article emphasizes the need for proper preparation phases in a periodized cycle and the avoidance of long static stretches before high-force activities. The importance of teaching athletes to transition from eccentric to concentric movements with minimal time delays is also proposed due to the finding that time delays appear to decrease the reuse of elastic energy. In addition to teaching within the criterion tasks, evidence is provided that minimizing transitions in plyometric training, a technique demonstrated to increase musculotendinous stiffness, can optimize power output in explosive movements. Finally, evidence is provided that training and teaching programs designed to optimize muscular stiffness may protect athletes against sports-related injuries.